PROPOSED ORDER OF
DEPARTMENT OF HEALTH SERVICES
TO ADOPT PERMANENT RULES
The Wisconsin Department of Health Services proposes an order
to repeal
DHS 157.09 (1) (a) 8.
a.; DHS 157.43 (2) (b); and DHS 157.83 (3) (b) 2.
b.;
to renumber
DHS 157.03 (402m); DHS 157.09 (1) (a) 8.
b., c., and d.; DHS 157.13 (10) (b); DHS 157.43 (2) (intro.) and (2) (a); and DHS 157.94 (5) (a);
to renumber and amend
DHS 157.83 (3) (b)
2.
a.; and DHS 157.85 (14) (gm) (intro.);
to amend
DHS 157.03 (84m) and Note, (198), (200) (c), (208), (221m), (404), and (419m); DHS 157.09 (1) (a) (intro.), (1) (a) 5.
a
. and b., (1) (a) 10. (intro.), (2) (c)
7.,
(2) (d) 1.
and
(e) 1.; DHS 157.11 (2) (a); DHS 157.13 (1) (h) (intro.), (1) (h) 1., (1) (i), (4) (e), (4) (f), (4) (h) 2., (10) (e) 2.;
DHS 157.15 (1) (a) 2.
and
4., (5) (a) (intro.), (5) (a) 1., (5) (a) 3., and (5) (b); DHS 157.21 (1); DHS 157. 22 (1) (e) Note, (4) (h)
2.,
(5) (d) 1.
and
Note; DHS 157.24 (1) (b); DHS 157.25 (1) (a) 1., 2.
(intro.), (1) (a) 2.
b
. and c., and (2) (a) 5.; DHS 157.44 (6) (a) 4.; DHS 157.61 (7) (a) 2.
b
, (8) (a) 1.
b., and (10) (a) and (c); DHS 157.63 (2) (b) 3.
and
(4) (c) 2.; DHS 157.67 (11) (f) and (12) (b) 3.; DHS 157.71 (8); DHS 157.72 (1) (a) 1.; DHS 157.74 (2) (b) 2., (d) 3., (2) (f), and (h) 1.
and
4.
c.; DHS 157.74 (3) (b) 2.
and
(4) (b); DHS 157.76 (11) (a); DHS 157.77 (2) (h) 1., and (i); DHS 157.78 (4) (d) 1.
and
3.,
(8) (title), and (9) (a);
DHS 157.79 (3) (c); DHS 157.80 (1) (b), (2) (a) 1., (2) (b) 4., and (2) (c); DHS 157.83 (3) (b) 1.
and
4.
d.; DHS 157.85 (3) (title), (13) (
em
)
2.
through
7., and (16) (g) 7.
d.; DHS 157.87 (1) (intro.), (3) (b) 6., and (4) (a); DHS 157.92 (2) (b) and (c) 4.; DHS 157.93 (4) (b); and DHS 157.94 (5) (d), (e), and (f), and (8);
to repeal and recreate
DHS 157.09 (1) (a) 11.
and 12.; DHS 157.10 (3); DHS 157.11 (1) (a); DHS 157.15 (5) (a) 2.;
DHS 157.76
(7)
(c);
DHS 157.87 (1) (a); DHS 157.93 (6); DHS 157.94 (3) and (6); DHS 157 Appendix A; DHS 157 Appendix B; DHS 157 Appendix E; DHS 157 Appendix H Table V; Appendix I; Appendix M; and Appendix O;
to
create
DHS 157.03 (6m), (12m) and Note, (25m), (36m), (56g) and Note, (56r) and Note, (77m), (108m), (109m), (124g), (139m), (143g), (150g), (166m), (189m) and Note, (193m), (215m), (219m), (221m) Note, (228m), (230m), (318m), (319g), (319r), (331g), (331r), (374m), (392m), (393m), and (402g); DHS 157.09 (1) (a) 13., (2) (c) 9.
through
11., (2) (g), (3); DHS 157.13 (1) (h) 3., (4) (d) 1. h., (4) (j)
5.,
(4m), (10) (b) 2.; DHS 157.15 (5) (a) 1.
e
. and f., (5) (c); DHS 157.25 (1) (d); DHS 157.33 (3) (a) 4.; DHS 157.61 (10) (d); DHS 157.74 (2) (m); DHS 157.76 (7) (d); DHS 157.78
(10);
DHS 157.80 (1) (f) 5.
and
6.;
DHS 157.84 (1) (b) 5.; DHS 157.85 (14)(gr); DHS 157.87 (1) (ag) and (
ar
), (4) (c), (d), and (e);
DHS 157.93 (4) (am); DHS 157.94 (5) (a) 2.; DHS 157
Subchapter XV; and DHS 157 Appendix U; relating to radiation protection.
RULE SUMMARY
Statute interpreted
Statutory authority
Explanation of agency authority
As specified under s.
254.34 (1)
,
Stats.,
the
department
is the state radiation control agency and is required under ss.
254.34 (1) (a)
,
254.365 (4)
, and
254.37 (3)
, Stats., to promulgate rules pertaining to the use of radiation in Wisconsin. Specifically, the
department
is required to promulgate and enforce rules pertaining to sources of ionizing radiation and for registration and licensing sources of
ionizing radiation, and enforcement as may be necessary to prohibit and prevent unnecessary radiation exposure. The
department
’s
rules for by-product material, source material, and special nuclear material are required to be in accordance with
42 USC 2021
(o) and be otherwise compatible with the requirements under
42 USC 2011
to
2114
and regulations adopted under
42 USC 2011
to
2114
.
Related statute or rule
Chapter
NR 809
incorporates the radioactivity standards for community water systems and the
exemptions and requirements
established in ss.
DHS 157.95
and
157.96
. The
department of natural resources
applies these standards to community drinking water systems.
Chapter
DHS 163
establishes requirements for identification, removal and reduction of lead-based paint hazards. Lead in paint analysis requires use of a portable device containing radioactive material which is required to be licensed under
ch.
DHS 157
. Section
DHS 157.05 (4)
also
requires any person providing training for certified lead inspectors or risk assessors to meet the training requirements of s.
DHS 163.24
(a) 1.
and
3.
and
to complete an additional
eight
hours of radiation safety training.
Chapter
462
,
Stats.,
requires
radiographers
to be licensed
and limited x-ray machine operators
to be
permitted
by the state
.
Sections
DHS 157.
74 (2) (m)
and
157.80 (2) (a) 1.
also
require
individuals operating x-ray equipment for diagnostic purposes
to
possess a current radiography license or limited x-ray machine operator’s permit from the State of Wisconsin.
Plain language analysis
Under s.
254.34 (1) (a)
and
(b)
Stats., the
d
epartment
is responsible for developing and enforcing rules, including registration and licensing of sources of ionizing radiation
,
to prohibit and prevent unnecessary radiation exposure. The
department
is also responsible for maintaining compliance with the
Agreement
Between The United States Nuclear Regulatory Commission and The State of Wisconsin for Discontinuance of Certain Commission Regulatory Authority and Responsibility Within the State Pursuant to Section 274 of the Atomic Energy Act of 1954, as Amended
(a
greement)
signed by Governor Doyle and the Nuclear Regulatory Commission (NRC)
in 2003. The a
greement
transferred regulatory authority over certain radioactive materials from the NRC to the state. Under the Agreement, the
department
is responsible for licensing and inspecting radioactive materials commonly used in medicine, industry, research and education.
The
state regulatory program
is periodically evaluated by NRC staff
.
The
Agreement
provides that the
state
will
revise the radioactive material
provisions
of
ch.
DHS 157
within
three
years of any applicable changes
to
Title10
CFR
.
Title 10 CFR
was revised in
2013
,
whereas
ch.
DHS 157
was last revised in 2010.
The
department
proposes to
revise
the radioactive material requirements in
ch.
DHS 157
in order to comply with the Agreement
.
No reasonable alternative exists to revising
provisions
in
ch.
DHS 157
pertaining to radioactive material,
because
the Agreement remains in effect.
The proposed revisions are anticipated to bring the state into compliance with the Agreement.
In addition, the
department
proposes to revise
provisions
of
ch.
DH
S 157
pertaining to x-rays
. These revisions are nece
ssary to
prohibit and prevent unnecessary radiation exposure
.
Revisions
reflect new diagnostic and therapeutic technologies,
the department’s
experience with implementing
and administering
the current rule, changes in comparable federal regulations,
suggested national
standards from the Conference of Radiation Control Program Directors,
and input provided to the
department
by an advisory group that included representatives of academic and medical facilities, radioactive materials users, x-ray users and large and small businesses.
No reasonable alternative exists to
revising
the
provisions of
ch.
DHS 157
pertaining to x-rays
, bec
ause
pursuant to
s.
254.34
, stats.,
the department
must
promulgate and enforce rules, including registration and licensing of sources of ionizing radiation, as may be necessary to prohibit and prevent
unnecessary radiation exposure.
The proposed revisions are anticipated to accomplish this purpose.
The proposed revisions to
ch.
DHS 157
accomplish the following:
Update the radiation protection and regulatory requirements for radioactive materials to
ensure c
ompatibility with current applicable regulations of the federal Nuclear Regulatory Commission (NRC) in
10 CFR Parts 19
,
20
,
31
-
37
,
39
,
40
,
70
,
71
and
150
, relating to notices, instructions and reports to workers regarding inspections and investigations
; standards for protection against radiation; general domestic licenses for byproduct material, specific domestic licenses to manufacture or transfer certain items containing byproduct material; specific domestic licenses of broad scope for byproduct material; licenses for industrial radiography and radiation safety requirements for industrial radiographic operations; physical protection
of
byproduct material; medical use of byproduct material; licenses and radiation safety requirements for irradiators; licenses and radiation safety requirements for well logging; domestic licensing of special nuclear material; packaging and transportation of radioactive material; and exemptions and continued regulatory authority in agreement states and in offshore waters.
Compatibility with current applicable regulations of the federal Food and Drug Administration (FDA) in
21 CFR Parts 900
,
1020
,
1030
, and
1040
, relating to mammography quality standards,
performance
standards for ionizing radiation emitting products; microwave and radio frequency emitting products; and light-emitting products for the protection
against
hazards
of radiation.
Codification of suggested national standards
for x-ray device imaging from the Conference of Radiation Control Program Directors in the
Suggested State Regulations for the Control of Radiation
.
Conformity
with
ch.
462
,
Stats.,
relating to licensing and the practice of radiographers and limited x-ray machine operators by removing any conflicts with
ch.
462
.
Stats.,
or rules promulgated thereunder by the radiography examining board.
C
orrect rule language based on the Department’s experience administering the current rule.
The department had initially proposed to require recording of a patient’s
radiation
dose
in the medical record for certain high dose medical procedures
as recommended by the Food and Drug Administration
.
However, based on input received from an advisory group, the department determined that this requirement is not feasible at present because existing methods for estimating patient exposure
are inadequate
.
Entities that may be affected by the proposed revisions to
ch.
DHS 157
are hospitals, academic facilities, medical clinics, dental facilities, chiropractic offices, veterinary facilities and industrial facilities that use radioactive materials or x-ray devices.
Summary of, and comparison with, existing or proposed federal regulations
Wisconsin’s Agreement with the Nuclear Regulatory Commission requires the
d
epartment to incorporate relevant changes to federal radioactive material regulations into its radiation protection rules within
three
years of the effective date of the federal regulations. The proposed changes to
ch.
DHS 157
ensure continued compatibility with new federal radioactive material regulations in 10 CFR Pts. 19, 20, 31, 33-36, 37, 39, 40, 70, 71 and 150
,
as required by s.
254.34 (1)
, Stats.
Comparison with rules in adjacent states
Illinois:
Illinois is an
a
greement
state with the Nuclear Regulatory Commission. As a result, Illinois law
in effect June 1, 2016
contains radiation protection and regulatory requirements similar to those
contained
in
ch.
DHS 157
and compatible with equivalent federal regulations in Titles 10 and 49,
C
FR
.
Iowa:
Iowa is an
a
greement
state with the Nuclear Regulatory Commission. As a result, Iowa law
in effect June 1, 2016
contains radiation protection and regulatory requirements similar to those in
ch.
DHS 157
and compatible with equivalent federal regulations in Titles 10 and 49,
CFR
.
Michigan:
Michigan is not an
a
greement state with the Nuclear Regulatory Commission.
Michigan previously declared its intent to become an
a
greement state but later decided to cease all activity toward pursuing the
a
greement.
As a result, Michigan law
in effect June 1, 2016
contain
s some
regulatory requirements similar
to
those in
ch.
DHS 157
. The Nuclear Regulatory Commission is currently responsible for regulating the majority of radioactive material use in Michigan under Titles 10 and 49,
CFR
.
Minnesota:
Minnesota is an
a
greement state with the Nuclear Regulatory Commission. Minnesota adopted new radiation protection regulations for radioactive materials effective January 1, 2005. As a result, Minnesota law
in effect June 1, 2016
contains radiation protection and regulatory requirements similar to those in
ch.
DHS 157
and compatible with equivalent federal regulations in Titles 10 and 49,
CFR
.
Summary of factual data and analytical methodologies
Th
e
d
epartment referred to all of the following to draft the proposed rules:
1. The input of an advisory
committee
that included
stakeholders
affected by the proposed rules. These included
representatives of academic and medical facilities, radioactive materials users, x-ray users
,
and large and small businesses.
2. A
n
a
greement state rule template called the “Suggested State Regulations for the Control of Radiation” (SSRCR) developed by the Conference of Radiation Control Program Directors, Inc. (CRCPD). The CRCPD is a national organization of primarily state radiation control staff that supports and represents state radiation control programs. The SSRCR is developed with the
involvement of federal radiation agencies, such as the Nuclear Regulatory Commission, the Food and Drug Administration and the Environmental Protection Agency. The SSRCR is also continually updated and used by most of the 37 existing
a
greement states to help meet federal requirements.
3.
Requirements of Titles 10, 21, and 49
CFR
; 42 USC;
Sections
254.31
to
254.45
, Stats., and the
Agreement
Between The United States Nuclear Regulatory Commission and The State of Wisconsin for Discontinuance of Certain Commission Regulatory Authority and Responsibility Within the State Pursuant to Section 274 of the Atomic Energy Act of 1954, as Amended
.
Analysis and supporting documents used to determine effect on small business
The methods specified in s.
227.114 (2)
,
Stats.,
for reducing a rule’s impact on small business
were considered
by the department
, but
have not been
adopted
in the proposed rules
because they are not feasible. Adopting the methods specified in s.
227.114 (2)
, Stats.,
would be contrary to the
state’s public policy on radiation control stated in s.
254.33
,
as well as
federal requirements,
and
the
a
greement between the state and the NRC
,
which are the basis for the proposed rule
.
T
he
department
’s
analysis
of the effect of rulemaking on small businesses regulated by
ch.
DHS 157
is therefore
confined
to proposed revisions addressing x-ray regulatory requirements.
The
department
’s
x-ray registration and inspection program, and radioactive materials licensing and inspection program, are both
entirely
supported by the annual fees authorized under s.
254.35 (3)
and s
254.365 (5)
, Stats. There are no fee increases proposed in this rule revision.
Any
fiscal impact to x-ray registrants
may stem from
proposed requirements in the following sections:
DHS 157.21
(1),
DHS
157.25
(2)
(a)
5.
,
DHS
157.74
(2)
(m),
DHS
157.77
(2)
(h)
and (i)
,
DHS
157.78
(10
),
DHS
157.80
(1)
(f)
5.
and
6.,
DHS
157.80
(2)
(a)
1., and
DHS
157.85
(14)
(
gn
)
.
The proposed requirements and the fiscal impact on small business are as follows:
DHS 157.21 (1)
:
The
department
proposes
that
any facility that
uses an
x-ray
device
designate a person in control
who is responsible for safe operation of the radiation installation. This is
already
required for licensees
who must designate a radiation safety officer
. Since
x-ray
registrants
may
designate an existing staff person
,
the
department
anticipates
minimal fiscal impact on any facility, including small business
es
.
DHS 157.25 (2) (a)
5.
:
Fluoroscopic devices are capable of generating str
o
ng radiation fields when operational. Currently, radiation monitoring is required for
any individual
working within
six
feet of operating medical fluoroscopic equipment. This requirement does not allow any exception for individuals who may need to walk briefly past the device
with minimal
exposure. As a result, the
department
proposes
to
provide flexibility to medical facilities, including small businesses, by only requiring monitoring for individuals working within
six
feet of operating fluoroscopic equipment longer than 10 minutes per week. This
is intended to
reduce the radiation monitoring costs for facilities with these devices.
DHS 157.74 (2)
(m)
:
This paragraph refers to the existing requirement in
s.
462
.02(1) (a)
, Stats.
that
any individual
who operates
x-ray equipment for diagnostic medical purposes have a current radiography license or
l
imited
x
-ray machine
o
perators permit issued by the
state.
These licenses and permits are
currently
issued by the
d
epartment
of
s
afety and
p
rofessional
s
ervices
.
The department anticipates no fiscal impact stemming from reference within DHS
157.74 (2) (m) to this existing
requirement.
DHS 157.77 (2)
(h)
and
(i)
:
These two paragraphs clarify the operator protection requirements for all types of x-ray systems, including veterinary systems
.
Specifically
,
DHS 157.77
(2)
(h)
requires
the x-ray control
to
be permanently mounted behind a protective barrier and
DHS 157.77
(2)
(i)
requires
persons within 2.7 meters (9 feet) to wear a protective apron with at least .25 mm of lead equivalence and have lead gloves of .5 mm lead equivalence if holding the animal
. There is minimal effort required to meet these requirements
,
as existing equipment may be used
. As a result, the
d
epartment anticipates minimal fiscal impact
on any facility.
DHS 157.78
(10)
:
Hand held dental x-ray units are being increasingly used in dental offices and during
public
dental events. These devices are capable of
expos
ing
patients and operators
to substantial radiation
if used inappropriately. As a result, the
department
proposes
minimum
operator training
for all personnel that operate hand
held dental x-ray units
.
This
training
must
include manufacturer
-
specific
training in
exposure control
,
operation
, use of safety devices, operator and patient protection
,
and quality control testing.
Affected entities
are given flexibility in how to provide training, which may include
in-house
(on site) training,
or training limited to the
entity’s
particular use of x-ray units
. In addition, the
department
proposes
new radiation safety requirements specific to this technology to ensure operator and public safety during use.
The
requirements
are drawn
from the
SSRCR
published by the
CRCPD
.
The
d
epartment
anticipates
that
there will be a small cost associated with the training
,
but little to no cost associa
t
ed with the radiation safety requirements.
DHS 157.80 (1) (f) 5.
and 6.
:
The
d
epartment
proposes to require that
facilities using newer
generation computed tomography
(CT)
systems
ensure that two-way verbal communication
exist
s
between
the
patient and the operator of
the device, and
that
a method
be provided
to permit
continuous observation of the patient during irradiation.
A
lthough
CT scans
can produce a
very
detailed image of
the body
from multiple x-ray images or ‘slices
,
’
radiation exposure to the patient can be very high. These devices
are used
primarily in large medical facilities.
T
he
d
epartment
anticipates
no additional
fiscal impact on facilities using these devices since
the
proposed
r
equirements are consistent
with
CRCPD suggested state regulations
and
similar requirements
that already exist in s.
DHS 157.81
.
DHS 157.80 (2) (a) 1
.:
This
provision
refers to the existing requirement in
ch
.
462
, Stats.
,
that individuals operating x-ray equipment for diagnostic medical purposes have a current radiography license or
limited x-ray machine
permit issued by the
Department
of Safety and Professional Services.
The
d
epartment
anticipates
no additional fiscal impact on
facilities using these devices.
DHS 157.85 (14) (
gn
)
:
Electronic brachytherapy is a new technology that uses small x-ray
devices
to treat cancer within the body
. The devices are capable of producing very high levels of radiation.
These devices tend to be
used
primarily in large medical facilities
and not small businesses
.
Based on input from the advisory
committee
, the department
proposes
quality control requirements for these devices to ensure safe operation.
The
d
epartment
anticipates
no additional fiscal impact on
facilities using these devices.
Effect on small business
Based on the foregoing analysis, the proposed rules are anticipated to have little to no economic impact on small businesses.
Agency contact person
Paul Schmidt, Chief
Radiation Protection Section
P.O. Box 2659
Madison, WI 53701-2659
Statement on quality of agency data
The department utilized the input of
an
advisory
committee
representing
entit
i
es affected by the proposed rules,
a rule template called the “Suggested State Regulations for the Control of Radiation” (SSRCR) developed by
the
CRCPD,
and
applicable federal regulations.
Please refer to the ‘Summary of Factual Data and Analytical Methodologies’ above
for more detail.
Place where comments are to be submitted and deadline for submission
Comments may be submitted to the agency contact person that is listed above until the deadline given in the upcoming notice of public hearing. The deadline for submitting comments and the notice of public hearing will be posted on the Wisconsin Administrative Rules Website at
http://adminrules.wisconsin.gov
after the hearing is scheduled.
RULE TEXT
SECTION 1.
DHS 157.01 (16) is created to read:
DHS 157.01
(16)
Subchapter XV establishes requirements for the physical protection program for any licensee that possesses
a
category 1 or
category 2 quantity of radioactive material
listed in Appendix U.
SECTION 2
.
DHS 157.03
(84m) and Note
is amended to read
:
DHS 157.03
(
84m
) "Criticality safety index" or "CSI" means the dimensionless number, rounded up to the next tenth, assigned to and placed on the label of a fissile material package to designate the degree of control of accumulation of packages,
overpacks
, or freight containers containing fissile material during transportation.
Note
: Determination of the criticality safety index is described in s.
DHS 157.93 (7)
and
(8)
. s.
DHS 157.93 (7)
and
(8)
, and
10 CFR 71.59
. The CSI for an
overpack
, freight container, consignment or conveyance containing fissile material packages is the arithmetic sum of the criticality safety indices of all the fissile material packages contained within the
overpack
freight container, consignment,
or conveyance
.
SECTION
3
.
DHS 157.03 (6m), (12m)
and Note
, (25m)
,
(
36m
)
, (56g) and
Note, (56r) and N
ote,
(77m),
(108m), (109m), (124g), (139m)
,
(143g),
(150g), (166m), (189m) and
Note, and
(193m)
are created to read:
DHS 157.03
(6m)
“Access control” means a system for allowing only approved individuals to have unescorted access to the security zone and for ensuring that all other individuals are subject to escorted access.
DHS 157.03
(
12m
)
"Aggregated" means accessible by the breach of a single physical barrier that would allow access to radioactive material in any form, including any devices that contain the radioactive material
.
Note:
An aggregated total activity equal or exceeding a category 2 to quantity of radioactive material
exceeds the thresholds set forth
in Appendix U.
DHS 157.
03
(
25m
)
"Approved individual" means an individual whom the licensee has determined to be trustworthy and reliable for unescorted access
under
ss.
DHS 157.100
to
157.106
and who has completed the training required by s.
DHS 157.108 (3)
.
DHS 157.03
(
36m
)
"Background investigation" means the investigation conducted by a licensee or applicant
for a license
to support the determination of trustworthiness and reliability.
DHS 157.03
(
56g
)
"Category 1 quantity of radioactive material" means a quantity of radioactive material meeting or exceeding the category 1 threshold in Appendix U of this chapter.
Note:
This is determined by calculating the ratio of the total activity of each radionuclide to the category 1 threshold for that radionuclide and adding the ratios together. If the sum is equal to or exceeds 1, the quantity would be considered a category 1 quantity. Category 1 quantities of radioactive material do not include the radioactive material contained in any fuel assembly, subassembly, fuel rod, or fuel
pellet.
Appendix
U is used to determine the category 1 threshold for a category 1 quantity of radioactive material. The category 1 and category 2 thresholds in Appendix U and Appendix T are not interchangeable.
DHS 157.
03
(
56r
)
"Category 2 quantity of radioactive material" means a quantity of radioactive material meeting or exceeding the category 2
threshold
,
but less than the category 1 threshold in
Appendix U of this chapter.
Note:
This is determined by calculating the ratio of the total activity of each radionuclide to the category 2 threshold for that radionuclide and adding the ratios together. If the sum is equal to or exceeds 1, the quantity would be considered a category 2 quantity. Category 2 quantities of radioactive material do not include the radioactive material contained in any fuel assembly, subassembly, fuel rod, or fuel
pellet.
Appendix
U is used to determine the category 2 threshold for a category 2 quantity of radioactive material. The category 1 and category 2 thresholds in Appendix U and Appendix T are not interchangeable.
DHS 157.03
(77m)
“Contamination” means the presence of a radioactive substance on a surface in quantities i
n excess of 0.4
Bq
/cm2 (1x10-5
micro
Ci
/cm2) for beta and gamma emitters and low toxicity alpha em
itters, or 0.04
Bq
/cm2 (1x10-
6
micro
Ci
/cm
2) for all other alpha emitters.
DHS 157.03
(
108m
)
"Diversion" means the unauthorized movement of
category 1 or category 2 quantity of
radioactive material
that is
subject to
subch
. XV to a location different from the material’s authorized destination inside or outside of the site at which the material is used or stored.
DHS 157.03
(109m)
“Dose length product” or “DLP” means the metric which is related to the total energy imparted in the patient, and is determined by multiplying the
CTDIvol
value by the scan length, resulting in the units of
mGy
-cm. DLP is calculated using the following formula:
where
:
L = the length of patient scanned
.
p =
is the pitch
.
CTDI100
,cent
= CTDI100 value determined at the center of a standardized phantom
.
CTDI100
,periphery
= CTDI100 value determined at the periphery of a standardized phantom.
DHS 157.03
(
124g
)
"Escorted access" means
the continuous direct visual surveillance by an approved individual over an individual in the security zone who is not approved for unescorted access.
DHS 157.03
(
139m
)
"Fingerprint
order
" means
an order
issued by the NRC,
a
license condition by the department, or
a
legally binding requirement issued by
another
agreement state
that require
s
a
fingerprints and criminal history records check for individuals
who have
unescorted access to category 1 and category 2 quantities of radioactive material or safeguards information-modified handling.
DHS 157.03
(
143g)
“Fixed contamination” means contamination that cannot be removed from a surface during normal conditions of transport.
DHS 157.03
(
150g
)
"Government agency" means any executive department, commission, independent establishment, corporation, wholly or partly owned by the United States of America which is an instrumentality of the United States, or any board, bureau, division, service, office, officer, authority, administration, or other establishment in the executive branch of the Government.
DHS 157.03
(
1
66
m
)
“Indian tribe” means an Indian or Alaska native tribe, band, nation, pueblo, village, or community that the Secretary of the Interior acknowledges to exist as an Indian tribe pursuant to the Federally Recognized Indian Tribe List Act of 1994, 25 W.S.C. 479a.
DHS 157.03
(
189m
)
“License verification system” means the national verification system that enables authorized government authorities and authorized licensees to verify certain information about licensees authorized to possess, use, or ship radioactive materials.
Note:
The system may be used to confirm that a license is valid and accurate, a licensee is authorized to acquire quantities and types of radioactive materials, and the licensee’s category 1 or 2 quantities of radioactive material inventories do not exceed the possession limits of the license.
DHS 157.03
(
193m
)
"Local law enforcement agency” or “LLEA" means a public or private organization that has been approved by a federal, state, or local government to carry firearms and make arrests, and is authorized and has the capability to provide an armed response in the jurisdiction where the licensed category 1 or category 2 quantity of radioactive material is used, stored, or transported.
SECTION
4
.
DHS 157.0
3
(198)
,
(200)
(c)
,
and
(208)
are
amended to read
:
DHS 157.03
(198)
"
Low specific activity - I" or "LSA-I material" means any of the following:
(a) Uranium and thorium
ores,
concentrates of uranium and thorium ores, and other ores containing naturally occurring radioact
ive radionuclides which are
not
intended to be processed for the use of radionuclides.
(b)
Solid unirradiated natural uranium or depleted uranium or natural thorium or their solid or liquid compounds or mixtures.
Natural uranium, deple
ted uranium, natural thorium or
their compounds or mixtures, provided they are unirradiated and in solid or liquid form
.
(c) Radioactive material,
other than fissile material
, for
which the A
2
value is unlimited.
(d) Other radioactive material in which the radioactive material is distributed throughout and the estimated average specific activity does not exceed 30 times the value for exempt material activity concentra
tion determined under Appendix
A
O
.
DHS 157.03
(200)
(c)
The estimated average specific activity of the solid
, excluding
any shielding material,
does not exceed 2 x 10-3 A
2
/g.
DHS 157.03
(
208)
"Medical event" means an
improper
administration of radiation or radioactive material to a patient or human research subject that requires reporting to the department.
SECTION
5.
DHS 157.03 (215m) and (219m) are created to read:
DHS 157.03
(
215m
)
"Mobile device" means a piece of equipment containing licensed radioactive material that is either mounted on wheels or casters, or otherwise equipped for moving without a need for disassembly or dismounting; or designed to be hand carried.
“
Mobile device
”
does
not include stationary equipment installed in a fixed location.
DHS 157.03
(
219m
)
"Movement control center" means an operations center that is remote from transport activity and that maintains position information on the movement of radioactive material, receives reports of attempted attacks or thefts, provides a means for reporting these and other problems to appropriate agencies and
,
request
s
and coordinate
s
appropriate aid.
SECTION
6
.
DHS 157.03 (221m) is
amended
to read:
DHS 157.03
(221m)
"Nationally tracked source" means a sealed source containing a quantity equal to or greater than
category 1
or
category 2
levels
thresholds
of any radioactive material
listed in Appendix T. In this context a sealed source is defined as radioactive material that is sealed in a capsule or closely bonded, in a solid form and which is not exempt from regulatory control. It does not mean material encapsulated solely for disposal, or nuclear material contained in any fuel assembly, subassembly, fuel rod, or fuel pellet. Category 1 nationally tracked sources are those containing radioactive material at a quantity equal to or greater than the
category
1 threshold.
C
ategory
2 nationally tracked sources are those containing radioactive
material at a quantity equal to or greater than the
category
2 threshold but less than the
category
1 threshold.
SECTION
7
.
DHS 157.03
(221m) Note, (228m), (230m), (318m),
(319g), (
319r), (331g), (331r), (374m), (392m), (393m), and (402g) are created to read:
DHS 157.03
(221m)
N
ote
:
Appendix T is used to
determine
the category 1 and category 2 thresholds for a nationally tracked source. The category 1 and category 2 thresholds in Appendix T and Appendix U are not interchangeable.
DHS 157.03
(
228m
)
"No-later-than arrival time" means the date and time that the shipping licensee and receiving licensee have established as the time at which an investigation will be initiated if the shipment has not arrived at the receiving facility. The no-later-than arrival time may not be more than 6 hours after the estimated arrival time for shipments of category
2 quantities of radioactive material.
DHS 157.03
(230m)
“Non-fixed contamination” means contamination that can be removed from a surface during normal conditions of transport.
DHS 157.03
(
318m
)
"Reviewing official" means the individual who
shall make
the trustworthiness and reliability determination of an individual to determine whether
the
individual may have,
or continue to have,
unescorted access to the category 1 or category 2 quantities of radioactive materials that are possessed by
the
licensee.
DHS 157.03
(
319
g
)
“S
abotage” means
the act of
an
person who
intentiona
l
l
y
damage
s, interferes, or tampers w
it
h reasonable grounds to believe his or her
act will hinder, delay, or interfere with the normal operation of any one of the following
:
(a)
A
category 1 or category 2 quantity of radioactive material
.
(b)
A
device that contains a category 1 or category 2 quantity of radioactive material
.
(c)
The
components of the security system
.
DHS 157.03
(
319r
)
"Safe haven" means a readily recognizable and readily accessible site at which security is present or from which, in the event of an emergency, the transport crew can notify and wait for the local law enforcement authorities.
DHS 157.03
(
331g
)
“Security order” means any order that was issued by the NRC that required fingerprints and an FBI criminal history records check for
access to any one of the following:
(a)
Safeguards
information
.
(b)
Safeguards
information-modified handling
.
(c) Risk
significant material such as special nuclear material
or large quantities of uranium
hexafluoride.
DHS 157.03
(
331r
)
"Security zone" means any temporary or permanent area established by the licensee for the physical protection of category 1 or category 2 quantities of radioactive material.
DHS 157.03
(
374m
)
"Telemetric position monitoring system" means a data transfer system that captures information by instrumentation or measuring devices about the location and status of a transport vehicle or package between the departure and destination locations.
DHS 157.03
(
392m
)
“Tribal official” means the highest ranking individual that represents Tribal leadership, such as the Chief, President, or Tribal Council leadership.
DHS 157.03
(
393m
)
"Trustworthiness and reliability" means the characteristics of an individual considered dependable in judgment, character, and performance, such that unescorted access to category 1 or category 2 quantities of radioactive material by that individual does not constitute an unreasonable risk to the public health and safety or security. A determination of trustworthiness and reliability for this purpose is based upon the results from a background investigation.
DHS 157.03
(
402g
)
"Unescorted access" means solitary access to a
c
ategory 1 or category 2 quantity of radioactive material or the devices that contain the material.
SECTION
8
.
DHS 157.03 (402m) is renumbered DHS 157.03 (402r).
SECTION
9
.
DHS 157.03 (404) and (419m) are amended to read:
DHS 157.03
(404)
"Unrefined and unprocessed ore" means ore in its natural form prior to any processing, such as grinding, roasting, refining or altering the ore from its natural state.
Processing does not include sieving or encapsulation of ore or preparation of samples for laboratory analysis.
DHS 157.03
(
(
419m)
"
Well
-
logging
Well logging
assistant" means any individual who, under the personal supervision of a well logging supervisor, handles sources of radiation that are not in logging tools or shipping containers or who performs surveys required by s.
DHS 157.55
.
SECTION
1
0
.
DHS 157.09 (1) (a)
(intro.)
,
and
(1) (a)
5.
a
. and
b. are
amended to read:
DHS 157.09
(1)
(a)
A person is exempt from
this subchapter
subch
. III and X
if the person receives,
possesses,
uses, owns or transfers any of the following types and forms of source material:
DHS 157.09
(1)
(a) 5.
a
.
Glazed ceramic tableware
manufactured before August 27, 2013
, provided that the glaze contains not more than 20% by weight source material.
DHS 157.09
(1)
(a) 5.
b.
Glassware containing not more than
10
2
% by weight source
material
,
or for glassware manufactured before August 27, 2013, 10% by weight source material
; but not including commercially manufactured glass brick, pane glass, ceramic tile or other glass or ceramic used in construction.
SECTION
1
1
.
DHS 157.09 (1) (a) 8.
a
. is repealed
.
SECTION
1
2
.
DHS 157.09 (1) (a) 8.
b., c., and d. are renumbered
DHS 157.09 (1) (a) 8.
a.,
b.,
and
c.
SECTION
1
3
.
DHS 157.09 (1) (a) 10.
(
intro
.)
is
amended to read:
DHS 157.09
(1)
(a)
10.
(
intro
.)
Thorium
or uranium
contained in
or on
finished optical lenses, provided that a lens does not contain more than
30
10
% by weight of thorium
or uranium or for lenses manufactured before August 27, 2013, 30% by weight of thorium
and that this exemption is not deemed to authorize either of the following:
SECTION
1
4
.
DHS 157.09 (1)
(
a) 11.
a
nd
12
.
a
re
repealed and recreated to read:
DHS 157.09
(1)
(a) 11.
Thorium contained in any finished aircraft engine part containing nickel-
thoria
alloy, provided that the thorium is dispersed in the alloy in the form of finely divided
thoria
, and the thorium content in the nickel-
thoria
alloy does not exceed 4% by weight.
DHS 157.09
(1)
(a)
12.
Only persons authorized
by a license issued under
10 CFR 40.52
,
may
initially transfer
for sale or distribution
such products containing source material to
a person
exempt under this subsection
.
SECTION
1
5
.
DHS 157.0
9
(1)
(a
)
13
.
is
created to read:
DHS 157.09
(1)
(a) 13.
Persons authorized by an agreement state to manufacture, process, or produce materials or products containing source material, and persons who import finished products or parts for sale or distribution, shall be licensed for distribution only under
10 CFR 40.52
, and are exempt from
s.
DHS 157.13 (2) (a)
and
(b)
, and
subch
.
III and X
.
SECTION
1
6
.
DHS 157.09 (2) (c) 7.
i
s
amended
to read:
DHS 157.09
(2)
(c)
7.
Electron tubes, including spark gap tubes, power tubes, gas tubes including glow lamps, receiving tubes, microwave tubes, indicator tubes, pick-up tubes, radiation detection tubes and any other completely sealed tube that is designed to conduct or control
electrical currents, provided that the radiation dose rate from each electron tube containing radioactive material does not exceed 10
uGy
microgy
(1
millirad
) per hour at one centimeter from any surface when measured through 7 milligrams per square centimeter of absorber and that each tube does not contain more than one of the following specified quantities of radioactive material:
SECTION
1
7
.
DHS 157.09 (2) (c)
9.
,
10., and
11.
are
created to read:
DHS 157.09
(2)
(c)
9.
Static elimination devices which contain, as a sealed source or sources, radioactive material consisting of a total of not more than 18.5
MBq
(500
microcuries
) of polonium-210 per device.
DHS 157.09
(2)
(c)
10.
Ion generating tubes designed for ionization of air that contain, as a sealed source or sources, radioactive material consisting of a total of not more than 18.5
MBq
(500
microcuries
) of polonium-210 per device or of a total of not more than 1.85
GBq
(50
mCi
) of hydrogen-3 (tritium) per device.
DHS 157.09
(2)
(c)
11.
Devices
authorized before October 23, 2012 for use under the general license then provided in DHS 157.11 (2)
(a) and equivalent regulations of
agreement state
s
,
and manufactured, tested, and labeled by the manufacturer in accordance with the specifications contained in a specific license issued by the NRC.
SECTION
1
8
.
DHS 157.09 (2) (d) 1.
and
(e) 1.
are
amended to read:
DHS 157.09
(2)
(d) 1.
Except for persons who manufacture, process, produce, or initially transfer for sale or distribution
of
self-luminous products containing tritium, krypton-85 or promethium-147, and except as provided in
subd
. 3., any person is exempt from this subchapter to the extent that such person receives, possesses, uses, transfers, owns or acquires tritium, krypton-85 or promethium-147 in self-luminous products manufactured, processed, produced or initially transferred under a specific license issued by the NRC according to
10 CFR 32.22
, which authorizes the initial transfer of the product for use under this subdivision.
DHS 157.09
(2)
(e) 1.
Except for persons who manufacture, process, produce or initially transfer for sale or distribution gas and aerosol detectors containing radioactive material, a person is exempt from this subchapter if the person receives, possesses, uses, transfers, owns or acquires radioactive material in gas and aerosol detectors designed to protect life or property from fires and airborne hazards provided that the detectors containing radioactive material have been manufactured, processed, produced or initially transferred for sale or distribution under a specific license issued by the NRC under
10 CFR 32.26
, a licensing state, other agreement state or the department under s.
DHS 157.13 (4) (c)
, which authorizes the transfer of the detectors to persons who are exempt from regulatory requirements.
This exemption also covers gas and aerosol detectors manufactured or distributed before November 30, 2007 in accordance with a specific license issued by a
n agreement
state under comparable provisions under
10 CFR 32.26
authorizing distribution to persons exempt from regulatory requirements.
SECTION
19
.
DHS 157.09 (2) (g) and
DHS 157.09
(3) are cre
a
ted to read:
DHS 157.09
(2)
(g)
Industrial use devices containing exempt quantities or disturbed under a general license.
1.
Except for persons who manufacture, process, produce or initially transfer for sale or distribution of industrial devices designed and manufactured for the purpose of detecting, measuring, gauging or controlling thickness, density, level, interface location, radiation, leakage, or qualitative or quantitative chemical composition, or for producing an ionized atmosphere containing radioactive material, a person is exempt from this subchapter if the person receives, possesses, uses, transfers, owns or acquires radioactive material in these certain detecting, measuring, gauging, or controlling devices and certain devices for producing an ionized atmosphere have been manufactured, processed, produced or initially transferred for sale or distribution under a specific license issued by the NRC under
10 CFR 32.26
, a licensing state, other agreement state or the department under s.
DHS 157.13 (4) (c)
, which authorizes the transfer of the detectors to persons who are exempt from regulatory requirements. This exemption does not cover sources not incorporated into a device, such as calibration and reference sources.
2. Industrial devices previously manufactured and distributed to general licensees under the specific license issued by an agreement state shall be considered exempt under this subdivision provided that the device is labeled under the specific license authorizing distribution of the generally licensed device and provided further that they meet the requirements of s.
DHS 157.13 (4) (c)
.
DHS 157.09
(3)
EXEMPTIONS OF CATEGORY 1 OR CATEGORY 2 QUANTITIES OF RADIOACTIVE WASTE
.
A licensee that possesses radioactive waste that contains
category 1 or category 2 quantities
of radioactive material, other than waste that contains discrete sources, ion-exchange resins, or activated material that weighs less than 2,000 kg (4,409
lbs
), is exempt from the requirements of ss.
DHS 157.100
to
157.122
and shall
implement all the following requirements to secure the radioactive waste:
(a)
Use continuous physical barriers that allow access to the radioactive waste only through established access control points.
(b)
Use a locked door or gate with monitored alarm at the access control point.
(c)
Assess and respond to each actual or attempted unauthorized access to determine whether an actual or attempted theft, sabotage, or diversion occurred.
(d)
Immediately notify the LLEA and request an armed response from the LLEA upon determination that there was an actual or attempted theft, sabotage, or diversion of the radioactive waste that contains category 1 or category 2 quantities of radioactive material.
SECTION
2
0
.
DHS 157.10 (3) is
repealed and recreated
to read:
DHS 157.10
(3
)
FEE SCHEDULE
.
The following is the schedule of application, annual, amendment and reciprocity fees for specific radioactive material licenses.
Category
|
License Type
|
Application & Annual Fee
|
1.
|
Special Nuclear Material
|
|
A.
|
License for possession and use of SNM in sealed sources contained in devices used in measuring systems
|
$1,000
|
B.
|
License for use of SNM to be used as calibration and reference sources
|
$300
|
C.
|
SNM – all other, except license authorizing special nuclear material in unsealed form that would constitute a critical mass [Fee waived if facility holds additional license category]
|
$1,500
|
A.
|
Source material processing and distribution
|
$4,000
|
B.
|
Source material in shielding [Fee waived if facility holds additional license category]
|
$400
|
C.
|
Source material – all other, excluding depleted uranium used as shielding or counterweights
|
$3,000
|
A.
|
License of broad scope for processing or manufacturing of items for commercial distribution
|
$20,000
|
B.
|
License for processing or manufacturing and commercial distribution of radiopharmaceuticals, generators, reagent kits and sources or devices
|
$12,000
|
C.
|
License for commercial
distribution or redistribution of radiopharmaceuticals, generators, reagent kits and sources or devices
|
$3,000
|
D.
|
Other licenses for processing or manufacturing of items for commercial distribution
|
$4,000
|
E.
|
License for industrial radiography operations performed only in a shielded radiography installation
|
$3,000
|
F.
|
License for industrial radiography performed only at the address indicated on the license, and at temporary job sites
|
$5,000
|
G.
|
License for possession and use of less than 370
TBq
(10,000 curies) of radioactive material in sealed sources for irradiation of materials where the source is not removed from the shield [Fee waived if facility holds additional irradiator license category]
|
$2,000
|
H.
|
License for possession and use of less than 370
TBq
(10,000 curies) of radioactive material in sealed sources for irradiation of materials where the source is exposed for irradiation purposes. The category also includes underwater irradiators for irradiation of materials in which the source is not exposed for irradiation
|
$3,000
|
I.
|
License for possession
and use of at least 370
TBq
(10,000 curies) and less than 3.7
PBq
(100,000 curies)of radioactive material in sealed sources for irradiation of materials
|
$5,000
|
J.
|
License for possession and use of 3.7
PBq
(100,000 curies) or more of radioactive material in sealed sources for irradiation of materials
|
$12,000
|
K.
|
License to distribute items containing radioactive materials to persons under a general license
|
$2,000
|
L.
|
License to possess radioactive materials intended for distribution to persons exempt from licensing
|
$2,500
|
M.
|
License of broad scope for research and development that does not authorize commercial distribution
|
$6,000
|
N.
|
Other licenses for research and development that do not authorize commercial distribution
|
$1,800
|
O.
|
License for installation, repair, maintenance leak testing or other service of devices or items containing radioactive material,
or to perform services for other persons, including testing of sealed sources for leakage or contamination, instrument calibration, and sample analysis,
excluding waste transportation or broker services
|
$1,800
|
P.
|
License for portable gauges, including
industrial
Lixiscope
®
|
$1,400
|
Q.
|
License for portable x−ray fluorescence analyzer calibration flood source,
dewpointer
or gas chromatograph
|
$200
|
R.
|
All other byproduct, naturally− occurring or accelerator− produced material licenses, except as otherwise noted
|
$2,000
|
A.
|
Commercial waste treatment facilities, including incineration
|
$200,000
|
B.
|
All other commercial facilities involving waste compaction, repackaging, storage or transfer
|
$25,000
|
C.
|
Waste processing – all other, including decontamination service
|
$5,000
|
A.
|
License for well logging using sealed sources or sub−surface tracer studies
|
$4,000
|
B.
|
License for well logging using sealed sources and sub−surface tracer studies
|
$5,000
|
A.
|
License for commercial collection and laundry of items contaminated with radioactive material
|
$16,000
|
A.
|
License for human use of byproduct, source, special nuclear or NARM material in sealed sources contained in
teletherapy
or stereotactic radiosurgery devices, including mobile therapy
|
$12,000
|
B.
|
License of broad scope for human use of byproduct, source, special nuclear or
NARM materials used in medical diagnosis, treatment, research and development, excluding
teletherapy
, or stereotactic radiosurgery devices
|
$20,000
|
C.
|
License for mobile nuclear medicine
|
$2,500
|
D.
|
Medical – all others, including SNM pacemakers and high dose rate remote
afterloading
devices
|
$5,000
|
E.
|
License for veterinary use of radioactive materials
|
$2,000
|
A.
|
License for possession and use of byproduct, naturally−occurring or accelerator produced radioactive material for educational use or academic research and development that does not authorize commercial distribution, excluding broad scope or human use licenses, with a combined possession limit of 12 isotopes and 37
GBq
(1 curie) total activity
|
$1,000
|
A.
|
License for accelerator production of radioisotopes with commercial distribution
|
$4,000
|
B.
|
Accelerator isotope production – all other [Fee waived if facility holds medical broad scope license with no commercial distribution]
|
$2,000
|
A.
|
Reciprocal recognition of an out−of−state specific license
|
50% of annual fee of applicable category
|
A.
|
Request to amend specific license − no license review
|
$0
|
Note:
Examples include spelling corrections and adding or removing previously authorized users.
|
B.
|
Request to amend specific license − license review required
|
$200
|
Note:
Examples include new isotopes, license termination
not
requiring a site visit and procedural changes.
|
C.
|
Request to amend specific license − license review and site visit required
|
$400
|
Note:
Examples include a facility move, license termination requiring a site visit and new processes.
|
SECTION
2
1
.
DHS 157.11 (1) (a)
is
repealed and recreated to read
:
DHS 157.11
(1)
(a)
General license for certain organizations to use and transfer limited amounts of source material.
A general license is issued authorizing commercial and industrial firms, research, educational and medical institutions and state and local government agencies to receive, possess, use, and transfer uranium and thorium, in their natural isotopic concentrations and in the form of depleted uranium, for research, development, educational, commercial, or operational purposes.
DHS 157.11
(1)
(a)
1
.
The general license issued under this paragraph shall be limited to the following forms and quantities:
a
.
No more than 1.5 kg (3.3
lb
) of uranium and thorium in dispersible forms (e.g., gaseous, liquid, powder, etc.) at any one time. Any material processed by the general licensee that alters the chemical or physical form of the material containing source material shall be accounted for as a dispersible form. A person authorized to possess, use, and transfer source material under this paragraph may not receive more than a total of 7 kg (15.4
lb
) of uranium and thorium in any one calendar year.
b.
No more than a total of 7 kg (15.4
lb
) of uranium and thorium at any one time. A person authorized to possess, use, and transfer source material under this paragraph may not receive more than a total of 70 kg (154
lb
) of uranium and thorium in any one calendar year. A person may not alter the chemical or physical form of the source material possessed under this subsection unless it is accounted for under the limits of
subd
. 1.
a
.
c
.
No more than 7 kg (15.4
lb
) of uranium, removed during the treatment of drinking water, at any one time. A person may not remove more than 70 kg (154
lb
) of uranium from drinking water during a calendar year under this paragraph.
d. No more than 7 kg (15.4
lb
) of uranium and thorium at laboratories for the purpose of determining the concentration of uranium and thorium contained within the material being analyzed at any one time. A person authorized to possess, use, and transfer source material under this paragraph may not receive more than a total of 70 kg (154
lb
) of source material in any one calendar year
.
2.
A person who receives, possesses, uses or transfers source material under the general license issued under this paragraph shall comply with all the following:
a
.
Not administer source material
under the general license issued under this paragraph
, or radiation from the source material, either externally or internally, to human beings except as authorized by the department in a specific license.
b.
Not export source material
under the general license issued under this paragraph
except as allowed
under
10 CFR Part 110
.
c
.
Not abandon source material
under the general license issued under this paragraph
.
3.
Source material may be disposed of by any of the following methods:
a.
A cumulative total of 0.5 kg (1.1
lb
) of source material in a solid, non-dispersible form may be transferred each calendar year, by a person authorized to receive, possess, use, and transfer source material under this general license to persons receiving the material for permanent disposal.
A person is exempt from the requirement to obtain a license under this subchapter if source material is transferred to the person for permanent disposal
a rly at state, or to the NRC. eral licensee, requirements: cipients in other states, shall be submitted to each responsible
under the provisions of this paragraph, and the person is not authorized
to possess source material under a specific license issued under this chapter.
4.
A person who receives, possesses, uses or transfers source material under the general license issued under this paragraph is subject to the provisions in ss.
DHS 157.01
to
157.03
,
157.05 (2)
,
157.06 (1)
to
(3)
,
157.13 (9)
,
157.13 (10)
,
157.13 (15)
,
157.13 (16)
,
157.31
,
157.32
,
157.89 (4) (b)
,
and
157.90
to
157.91
.
6
.
A person who receives,
possesses,
uses or transfers source material
pursuant to the specific terms of
a
general
license issued under this paragraph
, and who does not possess source
material under a specific license issued under this chapter,
is exempt from
subchs
. III and X, except that such person shall comply with s
s
.
DHS 157.33 (2)
and
DHS 157.30 (1)
.
7.
No person may initially transfer or distribute source material to persons
in possession of a
general license
issued
in
par. (1) a. or b.
, or equivalent regulations of the NRC or another
agreement state
, unless authorized by a specific license issued by the department, the NRC
,
or another
agreement state
. This prohibition does not apply to analytical laboratories returning processed samples to the client who initially provided the sample
.
SECTION
2
2
.
DHS 157.11 (2) (a) is amended to read:
DHS 157.11
(2)
DHS 157.11
(2)
(a)
General license relating to certain devices and equipment.
A general license is issued to transfer, receive, acquire, own, possess and use radioactive material incorporated in all the following devices or equipment which have been manufactured, tested and labeled by the manufacturer under a specific license issued to the manufacturer by the NRC
for use under
10 CFR 31.3
. This general license is exempt from the requirements of
subch
.
III, with the exception of ss.
DHS 157.30 (1)
,
157.32 (1)
and
(2)
, and
subch
.
X.
SECTION
2
3
.
DHS
1
57
.
13 (1) (h)
(intro.) and 1.is
amended to read:
DHS 157.13
(1)
(h)
Each
application to use radioactive material in the form of a sealed source or in a device that contains a sealed source shall contain
either
all
of the following:
1
.
Information that identifies the source or device by manufacturer and model number as registered with the NRC
under
10 CFR 32.10
or an agreement state
.
, or for a source or device containing radium-226 or accelerator-produced radioactive material
,
information that identifies the source or device by manufacturer and model number as
registered
with a state under provisions comparable to
10 CFR 32.210
.
SECTION
2
4
.
DHS 157.13 (1) (h) 3.
is
created to read:
DHS 157.13
(1)
(h) 3.
For sources or devices containing nat
urally occurring or accelerator-
produced radioactive material manufactured prior to November 30, 2007 that are not registered with the NRC under
10 CFR 32.210
or with an agreement state, and for which the applicant is unable to provide all categories of information specified in
10 CFR 32.210
(c), the applicant shall provide all of the following:
a. All available information identified in
10 CFR 32.210
(c) concerning the source,
and, if applicable, the device.
b. Sufficient additional information to demonstrate that there is reasonable assurance that the radiation safety properties of the source or device are adequate to protect health and minimize danger to life and property. Such information shall include a description of the source
or device, a description of radiation safety features, the intended use and associated operating experience, and the results of a recent leak test.
SECTION
2
5
.
DHS 157.13 (1) (i)
is
amended to read:
DHS 157.13
(1)
(i)
Each application for a specific license, other than a renewal, shall contain information describing how facility design and procedures for operation will minimize, to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning and minimize, to the extent practicable, the generation of radioactive waste.
Licensees shall, to the extent practical, conduct operations to minimize the introduction of residual radioactivity into the site, including the subsurface, in accordance with the existing radiation protection requirements in s.
DHS 157.21
and the radiological criteria for license termination in s.
DHS 157.33
.
SECTION
26
.
DHS 157.13 (4) (d) 1.
h
. is created to read:
DHS 157.13
(4)
(d) 1.
h.
Each
device has been registered in the Sealed Source and Device Registry.
SECTION
27
.
DHS 157.13 (4) (e)
,
(f)
and (h)
2.
are
amended to read:
DHS 157.13
(4)
(e)
Special requirements for the manufacture, assembly or repair of luminous safety devices for use in aircraft.
The department shall approve an application for a specific license to manufacture, assemble or repair luminous safety devices containing tritium or promethium-147 for use in aircraft, for distribution to persons generally licensed under s.
DHS 157.11 (2) (c)
if the applicant satisfies the general requirements specified in sub. (2) and the requirements of
10 CFR 32.53
to
32.56
,
32.101
and
32.110
or their equivalent.
(f)
Special requirements for license to manufacture calibration or reference sources containing americium-241, plutonium or radium-226 for distribution to persons generally licensed under s.
DHS 157.11 (2) (e)
.
The department shall approve an application for a specific license to manufacture calibration or reference sources containing americium-241, plutonium or radium-226 to persons generally licensed under s.
DHS 157.11 (2) (e)
if the applicant satisfies the general requirement of sub. (2) and the requirements of
10 CFR 32.57
to
32.59
,
1
0 CFR 32.102
and
10 CFR 70.39
or their equivalent.
SECTION
28
.
DHS
157.
13 (4) (j) 5.
is
created to read:
DHS 157.13
(4)
(j) 5.
The source or device has been registered in the
sealed source
and
device registry
.
SECTION
29
.
DHS
157.
13 (4m) is created to read:
DHS 157.13
(4m)
S
pecial Requirements for a Specific license to Initially transfer Source Material to a Person DHS 157.11 (1).
(a) The department shall approve an application for a specifi
c license to initially transfer
source material if all the fol
lowing conditions are satisfied:
1. The applicant satisfies the general requirements in
s.
DHS 157.13
(2)
.
2. The applicant submits adequate information on, and the
departme
nt approves the
methods to be used for quality control, labeling, and providing safety instructions to recipients
,
based upon
adequate
information
submitted
by the applicant
.
(b)
Each person licensed under par. (a)
shall
label the immediate container of each quantity of source material with the type of source material and quantity of material and th
e words, “radioactive material.”
(c) Each person licensed under par. (a)
shall
ensure that the quantities and concentrations of source material are as labeled and indicated in any transfer records.
(d) Each person licensed under par. (a)
shall
provide
all of
the
following
information to each person to whom source material is transferred for use under
s
.
DHS 157.11 (1)
,
or equivalent regulations of the NRC or another agreement state
,
before the source material is transferred
to the person
for the first time in each calendar year:
2.
Appropriate radiation safety precautions and instructions relating to handling, use, storage, and disposal of the
source
material.
(e) Each person licensed under
s.
157.13 (4m)
a.
shall report transfers as follows:
1. File a report with the department for each general licensee under s.
DHS 157.11(1)
or equivalent NRC or another agreement state
provisions
to whom greater than 50 grams (0.11
lb
) of source material has been transferred in a single calendar quarter. The report shall include the following information:
a. The name, address, and license number of the person who transferred the source material.
b. The name and address of the general licensee to whom source material is distributed; a responsible agent, by name and/or position and phone number, of the general licensee to whom the material was sent; and the type, physical form, and quantity of source material transferred.
c. The total quantity of each type and physical form of source material transferred in the reporting period to all such generally licensed recipients.
2. For material shipped to another state, file a report with each applicable responsible state agency or the NRC that identifies all persons, operating under provisions equivalent to s.
DHS 157.11(1)
, to whom greater than 50 grams (0.11
lb
) of source material has been transferred within a single calendar quarter. The report shall include the following information specific to those transfers made to the applicable responsible state agency, or NRC, being reported to:
a. The name, address, and license number of the person who transferred the source material.
b. The name and address of the general licensee to whom source material was distributed; a responsible agent, by name and/or position and phone number, of the general licensee to whom the material was sent; and the type, physical form, and quantity of source material transferred.
c.
The total quantity of each type and physical form of source material transferred in the reporting period to all such generally licensed recipients.
3.
Submit each report by January 31 of each year covering all transfers for the previous calendar year. If no transfers were made to persons generally licensed s.
DHS 157.11(1)
or equivalent NRC or another agreement state provision during the current period, a report shall be submitted to the department and applicable responsible state agency or the NRC. If no transfers have been made to general licensees in a particular state during the reporting
period, this
information shall be reported to the responsible state
agency or the NRC upon request.
(f) Each person licensed under par. (a)
shall
maintain all information that supports the reports required by this subsection concerning each transfer to a general licensee for a period of
one
year after the event is included in a report.
SECTION
30
.
DHS
157.
13 (10) (b)
is renumbered DHS 157.13 (10 (b) 1.
SECTION
3
1
.
DHS 157.13 (10)
(
b
) 2.
i
s
created to read:
DHS 157.13
(10)
(b)
2
.
An application for transfer of license shall include all the following:
a. The identity, technical and financial qualifications of the proposed transferee.
b. Financial assurance for decommissioning information, as applic
able, required by s.
DHS 157.15
.
SECTION
32
.
DHS 157.13
(10)
(e)
2.
i
s
amended to read:
DHS 157.13
(10)
(e)
DHS 157.13
(10)
(e)
2.
An entity defined in
11 USC 101
(
14
15
)
controlling the licensee or listing the license or licensee as property of the estate.
SECTION
3
3
.
DHS
157.
15 (1) (a) 2.
and
4.
, (5) (a) (intro.) and 1.
are
amended to
read:
DHS 157.
15
(1)
(a) 2.
Unsealed radioactive material
with a half-life greater than 120 days
involving a combination of isotopes with R divided by 10
5
being greater than one, where R is defined as the sum of the ratios of the quantity of each isotope to the applicable value in Appendix I.
DHS 157.
15
(1)
(a)
4.
Sealed sources or plated foils
with a half-life greater than 120 days
involving a combination of isotopes with R divided by 10
12
being greater than one, where R is defined as the sum of the ratios of the quantity of each isotope to the applicable value in Appendix I.
DHS 157.15
(5)
Decommissioning Funding Plan.
(a)
A decommissioning funding plan shall
be submitted
to the department
for review and approval and
shall
include all the following information:
DHS
157.15
(5)
(a)
1
.
A
detailed
cost estimate for decommissioning
that considers
in an amount reflecting
all of the following:
SECTION
34
.
DHS
157.15 (5) (a) 1.
e
. and f. are created to read:
DHS 157.
15
(5)
(a) 1.
e.
The volume of onsite subsurface material containing residual radioactivity that will require remediation to meet the criteria for license termination.
DHS 157.15
(5)
(a) 1.
f. The cost of an independent contractor to perform all decommissioning activities including an adequate contingency factor.
SECTION
35
.
DHS
157.15 (5) (a) 2.
is
repealed and recreated
to read:
DHS
157.15
(5)
(a)
2.
Identification of and justification for using the key assumptions contained in the decommissioning cost estimate.
SECTION
3
6
.
DHS
157.15 (5) (a) 3.
and
(5)
(b) are amended to read:
DHS 157.15
(5)
(a)
3.
A description of the method
for adjusting cost estimates and associated funding levels periodically over the life of the facility. Cost estimates shall be adjusted at intervals not to exceed 3 years.
for
assuring funds for decommissioning according to sub. (6), including means for adjusting cost estimates and associated funding levels periodically over the life of the facility.
Cost estimates shall be adjusted at intervals not to exceed 3 years
.
DHS
157.15
(5)
(
b
)
The decommissioning funding plan shall also contain the licensee's certification that financial assurance has been provided in the amount of the cost estimate for decommissioning and
that
a signed original of the financial instrument obtained to satisfy the requirements of sub. (6)
has
been submitted and accepted,
unless
a previously submitted and accepted financial instrument continues to cover the cost estimate for decommissioning
.
SECTION
3
7
.
DHS
157.15 (5) (c) is created to read:
DHS 157.15
(5)
(c) At intervals not to exceed 3 years
,
the licensee shall resubmit
the decommissioning funding plan
to the department
with adjustments as necessary to account for changes in costs and extent of contamination.
The
amount of financial assurance
shall not
be
decreased
until the updated decommissioning funding plan is approved. The
licensee
shall update the information submitted with the original or
previously
approved
decommissioning funding
plan, and shall specifically consider the effect of all the following events on decommissioning costs:
1. Spills of radioactive material producing additional residual radioactivity in onsite subsurface material.
2. Waste inventory increasing above the amount estimated.
3. Waste disposal costs increasing above the amount previously estimated.
4. Facility modifications.
5. Changes in authorized possession limits.
6. Actual remediation costs that exceed the previous cost estimate.
7. Onsite disposal.
8. Use of a settling pond.
SECTION
38
.
DHS
157.
21
(1) is amended to read
:
DHS 157.21
(1)
A
licensee or registrant shall develop, document and implement a radiation protection program sufficient to ensure compliance with the provisions of this
subchapter.
A licensee or registrant shall designate a person in control over each radiation installation.
SECTION
39
.
DHS
157.
22
(1)
(e
)
Note
,
(4)
(h)
2
.,
and (5) (d) 1.
and
Note
are
amended
to read:
DHS
157.
22
(1) (
e
)
Note:
See footnote
c/
c/
of Appendix E for the calculation method for determining DAC for
solu
a
ble
soluble
mixtures of uranium.
DHS 157.22
(4)
(h)
2
.
For an ALI and the associated DAC determined by the
nonstochastic
non-stochastic
organ dose limit of 0.5
Sv
(50 rem), the intake of radionuclides that would result in a committed effective dose equivalent of 0.05
Sv
(5 rem), that is, the stochastic ALI, is listed in parentheses in Table I of Appendix E. The licensee or registrant may, as a simplifying assumption, use the stochastic ALI to determine committed effective dose equivalent. However, if the licensee or registrant uses the stochastic ALI, the licensee or registrant shall also demonstrate that the limit in s.
DHS 157.22 (1) (a) 1.
b
.
is met.
DHS 157.22
(5)
(d)
1.
A licensee or registrant shall record the exposure history, as required by par. (
a
), on
a
a
n
occupational radiation exposure form provided by the department, or other clear and legible record of all the information required on that form. The form or record shall show each period in which the individual received occupational exposure to radiation or radioactive material and shall be signed by the individual who received the exposure. For each period for which a licensee or registrant obtains reports, a licensee or registrant shall use the dose shown in the report in preparing the occupational radiation exposure form or equivalent. For any period in which a licensee or registrant does not obtain a report, a licensee or registrant shall place a notation on the occupational radiation exposure form or equivalent indicating the periods of time for which data are not available.
DHS 157.22 Note
Note:
An occupational radiation exposure history form may be obtained by writing to: Department of Health Services, Radiation Protection Section, P.O. Box 2659, Madison WI 53701-2659; or by downloading the form from the Department website at:
http://dhs.wisconsin.gov/radiation/Index.htm
.
SECTION
4
0
.
DHS
157.
24
(1)
(b
)
is amended to read:
DHS 157.24
(1)
(b)
Notwithstanding the provisions of par. (a), sources
Each
source meeting the criteria under par. (a)
not
in use and identified as being in storage shall meet all the following conditions:
SECTION
4
1
.
DHS
157.25
(1)
(a)
1.
,
2.
(intro.),
(1)
(a)
2.
b
. and c. are
amended to read
:
DHS 157.25
(1)
(a)
1.
Surveys
of areas, including the subsurface,
necessary for the licensee or registrant to comply with this subchapter.
DHS 157.25
(1)
(a)
2.
Surveys
of areas, including the subsurface,
necessary and reasonable under the circumstances to evaluate any of the following:
DHS
157.25
(1)
(a)
2.
b.
Concentrations or quantities of
radioactive material
residual radioactivity
.
DHS
157.25
(1)
(a)
2.
c.
The potential radiological hazards
of the radiation levels detected and residual radioactivity detected
.
SECTION
4
2
.
DHS
157.25
(1)
(d)
is created to read:
DHS 157.25
(1)
(d
)
Notwithstanding s.
DHS 157.31
(3)
(a)
, records from surveys describing the location and amount of subsurface residual radioactivity identified at the site shall be kept with
decommissioning
records
and
shall be retained under s.
DHS 157.15
.
SECTION
4
3
.
DHS
157
.
25
(2)
(a)
5.
is
amended to read
:
DHS 157.25
(2)
(a)
5.
An individual working
longer than 10 minutes per
week
within 6 feet of operating medical fluoroscopic equipment.
SECTION
4
4
.
DHS
157.
33
(3)
(a)
4.
i
s
created to read
:
DHS 157.33
(3)
(a)
4.
Has provided sufficient financial assurance in the form of a trust fund to enable an independent third party, including a governmental custodian of a site, to assume and carry out responsibilities for any necessary control and maintenance of the site.
SECTION
45.
DHS 157.43 (2) (b) is repealed.
SECTION
46
.
DHS
157.
43
(2)
(intro.)
and
DHS
157.
43
(2)
(a)
are
renumbered
DHS
157.
43
(2)
(a) and
DHS
157.
43
(2)
(b)
.
SECTION
47
.
DHS
157.
44
(6)
(a)
4
.
is
amended to read:
DHS 157.44
(6)
(a)
4
.
After replacement, each personnel dosimeter shall be
processed according to NVLAP approved procedures
, or shall be
returned to the supplier for processing within 14 calendar days of the end of the monitoring period or as soon as practicable. In circumstances that make it impossible to return each personnel dosimeter
with
in 14 calendar days, the circumstances shall be documented and available for review by the department.
SECTION
48
.
DHS
157.
61
(7)
(a)
2.
b
, (8)
(a)
1.
b.,
and
(
10)
(a) and (c)
are
amended to read:
DHS 157.61
(7)
(a)
2.
b.
Two years of full-time practical training and/or supervised experience in medical physics either under the supervision of a medical physicist who is certified in medical physics by a specialty board recognized by the department, the NRC, or another agreement state or in clinical nuclear medicine facilities providing diagnostic and/or therapeutic services under the direction of physicians who meet the requirements for authorized users in s
s
.
DHS
157.61 (10)
,
157.63 (5)
or
157.64 (4)
.
DHS
157.
61
(8)
(a)
1.
b.
Attained two years full-time practical training and/or supervised experience in medical physics under the supervision of a medical physicist who is certified in medical physics by a specialty board recognized by the department, the NRC or an agreement state or in clinical radiation facilities providing high-energy, external beam therapy (photons and electrons with energies greater than or equal to 1 million electron volts) and brachytherapy services under the direction of physicians who meet the requirements for authorized users in
s
s
.
DHS
157.61 (10)
,
157.65 (8)
or
s.
DHS
157.67 (17)
.
DHS
157.
61
(10)
(a)
An individual identified as a radiation safety officer, a
teletherapy
or
authorized
medical physicist, or a nuclear pharmacist on a department, NRC or another agreement state license, the permit issued by a licensee of broad scope or the permit issued by an NRC master material licensee before October 24, 2002 need not comply with the training requirements of subs. (7) to (9), respectively.
DHS
157.
61
(10)
(c)
A physician, dentist or podiatrist identified as an authorized user for the medical, dental or podiatric use of radioactive material on a department, NRC or another agreement state license, the permit issued by a licensee of broad scope or the permit issued by an NRC master material licensee
before October 24, 2002
who performs only those medical uses for which they are authorized need not comply with the training requirements of ss.
DHS 157.63
to
157.67
.
SECTION
49
.
DHS
157.
61
(10)
(d) is created to read:
DHS 157.61
(10)
(d)
Individuals who
are
not
required to
comply with
the
training requirements as described in this section may serve as preceptors for, and supervisors of, applicants seeking authorization on department licenses for the same uses for which these individuals are authorized.
SECTION
5
0
.
DHS 157.63
(2)
(b)
3.
a
nd
(4)
(c)
2.
are
amended
to read:
DHS 157.63
(2)
(b)
3.
An individual under the supervision, as specified in s.
DHS 157.61 (
10
3
)
, of the authorized nuclear pharmacist in subd.1., or the physician in
subd
. 2.
DHS 157.63
(4)
(c)
2.
Work experience, under the supervision of an authorized user who meets the requirements in this subsection, sub.
(4)
or
(5), s.
DHS 157.61 (10)
,
or
157.64 (4)
, or equivalent agreement state requirements, involving all the following:
SECTION
5
1
.
DHS 157.67
(11)
(f)
a
nd
(12)
(b)
3
.
are
amended
to read:
DHS 157.67
(11)
(f)
A licensee shall have an authorized medical physicist review the results of each spot-check within 15 working days of the spot check. The authorized medical physicist shall notify the licensee
as soon as possible
in writing of the results of each spot-check
within 10 working days
.
DHS 157.67
(12)
(b)
3.
The authorized
medical
physicist shall notify the licensee
as soon as possible
in writing of the results of the spot check
review within 10 working days
.
SECTION
5
2
.
DHS 157.71
(8)
is
amended
to read:
DHS 157.71
(8)
RECORDS OF DOSAGES OF UNSEALED RADIOACTIVE MATERIAL FOR MEDICAL USE
.
A licensee shall maintain a record of dosage determinations required by s.
DHS 157.62 (3)
for 3 years. The record shall contain the radiopharmaceutical, patient's or human research subject's name or identification number if one has been assigned, the prescribed dosage, the determined dosage or a notation that the total activity is less than 1.1
MBq
(30
mCi
microcuries
)
, the date and time of the dosage determination and the name of the individual who determined the dosage.
SECTION
5
3
.
DHS 157.72
(1)
(a)
1.
is
amended
to read:
DHS 157.72
(1)
(a)
1
.
A dose that differs from the prescribed dose
or dose that would have resulted from the prescribed dosage
by more than 0.05
Sv
(5 rem) effective dose equivalent, 0.5
Sv
(50 rem)
to an organ or tissue or 0.5
Sv
(50 rem) shallow dose equivalent to the skin and to which any of the following apply:
SECTION
5
4
.
DHS
157.74
(2)
(b)
2.
,
(d)
3.,
(2)
(f),
and
(h)
1.
and
4.
c
.
are
amended
to read:
DHS 157.74
(2)
(b)
2.
Type and size of the
film
image receptor
or film-screen combination to be used.
DHS 157.74
(2)
(d)
3.
Operators of c-arm configuration units which do not operate at a tube current in excess of 0.2 mA are exempt from the requirement to wear a leaded apron, provided the operator wears a
personnel
personal
dosimeter as required under s.
DHS 157.25 (2)
.
DHS 157.74
(2)
(f) Persons may not be exposed to the useful beam except for
healing arts purposes and unless such exposure has been authorized
by a licensed practitioner of the
healing arts
or a Wisconsin licensed physical therapist.
Del
iberate exposure for any of the
following purposes is prohibited
:
DHS 157.74
(2)
(h)
1.
The speed of the
screen and film combinations
image receptor
used shall be of a speed consistent with the diagnostic objective of the examinations. Film cassettes without intensifying screens may not be used for any routine diagnostic radiological imaging, with the exception of veterinary radiography and standard film packets for intra-oral use in dental radiography.
DHS 157.74
(2)
(h)
4.
c.
Antiscatter
Anti-scatter
grids or an appropriate air gap technique to reduce scatter to the image receptor shall be used for all x-ray examinations of the human torso utilizing stationary x-ray equipment for patients 12 years of age or older.
SECTION
55
.
DHS
157
.
74
(2)
(m)
is created to read:
DHS 157.74
(2)
(m)
Each individual operating x-ray equipment for diagnostic medical purposes on humans shall have a current
r
adiography
l
icense or
l
imited
x
-ray
m
achine
o
perators permit from the State of Wisconsin.
SECTION
56
.
DHS
157
.74
(3)
(b)
2.
and
(
4)
(b)
are
amended to read:
DHS 157.74
(3)
(b)
2.
Quality control and maintenance procedures shall be performed on a regular schedule according to the device manufacturer's recommendations
or procedures approved by the department.
If analysis shows that the system test results fall outside the device manufacturer's recommended limits corrective action shall be taken prior to performing patient examinations
.
DHS 157.74
(4)
(b)
The darkroom shall be light tight with proper safelights so that any film type in use exposed in a cassette to x-radiation sufficient to produce an optical density from
one to 2
1 to 2
when processed may not suffer an increase in density greater than 0.1, or 0.05 for mammography, when exposed in the darkroom for 2 minutes with all safelights on. This test shall be performed at least once every 6 months. If used, daylight film handling boxes shall preclude fogging of the film. Darkrooms typically used by more than one person shall be provided a method to prevent accidental entry while undeveloped films are being handled or processed.
SECTION
57
.
DHS 157.76
(7)
(c) is repealed and recreated to read:
DHS 157.76
(7)
(c) For x-ray controls manufactured on or after June 10, 2006, all of the following shall be provided for each fluoroscopic tube:
1. A display of the fluoroscopic irradiation time at the fluoroscopist's working position.
2. The display required in
subd
. 1.
shall
function independently of the audib
le signal described in sub.
(7) (
a
) and meet all the following requirements:
a. When the x-ray tube is activated, the fluoroscopic irradiation time in minutes and tenths of minutes shall be continuously displayed and updated at least once every 6 seconds.
b. The fluoroscopic irradiation time shall also be displayed within 6 seconds of termination of an exposure and remain displayed until reset.
c. Means shall be provided to reset the display to zero prior to the beginning of a new examination or procedure.
3. A signal audible to the fluoroscopist shall sound for each passage of 5 minutes of fluoroscopic irradiation time during an examination or procedure. The signal shall sound until manually reset or, if automatically reset, for at least 2 seconds.
SECTION
58
.
DHS
157
.76
(7)
(d) is created to read:
DHS 157.76
(7)
(d) If fluoroscopic equipment
is modified in accordance with
21 CFR 1020.30
(q)
to comply with the requirements in par. (a), it shall bear a label
that states
:
SECTION
59
.
DHS
157
.7
6
(11
)
(
a
) is amended to read:
DHS 157.76
(11)
(a)
The
facility
registrant
shall ensure that only a licensed practitioner or a radiologic technologist who is trained in the safe use of fluoroscopic x-ray systems is allowed to operate these systems. All fluoroscopic x-ray images shall be viewed, directly or indirectly, and interpreted by a licensed practitioner.
SECTION
60
.
DHS 157.77
(2)
(h
)
1
.
,
and (i)
are
amended to read:
DHS 157.77
(2)
(h)
1.
Stationary x-ray systems shall be required to have the x-ray control permanently mounted
in a protected area
behind a protective barrier such
that the operator is required to remain
in that protected area
behind the protective barrier
during the entire exposure.
DHS 157.77
(2)
(i)
Operator protection for veterinary systems.
All stationary, mobile or portable x-ray systems used for veterinary work shall be provided with either a 2 meter (6.5 feet) high protective barrier for operator protection during exposures or a means to allow the operator to be at least 2 meters (6.5 feet) from the tube
housing assembly during exposures.
Persons within 2.7 meters (9 feet) of the tube or animal during exposures shall be protected with at least 0.25mm lead aprons.
Persons restraining the animal during radiography shall be protected with at
least
0.5 mm
0
.25mm
lead aprons and full coverage gloves or full coverage mittens containing not less than 0.5mm lead equivalent material.
The exposure control may be foot operated.
SECTION
6
1
.
DHS 157.78
(4)
(d)
1.
and
3.
,
(8)
(title),
and
(9
)
(a)
are
amended to read:
DHS 157.78
(4)
(d)
1.
A stationary x-ray system shall have an x-ray exposure control that
may be moved
to a protected are
a
so that the operator is required to remain in that protected area
is operable from behind a protective barrier
during the entire exposure. The exposure
control
cord shall be of sufficient length to allow the operator to be at least 2 meters (6.5 feet) from the x-ray tube head and not in the direction
of
the
tube
primary beam
is pointed
. The operator shall be able to determine when the exposure has completed either by audible tone or
by
visible signal.
DHS 157.78
(4)
(d)
3.
A mobile or portable x-ray system that is used for less than one week in the same location shall be provided with either a protective barrier at least 2 meters (6.5 feet) high for operator protection or means to allow the operator to be at least 2 meters (6.5 feet) from the tube housing assembly
while making
during
exposures.
DHS 157.78
(8)
((8
Kvp
kVp
limitations.
Dental x-ray machines with a nominal fixed
kVp
of less than 50
kVp
may not be used to make diagnostic dental radiographs of humans.
DHS 157.78
(9)
(a
)
Intraoral
film holding
image receptor
devices shall be used.
SECTION
6
2
.
DHS 157.78
(
1
0)
is
created
to read:
DHS 157.78
(10)
HAND-HELD INTRAORAL DENTAL RADIOGRAPHIC UNITS
.
A dental
radiographic
unit that is
designed to be operated as a hand-held unit shall meet
all the following requirements:
(
a) For all uses:
1. Operators of hand-held intraoral dental radiographic units shall be trained to
operate such equipment.
The training
shal
l
cover
: manufacturer specific exposure control, use of safety devices, operator and patient protection
,
and quality control testing.
2. When operating a hand-held intraoral dental radiographic unit, operators shall wear a lead apron and thyroid collar unless the hand-held intraoral device has a secondary protective barrier.
3. A hand-held intraoral dental radiographic unit shall be
immobilized
during a
patient examination. A tube stand may be utilized to immobilize a hand-held intraoral dental radiographic unit during patient examination.
4. The operator shall ensure there are no bystanders within a radius of at least
2
meters (6.5
ft
) from the patient being examined during
exposures
.
(
b) For permanent facilities:
1. Hand-
held intraoral dental radiographic units shall be u
sed for patient examinations in
dental offices that meet the structural shielding requirements specified by the department.
2. Hand-held intraoral dental radiographic units may not be used for patient examinations in hallways and waiting rooms.
SECTION
68
.
DHS 157.
79
(3)
(c)
is amended to read:
DHS 157.79
(3)
(
c)
Any person holding or supporting an animal or the
film
image receptor
during radiation exposure shall wear protective gloves that surround the hand and a protective apron having a lead equivalent of not less than
0.5
0.25
millimeter. Devices that only partially shield the hands are prohibited
SECTION
69
.
DHS 157.80
(1)
(b) is
amended to read:
DHS 157.80
(1)
(b)
Tomographic plane indication and alignment.
A computed tomography x-ray system shall meet all of the following plane indication and alignment requirements, as applicable:
DHS 157.80(1)(b)1.
1.
A single tomogram system shall allow for visual d
etermination of the tomographic
plane or a reference plane offset from the tomographic plane.
DHS 157.80(1)(b)2.
2.
A multiple tomogram system shall allow for visual determination of the location of a reference plane.
DHS 157.80 Note
Note:
The reference plane may be offset from the location of the tomographic planes.
DHS 157.80(1)(b)3.
3.
If a device using a light source is used to satisfy the requirements in
subd
. 2., the light source shall
provide illumination levels sufficient to permit visual determination of the location of the tomographic plane or reference plane under ambient light conditions of up to 500 lux.
SECTION
70
.
DHS 157.80
(1)
(f)
5.
and
6
.
are
created
to read:
DHS 157.80
(1)
(f)
5.
Two-way aural communication shall exist between the patient and the operator at the control panel.
6.
A viewing window,
or viewing system, such
as
closed circuit television or an equivalent
,
shall be
installed
to permit continuous observation of the patient during irradiation
.
The window or viewing system shall be installed such that the
operator, located at the control position, can continuously observe the patient during irradiation.
When the primary viewing system is electronic, an alternative system shall be available for use in
the
event of failure of the primary viewing system.
SECTION
71
.
DHS 157.80
(2)
(a
)
1
.
, (b)
4.
,
and (c)
are
amended to read:
DHS 157.80
(2)
(a)
(a)
1.
A CT x-ray system for human use may only be operated for diagnostic procedures by an American registry of radiologic technologists certified person who
is licensed as a
radiographer
by the State of Wisconsin or has met the
radiographer
license
exemptions) and
has been specifically trained in its operation
.
DHS 157.80(2)(a)2.
DHS 157.80
(2)
DHS 157.80(2)(a)
DHS 157.80(2)(b)
(b)
4.
A current technique chart
or list of protocols
available at the control panel, which specifies for each routine examination the CT conditions of operation and the number of scans per examination including body part size
and correct kV/mA for that body
part.
The technique
chart
or
a list of protocols
shall be used to
adjust techniques based on the
body
part being examined
.
DHS 157.80(2)(b)1.
DHS 157.80
(2)
(c)
Calibration and spot check measurements shall be made at a frequency recommended by the manufacturer
or established by a medical physicist
. If the calibration or spot check of the CT x-ray system identifies that a system operating parameter has exceeded a tolerance established by the medical physicist, use of the CT x-ray system on patients shall be limited to those uses permitted by established written instructions of the medical physicist.
SECTION
72
.
DHS
157.83
(3)
(b)
1.
is
amended to read:
DHS 157.
83
(3)
(b)
1.
Notify
their department head no later than the next calendar day
the department by telephone or in person no later than
3
working
days
after discovery of the medical event.
SECTION
73
.
DHS
157.83
(3)
(b)
2
.
a
.
is
renumbered DHS 157.83 (3) (b) 2.
a
nd
as renumbered is
amended to read:
DHS
157.83
(3)
(b)
2.
Submit a written report to the department within 15 working days after discovery of the medical event. The written report shall include: the registrant's name; the prescribing physician's name; a brief description of the event; the effect on the patient; what improvements are needed to prevent recurrence; actions taken to prevent recurrence; whether the registrant notified the patient or the patient's responsible relative or guard
ian and if not, why not; and if
the
patient was notified, what information was provided to the
patient.
This report may
not include the patient's name or other information that could lead to identification of the patient.
DHS 157.83 Note
Note:
Mail the report to the Department at: Department of Health Services, Radiation Protection Section, PO Box 2659,
Madison
WI 53701-2659.
SECTION
74
.
DHS 157.83
(3) (b) 2.
b
. is
repealed
.
SECTION
75
.
DHS 157.83 (3) (b) 4.
d
. is amended to rea
d:
DHS 157.83
(3)
(b) 4.
d.
What improvements
a
re
n
eeded
were
identified and actions taken
to prevent recurrence
and the actions taken to prevent recurrence
.
SECTION
76.
DHS 157.84
(1)
(b)
5.
is
created to read:
DHS 157.84
(1)
(b)
DHS 157.84(1)(b)
5.
Replacing the therapeutic radiation machine in an existing treatment room.
SECTION
77
.
DHS 157.85
(3)
(title)
and
(13
)
(
em
)
2.
to
7.
are
amended to read
:
DHS
157.85
(3)
DHS 157.85
(3)
A
djustable or
Removeable
Removable
Beam-Limiting
Devices
.
DHS 157.85
(13)
(
em
)
2.
Proper operation of back-up exposure control devices
.
External testing protocol is acceptable as long as the back-up exposure control is tested per the manufacturer’s scheduled calibration cycle.
3.
The output within
2%
the manufacturer’s specified tolerance
of the expected value, if
applicable,
or
determination of
the
calculated
output if there is no expected value.
4.
Evaluation that the relative dose distribution about the source is within
5%
the manufacturer’s specified
tolerance
of the expected
value
.
5.
Source
For electronic brachytherapy systems where the source is moveable, the source
position accuracy
to
shall be
within 1 millimeter within the applicator.
Fixed x-ray source systems shall meet the manufacturer’s tolerances for source location and shape within the applicator.
6.
D
etermination
For systems with transfer tubes and applicators,
determination
of the proper length of source transfer tubes and applicators
.
7.
D
etermination
For systems with transfer tubes and applicators,
determination
of the operability of the source transfer tubes, applicators and transfer tube-applicator interfaces.
SECTION
78
.
DHS 157.85
(14
)
(gm)
(intro.)
is
renumbered DHS 157.85 (14
)
(
gg
) (intro.) and as renumbered is amended
to read:
DHS 157.85
(14)
(
g
g
)
Daily quality control checks for
adjustable source
electronic brachytherapy shall include all the following:
SECTION
79
.
DHS 157.85
(14
)
(
gr
) is created to read:
DHS 157.85
(14)
(
g
r
) Daily quality control checks for fixed source electronic brachytherapy shall include all the following:
1.
The probe
shall
be checked and adjusted for mechanical straightness
to be less than or equal to 0.02
cm deflection
.
2.
After the mechanical straightness of the probe is adjusted or checked, the beam itself
shall
be dynamically adjusted to be straight within the probe. This will center the beam to within 0.07mm upon the target.
3.
The beam
shall
be checked and adjusted for isotropy to within 12%.
4.
The dose output
shall
be checked with an
ion
chamber and compared to the manufacturer’s dose value.
5. If dose output exceeds ± 5% of manufacturer’s dose value, the physicist
shall
investigate why
;
if the output exceeds ± 10% of manufacturer’s value the treatment
shall
not
occur
until the unit is brought within the manufacturer’s tolerance of 5%.
SECTION
80
.
DHS
157.85
(16)
(g)
7
.
d
.
is amended to read
:
DHS 157.85
(16)
(g)
7
.
d.
A medical physicist
,
oncologist, or
and
operator shall be
physically
present
during the initiation
and
at the controls throughout the
course of
patient
the patient’s
treatment.
A medical physicist and oncologist shall remain available during treatment.
SECTION
81
.
DHS
157.87
(1)
(intro.)
is
amended to read:
DHS 157.87
(1)
GENERAL REQUIREMENTS
.
For certified cabinet x-ray systems including those designed to allow admittance of individuals
, x-ray devices not designated as industrial radiography, and x-ray devices not used for medical imaging or therapy
, all of the following requirements apply:
SECTI
O
N
82
.
DHS 157.87 (1) (a) is repealed and recreated to read:
DHS 157.87
(1)
(
a
)
Registrants and operators shall have documented training in the proper use of the system or device from one of the following:
1. The system or device manufacturer.
2. In-house staff previously trained by the system or device manufacturer.
SECTION
83
.
DHS 157.87 (1) (
ag
) and (
ar
) are created to read:
DHS 157.87
(1)
(
ag
) The training required in
par
. (a)
shall
include all the following:
1. Basic radiation protection
.
2. Operating procedures specific to system or device
,
including the use of various functions, safety, and maintenance.
3. Emergency procedures applicable to the system or device.
(
ar
) During the operation of any x-ray system or device, the operator shall ensure that ancillary personnel, members of the general public and themselves are protected from the radiation.
SECTION
84.
DHS 157.87
(3)
(b)
6.
and
(4) (a) are
amended to read:
DHS 157.87
(3)
(b)
6.
DHS 157.87
(3)
(b) 6.
Whenever personnel monitoring devices show an increase of 50% over the previous monitoring period or the readings are approaching the limits of sub. (2) (
g
) or (h). Radiation survey measurements are not
be
required if a person in control demonstrates compliance with par. (a)
in
some other manner.
DHS 157.87
(4)
(
a
)
Procedures.
Operating procedures shall be written and available to all analytical x-ray equipment workers. No individual may operate analytical x-ray equipment in any manner other than that specified in the procedures unless the individual has obtained written approval of the
safety office or the responsible
person
identified on the registration
in control
.
SECTION
85.
DHS 157.87 (4) (c), (d)
,
and (e) are created to read:
DHS 157.87
(4)
(c)
Training.
Operators of x-ray devices not designated
for
industrial radiography and not used for medical imaging or therapy shall have documented training in the proper use of the device from one of the following:
1. The device manufacturer.
2. In-house staff previously trained by the device manufacturer.
(d)
Training
Requirements
.
The training required under
par
.
(c)
shall
include all the following:
1. Basic radiation protection.
2. Operating procedures specific to the device
,
including the use of various
system
functions, safety, and maintenance.
3. Emergency procedures applicable to the device.
(e)
Area Control
.
During the operation of any x-ray system
,
the operator shall ensure that ancillary personnel, members of the general public and
the operator
are protected from the radiation.
SECTION 86
.
DHS 157.92 (2) (b)
and (c) 4.
are
amended to read
:
DHS 157.92
(2)
(b) A licensee is exempt from the requirements of this subchapter with respect to shipment or carriage of any of the following materials:
1. Naturally occurring radioactive material and ores
containing naturally occurring radionuclides
that
are
either in their natural state or have only been processed for purpose other than the extraction of the radionuclides, and
that
are not intended to be processed for use of these radionuclides, provided the activity concentration of the material does not exceed 10 times the values specified in Appendix O, Table
VII
or
Table VIII
.
2. Materials for which the activity concentration is not greater than the activity concentration values specified in Appendix O, Table VII
or Table VIII
, or for which the consignment activity is not greater than the limit for an exempt consignment found in Appendix O, Table VII
or Table VIII
.
3. Non-radioactive solid objects with radioactive substances present on any surfaces in quantities not in excess of the levels in the definition of contamination.
DHS 157.92
(2)
(c)
4.
Uranium enriched in uranium-235 to a maximum of one percent by weight, and with total plutonium and uranium-233 content of up to one percent of the mass of uranium-235, provided that the mass of any beryllium, graphite, and hydrogenous material enriched in deuterium present in the package is less than 5% of the uranium mass
.
,
and that the fissile material is distributed homogeneously and does not form a lattice arrangement within the package.
SECTION
87
.
DHS 157.93 (4
) (a
m
) is created
to read
:
DHS 157.93
(4)
(am)
The
general license issued in par. (a)
applies
only to a licensee who has a quality assurance program approved by the commission as satisfying the provision of subpart H of
10 CFR 71
.
SECTION
8
8
.
DHS 157.93 (4
) (
b
) is amended to read
:
DHS 157.93
(4)
(
b
)
The
general license issued in par. (a)
applies
only to a licensee who meets all the following criteria:
The licensee issued a general license in par. (a)
shall
meet the following:
1.
Has
Maintain
a copy of the specific license, certificate of compliance, or other approval by the nuclear regulatory commission of the package and
has
the drawings and other documents referenced in the approval relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment.
2.
Complies
Comply
with the terms and conditions of the license, certificate, or other approval by the nuclear regulatory commission, as applicable, and the applicable requirements of
this subsection.
ch
.
DHS 157
and s
ubpart A, G, and H of
10 CFR 71
.
3. Prior to the licensee's first use of the package, submits in writing to the nuclear regulatory commission the licensee's name and license number and the package identification number specified in the package approval. A licensee shall submit this information in accordance with
10 CFR 71.1
(a).
4. Has a quality assurance program that complies with subpart H of
10 CFR 71
.
SECTION
89
.
DHS 157.93 (6)
is repealed and recreated to read:
DHS 157.93
(6)
(a)
A general license is issued to any licensee to transport, or to deliver to a carrier for transport, licensed material in a package whose design has been approved in a foreign national competent authority certificate and which has been revalidated by the US department of transportation as meeting the applicable requirements of
49 CFR 171.23
.
(
am
) The general license issued in par. (a)
applies
only to a licensee who has a quality assurance program approved by the commission as satisfying the applicable provision of s. DHS 157. 94 (6)
DHS 157.93(6)(b)
(b)
The general license in par. (a)
applies
only to international shipments.
DHS 157.93(6)(c)
(c)
The licensee issued a general license in par. (a)
shall
meet the following:
Down
Up
DHS 157.93(6)(c)1.
1.
Maintain a copy of the applicable certificate, the revalidation, and the drawings and other documents referenced in the certificate relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment.
DHS 157.93(6)(c)2.
2.
Comply with the terms and conditions of the certificate and revalidation, and with the requirements s.
DHS 157.92
and
157.94
.
SECTION
9
0
.
DHS 157.94
(3
)
is repealed and recreated to
read:
DHS 157.94
(3)
Shipment and packaging records
.
(
a
) A licensee shall maintain for a period of 3 years after shipment
,
a record of each shipment of licensed material not exempt under s.
DHS 157.92 (2)
, showing all of the following:
1. Identification of the packaging by model number and serial number.
2. Verification that the packaging, as shipped, had no significant defect.
3. Volume and identification of coolant.
4. Type and quantity of licensed material in each package and the total quantity of each shipment.
5.
For
each item of irradiate fissile material, the following:
a. Identification by model number and serial number.
b.
Irradiation
and decay history to the extent appropriate to demonstrate that its nuclear and thermal characteristics comply with license conditions.
c. Any abnormal or unusual condition relevant to radiation safety.
6. Date of the shipment.
7. For fissile package and for Type B
package,
and special controls exercised.
8. Name and address of the transferee.
9. Address to which the shipment was made.
10. Results of the determinations required by sub. (1)
and
by the conditions of the package approval.
(b) A licensee, certificate holder, and an applicant for a
CoC
, shall make available to the department for inspection, upon reasonable notice, of all records required by this subsection. Records are only valid if stamped, initialed, or signed and dated by authorized personnel, or otherwise authenticated.
(c) A licensee, certificate holder, and an applicant for a certificate of compliance shall maintain sufficient written records to furnish evidence of the quantity of packaging. The records to be maintained include results of the determinations required by s.
DHS 157.94 (8)
; design, fabrication, and assembly records; results of reviews, inspections, tests, and audits; results of monitoring work performance and materials analyses; and results of maintenance, modification, and repair activities. Inspection, test, and audit records must identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any deficiencies noted. These records must be retained for 3 years after the life of the packaging to which they apply.
SECTION
9
1
.
DHS 157.94
(5)
(a)
is renumbered DHS 157.94 (5) (a) 1.
SECTION
9
2
.
DHS 157.94 (5) (a) 2.
is
created to read:
DHS 157.94
(5)
(a)
2
.
Prior to the transport of any nuclear waste meeting the criteria in par.
(b) outside of the confines of the licensee’s facility or other place of use or storage
,
or prior to the delivery of any nuclear waste to a carrier for transport, within or across the boundary of the
federally recognized Indian
tribe’s
reservation, each licensee shall provide advance notification of transport to the
Indian
tribal
official of the participating
Indian
t
ribes or the
Indian t
ribal
o
fficial
’
s designee, and to the department.
DHS 157.94 Note
Note:
Notification of transport of nuclear waste may be sent to: Division of Emergency Management, 2400 Wright Street, Madison, Wisconsin, 53704. Notification may also be made by: telephone at 608-242-3232; or fax at 608-242-3247. The telephone number of the 24-hour duty officer is 1-800-943-0003.
Contact information for each State, including telephone and mailing addresses of governors and governors' designees, and participating Tribes, including telephone and mailing addresses of Tribal officials and Tribal official's designees, is available on the NRC Web site at:
https://scp.nrc.gov/special/designee.pdf
.
SECTION
9
3
.
DHS 157.94 (5) (d), (e), and (f) are amended to read:
DHS 157.94
(5)
(d)
The
notification required by par. (a)
shall
be made in writing to the office of the governor
,
or governor's designee,
the office of each appropriate tribal official
,
or tribal official’s designee,
and to the department. A notification delivered by mail
must
shall
be postmarked at least 7 days before the beginning of the 7-day period during which departure of the shipment is estimated to occur. A notification delivered by messenger or facsimile shall reach the office of the governor
,
or governor's designee,
the
Indian t
ribal official or
Indian
t
ribal official’s designee,
and the department at least 4 days before the beginning of the 7-day period during which departure of the shipment is estimated to occur. A copy of the notification shall be retained by the licensee for 3 years.
(e)
A
licensee shall notify the governor
,
or governor's designee,
Indian
t
ribal official or
Indian t
ribal official’s designee,
and the department of any changes to schedule information provided under par. (
a
). Notification shall be by telephone or facsimile to a designated responsible individual in the office of the governor
,
or governor's designee,
Indian
t
ribal official or
Ind
i
an t
ribal official’s designee
, and to the department. A licensee shall retain for 3 years a record of the name of the individual contacted.
(f)
A licensee
who cancels a nuclear waste shipment for which advance notification has been sent shall send to the governor
,
or governor's designee,
Indian
t
ribal official or
Indian t
ribal official’s designee,
and to the department a cancellation notice identifying the advance notification that is being canceled. A copy of the notice shall be retai
ned by the licensee for 3 years.
SECTION
9
4
.
DHS 157.94 (6
)
is
repealed and recreated to
read:
DHS 157.94
(6)
Quality assurance requirements.
(a) A licensee, certificate holder, and applicant for a certificate of compliance are responsible for the quality assurance requirements as they apply to design, fabrication, testing, and modification of packaging. A licensee is responsible for the quality assurance provision which applies to its use of a packaging for the shipment of licensed material subject to this
subchapter
.
(b) A licensee, certificate holder, and applicant for a
Certificate of Compliance
shall establish, maintain, and execute a quality assurance program satisfying each of the applicable criteria of
10 CFR 71.101
through
71.137
and satisfying any specific provisions that are applicable to the licensee's activities including procurement of packaging. The licensee, certificate holder, and applicant for a
CoC
shall execute the applicable criteria in a graded approach to an extent that is commensurate with the quality assurance requirement's importance to safety.
(c) Before the use of any package for the shipment of licensed material subject to this subsection, a licensee shall obtain nuclear regulatory commission approval of its quality assurance program.
(d) A licensee, certificate holder, and applicant for a
Certificate of Compliance
shall be responsible for
establishing and executing
the quality assurance program. A licensee, certificate holder, and applicant for a
Certificate of Compliance
may delegate to others, such as contractors, agents, or consultants, the work of establishing and executing the quality assurance program, or any part of the quality assurance program, but shall retain responsibility for the program. These activities include performing the functions associated with attaining quality objectives and the quality assurance functions.
(e) The quality assurance functions include the following:
1. Assuring that an appropriate quality assurance program
is established and effectively
executed; and
2. Verifying, by procedures such as checking, auditing, and inspection, that activities affecting the safety-related functions have been performed correctly.
(f) Changes to a quality assurance program shall comply with the following:
1. Each quality assurance program approval holder shall submit in accordance with
10 CFR 71.1
(a), a description of a proposed change to its NRC-approved quality assurance program that will reduce commitments in the program description as approved by the NRC.
a. The quality assurance program approval holder shall not implement the change before receiving NRC approval.
b. The description of a proposed change to the NRC-approved quality assurance program must identify the change, the reason for the change, and the basis for concluding that the revised program incorporating the change continues to satisfy the applicable requirements of
10 CFR 71
subpart H.
2. Each quality assurance program approval holder may change a previously approved quality assurance program without prior NRC approval, if the change does not reduce the commitments in the quality assurance program previously approved by the NRC. Changes to the quality assurance program that do not reduce the commitments shall be submitted to the NRC every 24 months, in accordance with
10 CFR 71.1
(a). In addition to quality assurance program changes involving administrative improvements and clarifications, spelling corrections, and non-substantive changes to punctuation or editorial items, the following changes are not considered reductions in commitment:
a. The use of a quality assurance standard approved by the NRC that is more recent than the quality assurance standard in the certificate holder’s or applicant’s current quality assurance program at the time of the change.
b. The use of generic organizational position titles that clearly denote the position function, supplemented as necessary by descriptive text, rather than specific titles, provided that there is no substantive change to either the functions of the position or reporting responsibilities.
c. The use of generic organizational charts to indicate functional relationships, authorities, and responsibilities, or alternatively, the use of descriptive text, provided that there is no substantive change to the functional relationships, authorities, or responsibilities.
d. The elimination of quality assurance program information that duplicates language in quality assurance regulatory guides and quality assurance standards to which the quality assurance
program approval holder has com
mitted to on record.
e. Organizational revisions that ensure that persons and organizations performing quality assurance functions continue to have the requisite authority and organizational freedom, including sufficient independence from cost and schedule when opposed to safety considerations.
3.
Each quality assurance program approval holder shall maintain records of quality assurance program changes.
(g) The licensee, certificate holder, and applicant for a Certificate of Compliance shall maintain sufficient written records to describe the activities affecting quality.
1. The records shall include the following:
a. Changes to the quality assurance program as required by par. (f).
b. The documented instructions, procedures, or drawings of a type appropriate to the circumstances to prescribe quality assurance activities including appropriate quantitative and qualitative acceptance criteria for determining that activities important to quality have been satisfactorily accomplished.
c. Closely related specifications such as required qualifications of personnel, procedures, and equipment.
d
. the instructions or procedures which establish a records retention program that is consistent with applicable regulations and designates factors such as duration, location, and assigned responsibility.
2. The licensee, certificate holder, and applicant for a Certificate of Compliance shall retain these records for 3 years beyond the date when the licensee, certificate holder, and applicant for a Certificate of Compliance last engages in the activity for which the quality assurance program was developed. If any portion of the quality assurance program, written procedures or instructions is superseded, the licensee, certificate holder, and applicant for a Certificate of Compliance shall retain the superseded material for 3 years after it is superseded.
SECTION
9
5
.
DHS 157.94 (8
)
is
amended to read:
DHS 157.94
(8)
Preliminary Determinations
.
Prior to the first use of any packaging for the shipment of radioactive material a licensee shall
do all the following:
(a) Ascertain that there are no defects that could significantly reduce the effectiveness of the packaging.
(b) Where the maximum normal operating pressure will exceed 35 kilopascal (5
lb
/in2) gauge
, test the containment system at an internal pressure at least 50% higher than the maximum normal operating pressure to verify the capability of that system to maintain its structural integrity at that pressure.
(c) Determine that the packaging has been fabricated in accordance with the design approved by the nuclear regulatory commission.
(d) Conspicuously and durably mark the packaging with its model number, serial number, gross weight, and a package identification number as assigned by the nuclear regulatory commission.
ascertain
that the determination requirements in
10 CFR 71.85
(a) through (c) have been made
.
SECTION
9
6
.
DHS 157
Subchapter XV
is
created to read:
Subchapter XV
(title)
Subchapter XV
– Physical Protections of Category 1 and Category 2 Quantities of Radioactive Material
DHS 157.100
Personnel access authorization.
(1)
General Requirements
.
(a)
A licensee that possesses a quantity of radioactive material at or above the category 2
quantity of radioactive material
threshold shall establish, implement, and maintain
an
access authorization program
that
meet
s
the requirements of this subchapter.
(b) An applicant for a new license and a licensee that would become newly subject to the requirements of this subchapter upon application
to amend
its license shall implement the
requirements of this subchapter as appropriate and be inspected by the department before taking possession of a
category 1 or category 2 quantity of radioactive material.
(c)
A licensee that has not previously implemented the physical protection license condition requirements or been subject to the provisions of
this section and
ss.
DHS 157.
101
to
157.106
shall implement the provisions of
this section and
ss.
DHS 157.
101
to
157.106
before aggregating radioactive material to a quantity that equals or exceeds the category 2 threshold.
(2)
General Performance Objective
.
The licensee’s access authorization program shall ensure that the individuals specified in
sub.
(3) (
a
) a
re trustworthy and reliable.
(3)
Applicability
.
(
a)
A licensee shall subject
all of
the following individuals to
the
access authorization program
specified
under s.
DHS 157.101
:
1.
An individual whose assigned duties require unescorted access to category 1 or category 2 quantities of radioactive material or to any device that contains the radioactive material.
2.
An individual named as a r
eviewing official
for the licensee
.
(b)
A licensee need not subject the categories of individuals listed in s.
DHS 157.104 (1) (a)
to
(m)
to the investigation elements of the access authorization program.
(c)
Except as provided in par. (d), a
licensee shall approve for unescorted access to category 1 or category 2 quantities of radioactive material only those individuals with job duties that require unescorted access to category 1 or category 2 quantities of radioactive material.
(d)
A licensee may include individuals needing access to safeguards information-modified handling under
10 CFR 73
in the access authorization program under
this section and
ss.
DHS 157.
101
to
157.106
.
DHS 157.101
Access authorization program.
(1)
Granting Unescorted Access Authorization
.
(a) A licensee shall implement the requirements of this subchapter for granting initial or reinstated unescorted access authorization.
(b)
An individual
who
has
been determined to be trustworthy and reliable shall complete the security training required
under
s.
DHS 157.108 (3)
before being allowed unescorted access to category 1 or category 2 quantities of radioactive material.
(2)
R
eviewing Officials
.
(a)
Only a reviewing official
may make trustworthiness and reliability determinations that allow individuals to have unescorted access to category 1 or category 2 quantities of radioactive materials possessed by a licensee.
(b)
Each licensee shall name one or more individuals to be
a
reviewing official. After completing
a
background investigation on the reviewing official,
the
licensee shall provide
to the department
, under oath or affirmation, a
written
certification that the reviewing official is
deemed trustworthy and reliable by the licensee. The fingerprints of the named reviewing official shall be taken by a law enforcement agency,
a
federal or state
agency
that provide
s
fingerprinting services to the public, or
a
commercial fingerprinting
service
authorized by a state to take fingerprints.
Every 10 years, the
licensee shall recertify that the reviewing official is deemed trustworthy and reliable under s.
DHS 157.102 (
3
)
.
(c)
The licensee shall permit its reviewing official
to have unescorted access to category 1 or category 2 quantities of radioactive materials or access to safeguards information or safeguards information-modified handling, if
the
licensee possesses safeguards information or safeguards information-modified handling.
(d)
A reviewing official
may not approve other individuals to act as
a
reviewing
official
.
(e)
A reviewing official does not need to undergo a new background investigation before being named by a licensee as the reviewing official if any of the following apply:
1.
The individual has undergone a background investigation that included fingerprinting and a FBI criminal history records check and has been determined to be trustworthy and reliable by the licensee.
(3)
Informed Consent
. (a)
A licensee may not initiate a background investigation without the informed and signed consent of the individual. This consent shall include authorization to share personal information with other individuals or organizations as necessary to complete the background investigation. Before
making
a final adverse determination,
the
licensee shall provide the individual with an opportunity to correct any inaccurate or incomplete information that is
obtained
during the background investigation. A licensee does not need to obtain
a
signed consent from those individuals that meet the requirements of s.
DHS 157.102 (2)
. A signed consent shall be obtained before any reinvestigation.
(b)
The subject individual may withdraw consent
to a background investigation
at any time.
I
f an individual withdraws consent
for
a
background investigation
,
the
licensee shall
inform the individual of
all of
the following:
1.
The
licensee may not initiate any elements of the background investigation that were not in progress at the time the individual withdrew consent.
2.
A
withdrawal of consent for
a
background investigation is sufficient cause for denial or termination of unescorted access authorization.
(4)
Personal History Disclosure
.
An
individual who
applies
for unescorted access authorization shall disclose the personal history information that is required by
the
licensee’s access authorization program for the reviewing official to make a determination of the individual’s trustworthiness and reliability. Refusal to provide, or the falsification of, any
personal history information required
under
this subchapter is sufficient cause for denial or termination of unescorted access.
(5)
Determination Basis
. (a)
The reviewing official shall determine whether to permit, deny, unfavorably terminate, maintain, or administratively withdraw an individual’s unescorted access authorization based on an evaluation of all the information collected to meet the requirements of this subchapter.
(b)
The reviewing official may not permit any individual to have unescorted access until the reviewing official has evaluated all the information collected to meet the requirements of this
section
and
has
determined that the individual is trustworthy and reliable. The reviewing official may deny unescorted access to any individual based on information obtained at any time during the background investigation.
(c)
The reviewing official may terminate or administratively withdraw an individual’s unescorted access authorization based on information obtained after the background investigation has been completed and the individual
has been
granted unescorted access authorization.
(d)
A licensee shall document the basis for concluding whether or not there is reasonable assurance that an individual is trustworthy and reliable.
(e)
A licensee shall maintain a list of
individuals who are
approved for unescorted access authorization. When a licensee determines that
an individual
no longer requires unescorted access or
no longer
meets the access authorization requirement
s
, the licensee shall remove the
individual
from the approved list as soon as possible, but no later than 7 working days
of that determination
, and take prompt measures to ensure that the individual does not have unescorted access to
category 1 or category 2 quantities of radioactive
material.
(6)
Procedures
.
(a)
A licensee shall develop, implement, and maintain written procedures for implementing the access authorization program. The procedures shall include
provisions
for
providing
notification
to
individuals who are denied unescorted access
authorization
, or whose unescorted access
authorization
is terminated
;
provisions for the review of the decision
at the request of the affected individual
; and provisions allowing the individual
an opportunity to provide additional relevant information
.
(b
)
The notification
required under par. (
a
)
shall
include the grounds for denial or termination
and
the licensee’s procedures on
how the individual
may request a review of the
decision
to deny or terminate the individuals unescorted access authorization
.
(7)
Right to Correct and Complete Information
.
(a)
Before any final adverse determination
is made
, a licensee shall provide
to
each individual
who is
subject to
a background
investigation
under
this subchapter
,
written
notice that the individual may
complete, correct, and explain information obtained as a result of
the
background investigation.
A copy of the notice and confirmation of receipt of the notice
shall be maintained by the licensee for
one
year from the date of the
notice
.
(
b)
Challenge procedures may be initiated by an individu
a
l
who
believes that
criminal history
records obtained by the licensee
are
incorrect or incomplete in any respect
,
and
who
wishes to change, correct, update, or explain anything in the record. A licensee shall provide at least 10 days for an individual to challenge the results of a
n
FBI criminal history records check after the record is made available for
the individual’s
review. A licensee may make a final adverse determination based upon the criminal history records only after receipt of the FBI’s confirmation or correction of the record.
Note
:
These procedures include direct application
to the law enforcement agency that contributed the questioned information
by the individual challenging the record
,
or a direct challenge to the Federal Bureau of Investigation, Criminal Justice Information Services (CJIS) Division
regarding
the accuracy or completeness of any entry on the
individual’s
criminal history record
. In the latter case, the Federal Bureau of Investigation (FBI) will forward the challenge to the agency that submitted the data, and will request that the agency verify or correct the challenged entry. Upon receipt of an official communication directly from the agency that contributed the original information, the FBI Identification Division makes any changes necessary in accordance with the information supplied by that agency
.
An individual may challenge the accuracy or completeness of any entry on the criminal history record
by applying directly
to the Federal Bureau of Investigation, Criminal Justice Information Services (CJIS) Division,
ATTN
: SCU, Mod. D–2, 1000 Custer Hollow Road, Clarksburg, WV 26306 as set forth in
28 CFR 16.30
through
16.34
.
(8)
Records
. (a)
A licensee shall retain documentation regarding the trustworthiness and reliability of individual employees for 3 years from the date the individual no longer requires unescorted access to category 1 or category 2 quantities of radioactive material.
(b)
A licensee shall retain a
s a record for 3 years, a
copy of
any
superseded portion of the
access authorization program procedures
, and a copy of current access authorization program procedures
after they
are
no longer needed.
(c)
A licensee shall retain the list of persons approved for unescorted access authorization for 3 years after the list is superseded or replaced.
DHS 157.102 Background investigations.
(1)
Initial Investigation
. (a)
Before allowing an individual unescorted access to category 1 or category 2 quantities of radioactive material or to the devices that contain the material, a licensee shall complete a background investigation of the individual seeking unescorted access authorization. The scope of the investigation shall encompass at least the 7 years preceding the date of the background investigation or
the length of time
since the individual’s
eighteenth birthday
, whichever is shorter. The background investigation shall include at a minimum all
of
the following:
1.
Criminal History Check. The licensee shall conduct f
ingerprinting and a FBI identification and criminal history records check under s.
DHS 157.103
.
2.
Verification of true identity.
The
licensee shall verify the true identity of the
applicant.
The
licensee shall review official identification documents
including but not limited to
driver’s license; passport; government identification; certificate of birth issued by the state, province, or country of birth and compare the documents to personal information provided by the individual to identify any discrepancy in the information.
The
licensee shall document the type, expiration, and identification number of the identification document, or maintain a photocopy of identifying documents on file under s.
DHS 157.105
.
The
licensee shall certify in writing that the identification was properly reviewed, and shall maintain the certification and all related documents for review upon inspection.
3.
Employment history verification.
The
licensee shall
verify the
applicant’s
employment history, including military history
,
with each employer for the 7 years
immediately preceding
the date of application
.
4.
Verification of education.
The
licensee shall verify
any
educational credentials or experience claimed by the applicant.
5.
Character and reputation determination.
The
licensee shall complete reference checks to determine the character and reputation of the
applicant
.
Unless other references are not available, reference
s
may not be
obtained from
any person who is known to be a close member of the
applicant’s
family, including but not limited to the
applicant’s
spouse, parents, siblings, or children, or any individual who resides in the
applicant
’s
permanent household. Reference checks under this subchapter shall be
obtained for the
limited
purpose of
determining
whether
the
applicant
has been and continues to be trustworthy and reliable.
6.
Additional information. The licensee shall, to the extent possible, obtain independent information to corroborate
information
provided by the
applicant
,
including but not limited to
,
seeking
references not supplied by the
applicant
.
(b)
If a
current or
previous employer, educational institution, or any other entity with which the
applicant
claims to have been engaged
,
fails to provide information
,
or indicates an inability or unwillingness to provide information
,
or if a licensee cannot reach the entity
,
within a time frame considered appropriate by
the
licensee but
no more than
10 business days
after
the request
,
the
licensee shall document the refusal, unwillingness, or inability in the
background
investigation
record
and attempt to obtain the information from an alternate source.
(2)
Grandfathering
.
(a)
1.
Except as provided in
subd
.
2.
a
n
individual
who
has
been determined to be trustworthy and reliable for unescorted access to category 1 or category 2 quantities of radioactive material under the fingerprint orders may continue to have unescorted access to category 1 and category 2 quantities of radioactive material without further investigation.
2. An individual grandfathered under
subd
. 1.
shall
be subject to the reinvestigation requirement
under sub. (3)
.
(b)
1.
Except a provided under
subd
.
2. an individual
who
has
been determined to be trustworthy and reliable under
10 CFR 73
or the security orders for access to safeguards information, safeguards information-modified handling, or risk-significant material
,
may have unescorted access to category 1 and category 2 quantities of radioactive material without further investigation. A licensee shall document that the individual was determined to be trustworthy and reliable under
10 CFR 73
or a security order.
2. An individual grandfather
e
d under
subd
. 1.
shall
be subject to the reinvestigation requirement
under sub. 3
.
(3)
Reinvestigations
. A licensee shall conduct a reinvestigation every 10 years for any individual with unescorted access to category 1 or category 2 quantities of radioactive material. The reinvestigation shall consist of fingerprinting and a FBI identification and criminal history records check under s.
DHS 157.103
. The reinvestigations shall be completed within 10 years of the date on which
fingerprinting and a
n
FBI identification and criminal history records check under s.
DHS 157.103
were last completed.
DHS 157.103
Criminal history records checks of individuals granted unescorted access.
(1)
General Performance Objective And Requirements
.
(a)
Except for those individuals listed in s.
DHS 157.104
and those individuals grandfathered under s.
DHS 157.102 (2)
,
a
licensee subject to the provisions of this subchapter shall fingerprint each individual
seeking
unescorted access to category 1 or category 2 quantities of radioactive material.
The
licensee shall transmit all collected fingerprints to the NRC for transmission to the FBI.
The
licensee shall use the information received from the FBI as part of the required background investigation to determine whether
the individual will be
grant
ed
or den
ied
unescorted access to category 1 or category 2 quantities of radioactive materials.
(b)
The
licensee shall notify each affected individual that
the individual’s
fingerprints will be used to secure a review
of the indiv
i
dual’s
criminal history record, and
shall also provide notice to the individual
of the procedures for revising the record or adding explanations to the record.
(c)
Fingerprinting is not required if a licensee is reinstating an individual’s unescorted access authorization to category 1 or category 2 quantities of radioactive materials
and
all the following
apply
:
1.
The individual returns to the same facility that granted unescorted access authorization within 365 days of the termination of his or her unescorted access authorization.
2
.
The
individual’s
previous
unescorted
access
authorization
was terminated under favorable conditions.
(d)
Fingerprints do not need to be taken if an individual
,
who is an employee of a licensee, contractor, manufacturer, or supplier
,
has been granted unescorted access to category 1 or category 2 quantities of radioactive material
;
access to safeguards information
;
or safeguards information-modified handling by another licensee based upon a background investigation
conducted under this subchapter
, fingerprint orders, or
10 CFR
73
. An existing criminal history records check file may be transferred to a licensee asked to grant unescorted access under s.
DHS 157.105 (3)
.
(e)
A licensee shall use the information obtained as part of a criminal history records check solely to determine an individual’s suitability for unescorted access authorization to category 1 or category 2 quantities of radioactive materials
;
access to safeguards information
;
or safeguards information-modified handling.
(2)
Prohibitions
. (a)
A licensee may not base a final determination to deny an individual unescorted access authorization to category 1 or category 2 quantities of radioactive material solely on the basis of information received from the FBI
’s
criminal history records
indicating
any of the following:
1.
An arrest more than
one
year old for which there is no information of the disposition of the case.
2.
An arrest that resulted in dismissal of the charge or an acquittal.
(b)
A licensee may not use information received from a criminal history records check obtained under this subchapter in a manner that would infringe upon the rights of any individual under the
First Amendment
to the Constitution of the United States, nor shall licensees use the information in any way that would discriminate among individuals on the basis of race, religion, national
origin, gender, or age
.
(3)
Procedures for Processing of Fingerprint Checks
.
(a)
To comply with this subchapter, a licensee shall submit to the U.S. Nuclear Regulatory Commission, Director, Division of Facilities and Security, 11545 Rockville Pike, Rockville, Maryland 20852-2738, ATTN: Criminal History Program, Mail Stop T-03B46M, one completed, legible standard fingerprint card
(
Form FD–258, ORIMDNRCOOOZ
)
,
an
electronic fingerprint scan
,
or where practicable, other fingerprint record for each individual requiring unescorted access to category 1 or category 2 quantities of radioactive material. Copies of these forms may be obtained by writing the Office of
the Chief
Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, by calling 1–630-829-9565, or by email to
FORMS.Resource@nrc.gov
. Guidance on submitting electronic fingerprints can be found at
http://www.nrc.gov/site-help/esubmittals.html
.
(b)
Fees for the processing of fingerprint checks are due upon application.
The
licensee shall submit payment with the application for the processing of fingerprints through corporate check, certified check, cashier’s check, money order, or electronic payment, made payable to ‘‘U.S. NRC.’’ For guidance on making electronic payments, contact the Security Branch, Division of Facilities and Security at 301–415–7513. Combined payment for multiple applications is acceptable. The nuclear regulatory commission publishes the amount of the fingerprint check application fee on the NRC’s public
website
. To find the current fee amount, go to the Electronic Submittals page at
http://www.nrc.gov/site-help/e-submittals.html
and see the link for the Criminal History Program under Electronic Submission Systems.
(c)
The nuclear regulatory commission
will
forward to the submitting licensee all data received from the FBI as a result of a licensee’s application for criminal history records checks.
DHS 157.104
Relief from fingerprinting, identification, and criminal history records checks and other elements of background investigation.
(1)
Fingerprinting, and the identification and criminal history records checks required by
section 149 of the Atomic Energy Act of 1954,
as amended, and other elements of the background investigation are not required for the following individuals before granting unescorted access to category 1 or category 2 quantities of radioactive materials:
(a)
An employee of the commission or of the executive branch of the U.S. government who has undergone fingerprinting for a prior U.S. government criminal history records check.
(b)
A member of Congress.
(c)
An employee of a member of Congress or congressional committee who has undergone fingerprinting for a prior U.S. government criminal history records check.
(d)
The Governor of a state or his or her designated state employee representative.
(e)
Federal, state, or local law enforcement personnel.
(f)
State
radiation control program directors
and
state homela
n
d security advisors
or their designated state employee representatives.
(g)
Agreement
state
employees conducting security inspections on
behalf of the NRC under an agreement executed under s
ection 274.i. of the Atomic Energy Act.
(h)
Representatives of the International Atomic Energy Agency (IAEA) engaged in activities associated with the U.S. IAEA Safeguards Agreement who have been certified by the NRC.
(i)
Emergency response personnel who are responding to an emergency.
(j)
Commercial vehicle drivers for road shipments of
category 1 and
category 2 quantities of radioactive material.
(k)
Package handlers at transportation facilities such as freight terminals and railroad yards.
(
L
)
Any individual who has an active federal security clearance, provided that he or she makes available
to the licensee
the appropriate documentation. Written confirmation from the agency or employer or both that granted the federal security clearance or reviewed the criminal history records check shall be provided to a licensee.
The
licensee shall retain documentation
of an individual’s federal security clearance and written confirmation from the agency, employer, or
both that granted the federal security clearance or reviewed the criminal history records check
for 3 years from the date the individual no longer requires unescorted access to category 1 or category 2 quantities of radioactive material.
(m)
Any individual employed by a service provider licensee for which the service provider licensee has conducted the background investigation for the individual and approved the individual for unescorted access to category 1 or category 2 quantities of radioactive material.
The
service provider
license
shall
provide written
verification
to the licensee.
The
licensee shall retain the documentation
of the written verification
for 3 years from the date the individual no longer requires unescorted access to category 1 or category 2 quantities of radioactive material.
(2)
Fingerprinting, and the identification and criminal history records checks required by
section 149 of the Atomic Energy Act of 1954, as amended
, are not required for an individual who has had a favorably adjudicated U.S. Government criminal history records check within the last 5 years, under a comparable U.S. Government program involving fingerprinting and a FBI identification and criminal history records check provided that he or she makes available the appropriate documentation. Written confirmation from the agency or employer or both that reviewed the criminal history records check shall be provided to the licensee. A licensee shall retain
the provided
documentation for 3 years from the date the individual no longer requires unescorted access to category 1 or category 2 quantities of radioactive material. These programs include, but are not limited to the following:
(a)
National Agency Check.
(b)
Transportation Worker Identification Credentials (TWIC) under
49 CFR 1572
.
(c)
Bureau of Alcohol, Tobacco, Firearms, and Explosives background check and clearances under
27 CFR
555
.
(
d
)
Health and Human Services security risk assessments for possession and use of select agents and toxins under
42 CFR 73
.
(e)
Hazardous Material security threat assessment for hazardous material endorsement to commercial driver’s license
under
49 CFR 1572
.
(f)
Customs and Border Protection’s Free and Secure Trade (FAST) Program.
DHS 157.105 Protection of information.
(1)
Any licensee who obtains background
investigation
information on an individual under this subchapter shall establish and maintain a system of files and written procedures for protection of the record and the personal information from unauthorized disclosure.
(2)
A licensee may not disclose the
background investigation
record or personal
history
information collected and maintained to persons other than the subject individual,
the individual’s
representative, or to
persons
who
need access
to the information in
order
to
perform assigned duties in the process of granting or denying unescorted access to category 1 or category
2 quantities of radioactive material, safeguards information, or safeguards information-modified handling. No individual authorized to have access to the information may disseminate the information to any other individual who does not have a need to know.
(3)
The personal information obtained on an individual from a background
inv
estigation may be provided to another licensee
under the following conditions
:
(a)
Upon the individual’s written request to a licensee holding the data to disseminate the information contained in
the individual’s
file.
(b)
The recipient licensee verifies information such as name, date of birth, social security number, gender, and other applicable physical characteristics.
(4)
The
licensee shall make background investigation records obtained under this subchapter available for examination by the department.
(5)
The
licensee shall retain all fingerprint and criminal history records
received from the FBI
, including data indicating no record, , or a copy of these records if the individual’s file has been transferred, for 3 years from the date the individual no longer requires unescorted access to category 1 or category 2 quantities of radioactive material.
DHS 157.106 Access authorization program review
.
(1)
Each licensee shall be responsible for the continuing effectiveness of
its
access authorization program. Each licensee shall ensure that
its
access authorization
program is
reviewed
for
compliance with the requirements of this subchapter and that comprehensive actions are taken to correct any
identified
. The
licensee
shall evaluate all program performance objectives and requirements. Each licensee shall periodically,
and
at least annually, review
its
access
authorization
program content and implementation.
(2)
The
licensee shall document the
results of
its access authorization program
review
and
any recommendations.
Documentation of the review
shall identify conditions that are adverse to the proper performance of the access authorization program, the cause of the condition
s
, and, when appropriate, recommend
ed
corrective actions, and corrective actions taken. A licensee shall review the
results
of its access authorization program review
and take any additional corrective actions necessary to preclude repetition of the
condition, including
additional review
.
(3)
The licensee shall maintain it access authorization program review
records
for 3 years.
DHS 157.107 Security program.
(1)
Applicability
.
(a)
Any licensee that possesses a category 1 or category 2 quantity of radioactive material shall establish, implement, and maintain a security program under the requirements of this subchapter.
(b)
An applicant for a new license and any licensee that would become newly subject to the requirements of this subchapter upon application for amendment of its license shall
implement the
applicable
requirements of this subchapter and be inspected by the department, before taking possession of a category 1 or category 2 quantity of radioactive material.
(c)
Any licensee that has not previously implemented the physical protection license condition requirements or been subject to ss.
DHS 157.107
to
157.115
shall provide written notification to the department at least 90 days before aggregating radioactive material to a quantity that equals or exceeds the category 2 threshold.
(2)
General Performance Objective
.
Each licensee shall establish, implement, and maintain a security program that is designed to monitor and
immediately
detect, assess, and respond to an actual or attempted unauthorized access to category 1 or category 2 quantities of radioactive material.
(3)
Program Features
. Each licensee’s security program shall
comply with
ss.
DHS 157.108
to
157.114
, as applicable
.
DHS 157.108 General security program requirements.
(1)
Security Plan
.
(a)
Any licensee identified in s.
DHS 157.107 (1)
shall develop a written security plan specific to its facilities and operations
specifying the
overall security strategy
t
hat
ensures
the integrated and effective functioning of the security program required by this subchapter.
At a minimum, t
he security plan shall:
1.
Describe the measures and strategies used to implement the requirements of this subchapter.
2.
Identify the security resources, equipment, and technology used to satisfy the requirements of this subchapter.
(b)
The security plan shall be reviewed and approved by the individual with overall responsibility for the security program.
(c)
A licensee shall revise its security plan as necessary to ensure the department’s requirements
are effectively implemented
. A licensee shall ensure all
of
the following:
1.
The revision
to
the security plan
has been reviewed and approved by the individual with overall responsibility for the security program.
2.
I
ndividuals
affected by the revised security plan
are
notified and given
instruct
ion
about
changes
to the plan
before they
are implemented.
(d)
A licensee shall retain a copy of the current security plan as a record for 3 years after the security plan is no longer required.
A
licensee shall retain
a record of any
superseded
portion of the security plan
for 3 years after
it
is superseded.
(2)
Implementing Procedures
. (a)
A licensee shall develop and maintain written procedures that document how the requirements of this subchapter and the security plan will be
implemented
.
(b)
The implementing procedures and revisions to these procedures shall be approved in writing by the individual with overall responsibility for the security program.
(c)
A licensee shall retain a copy of the current
implementing
procedure
s
as a record for 3 years after
they are
no longer
required
.
A
licensee shall retain
a record of any
superseded
portion of the
implementing procedures
for 3 years after
they are
superseded.
(3)
Training
. (a)
A licensee shall conduct training to ensure that individuals implementing the security program possess and maintain the knowledge, skills, and abilities
required
to carry out their assigned duties and responsibilities effectively. The training shall include instruction in all the following:
1.
The licensee’s security program
,
implementing
procedures
, and the
purposes and functions of the security measures employed
to secure category 1 or category 2 quantities of radioactive material
.
2.
The responsibility to report promptly to the licensee any condition that causes or may cause a violation of the department’s requirements.
3.
The responsibility of the licensee to report promptly to the
LLEA
and licensee any actual or attempted theft, sabotage, or diversion of category 1 or category 2 quantities of radioactive material.
4.
The appropriate response to security alarms.
(b)
In determining those individuals who
will
be trained on the security program, a
licensee shall consider each individual’s assigned activities during authorized use and response to potential situations involving actual or attempted theft, diversion, or sabotage of category 1 or category 2 quantities of radioactive material. The extent of the training
provided
to
an individual
shall be commensurate with the individual’s potential involvement in the security of category 1 or category 2 quantities of radioactive material.
(c)
Refresher training shall be provided at a frequency not to exceed 12 months and when significant changes have been made to the security program.
Refresher
training shall include all
of
the following
:
1.
Review of the training requirements
under
sub. (3)
and
any changes made to the security program since the last training.
2.
Reports on any relevant security issues, problems, and lessons learned.
3.
Relevant results of the department’s inspections.
4.
Relevant results of the licensee’s program review and testing and maintenance.
(d)
A licensee shall maintain records of the initial and refresher training for 3 years from the date of the training. The training records shall include dates of the training, topics covered,
a
list of licensee personnel in attendance, and related information.
(4)
Protection of Information
.
(a)
A licensee authorized to possess category 1 or category 2 quantities of radioactive material shall limit access to and unauthorized disclosure of their security plan, implementing procedures, and the list of individuals that have been approved for unescorted access.
(b)
Efforts to limit access shall include the development, implementation, and maintenance of written policies and procedures for controlling access to, and for proper handling and protection against unauthorized disclosure of the security plan and implementing procedures.
(c)
Before granting an individual access to the security plan or implementing procedures, a licensee shall do all
of
the following:
1.
Evaluate an individual’s need to know the security plan or implementing procedures.
2.
If the individual has not been authorized for unescorted access to category 1 or category 2 quantities of radioactive material, safeguards information, or safeguards information-modified handling,
the
licensee shall complete a background investigation to determine the individual’s trustworthiness and reliability. A trustworthiness and reliability determination shall be conducted by the reviewing official and shall include the background investigation elements contained in s.
DHS 157.102 (1) (a) 2.
to
6.
and
(
b
)
.
(d)
A licensee need not subject any of the following individuals to the background investigation elements for protection of information:
2.
Employees of s
ecurity service provider
s for whom
written verification
has been provided to the licensee
by the security service provider
that indicates
the employee has been determined to be trustworthy and reliable
based upon
the background investigation
elements contained
in s
s
.
DHS 157.102 (1) (a) 2.
to
6.
and
DHS 157.102
(2)
.
(e)
A licensee shall document the basis for concluding that an individual is trustworthy and reliable and should be granted access to the security plan or implementing procedures.
(f)
A licensee shall maintain a list of persons currently approved for access to the security plan or implementing procedures. When a licensee determines that a person no longer needs access to the security plan or implementing procedures or no longer meets the access authorization requirements for access to the information, the licensee shall remove the person from the approved list as soon as possible, but no later than 7 working days, and take prompt
measures to ensure that the individual cannot obtain the security plan or implementing procedures.
(g)
When not in use, a licensee shall store its security plan and implementing procedures in a manner to prevent unauthorized access. Information stored in non-removable electronic form shall be password protected.
(h)
A licensee shall retain all
of
the following as a record for 3 years after the document is no longer needed:
1.
A copy of the information protection procedures.
2.
The list of individuals approved for access to the security plan or implementing procedures.
DHS 157.109 LLEA coordination
.
(1)
A licensee subject to this subchapter shall coordinate, to the extent practicable, with an LLEA for responding to threats to a licensee’s facility, including any necessary armed response. The information provided to the LLEA shall include all the following:
(a)
A description of the facilities and the category 1 and category 2 quantities of radioactive materials along with a description of the security measures that have been implemented
by the licensee
to comply with this subchapter.
(b)
A notification that the licensee will request a timely armed response by the LLEA to any actual or attempted theft, sabotage, or diversion of category 1 or category 2 quantities of material.
(2)
A licensee shall notify the department within 3 business days if any of the following occur:
(a)
The LLEA has not responded to the request for coordination within 60 days of the coordination request.
(b)
The LLEA notifies the licensee that the LLEA does not plan to participate in coordination activities.
(3)
A licensee shall document its efforts to coordinate with the LLEA. The documentation shall be kept for 3 years.
(4)
A licensee shall coordinate with the LLEA at least every 12 months, or when changes to the facility design or operation adversely affect the
licensee’s
potential
vulnerability to theft, sabotage, or diversion
of its material
.
DHS 157.110 Security zones.
(1)
A licensee shall ensure that all category 1 and category 2 quantities of radioactive material are used or stored within licensee established security zones. Security zones may be permanent or temporary.
(2)
Temporary security zones shall be established as necessary to meet a licensee’s transitory or intermittent business activities, such as periods of maintenance, source delivery, and source replacement.
(3)
U
nescorted access
to security zones
by
shall
only be permitted
to
approved
individuals
through
the following conditions
, or combinations of conditions
:
(a)
C
ategory 1 and category 2 quantities of radioactive materials
are isolated
by the use of continuous physical barriers that allow access to the security zone only through established access control points. A physical barrier is a natural or man-made structure or formation sufficient for the isolation of the category 1 or category 2 quantities of radioactive material within a security zone.
(b)
The
security zone
is directly controlled
by approved individuals at all times.
(4)
For category 1 quantities of radioactive material during periods of maintenance, source receipt, preparation for shipment, installation, or source removal or exchange, a licensee shall, at a minimum, provide sufficient
numbers of
individuals approved for unescorted access to maintain continuous surveillance of sources in temporary security zones and in any security zone in which physical barriers or intrusion detection systems have been disabled to allow such activities.
(5)
Individuals not approved for unescorted access to category 1 or category 2 quantities of radioactive material shall be escorted by an approved individual when in a security zone.
DHS 157.111 Monitoring, detection
,
assessment
,
communication
, and response
.
(1)
Monitoring and Detection
.
(a)
A licensee shall establish and maintain the capability to continuously monitor and
immediately
detect all unauthorized entries into its security zones. A licensee shall provide the means to maintain continuous monitoring and detection capability if the primary power source is lost, or provide for an alarm and response if this capability to continuously monitor and
immediately
detect unauthorized entries is lost.
(b)
Monitoring and detection shall be performed by at least one of the following:
1.
A monitored intrusion detection system that is linked to an onsite or offsite central monitoring facility.
2.
Electronic devices for intrusion detection alarms that will alert nearby facility personnel.
3.
A monitored video surveillance system.
4.
Direct visual surveillance by approved individuals located within the security zone.
5.
Direct visual surveillance by a licensee designated individual located outside the security zone.
(c)
A licensee subject to this subchapter shall detect unauthorized removal of the radioactive material from the security zone
by establishing and maintain
ing the following capabilities:
1.
For category 1 quantities of radioactive material, immediate detection of any attempted unauthorized removal of the radioactive material from the security zone. Immediate detection capability shall be provided by any of the following:
a.
Electronic
sensors linked to an alarm.
b.
Continuous
monitored video surveillance.
c.
Direct
visual surveillance.
2.
For category 2 quantities of radioactive material, weekly verification through physical checks, tamper indicating devices, use, or other means to ensure that the radioactive material is present.
(2)
Assessment of Actual or Attempted Unauthorized Entry
. A licensee shall immediately assess each actual or attempted unauthorized entry into the security zone to determine whether the unauthorized access was an actual or attempted theft, sabotage, or diversion.
(3)
Personnel Communications and Data Transmission
. For personnel and automated or electronic systems supporting a licensee’s monitoring, detection, and assessment systems, a licensee shall comply with all
of
the following:
(a)
Maintain continuous
communication capability for personnel
and electronic data transmission and processing
capability
among site security systems.
(b)
Provide an alternative communication capability for personnel, and an alternative data transmission and processing capability if the primary means of communication or data transmission and processing is lost.
Alternative communications and data transmission systems
shall
not be subject to the same failure modes as the primary systems.
(4)
Response to Actual or Attempted Unauthorized Access, Theft, Sabotage, or Diversion
. A licensee shall immediately respond to any actual or attempted unauthorized access to the security zones, or actual or attempted theft, sabotage, or diversion of category 1 or category 2 quantities of radioactive material at licensee facilities or temporary job sites. For any unauthorized access involving an actual or attempted theft, sabotage, or diversion of category 1
or category 2 quantities of radioactive material, a licensee’s response shall include
immediately
requesting
an armed response from the LLEA.
DHS 157.112 Maintenance and testing.
(1)
Any licensee subject to this subchapter shall implement
a maintenance
and testing program to ensure that intrusion alarms, associated communication systems, and other physical components of the systems used to secure or detect unauthorized access to radioactive material are maintained in operable condition and are capable of performing their intended function when needed.
The equipment relied on to meet the security requirements of this subchapter shall be inspected and tested for operability and performance
at the frequency suggested by
the manufacturer. If there is no suggested frequency
by the manufacturer
, testing shall be performed
, at a minimum, every
12 months.
(2)
A licensee shall maintain records
documenting
maintenance and testing
activities for 3 years.
DHS 157.113 Requirements for mobile devices.
(1)
Any licensee that possesses mobile devices containing category 1 or category 2 quantities of radioactive material shall comply with all the following:
(a)
Have
2
independent physical controls
,
form
ing
tangible barriers
that
secure the material from unauthorized removal when the
mobile
device is not under direct control and constant surveillance by the licensee.
(b)
For
a mobile device
in or on a vehicle or trailer, unless the health and safety requirements for a site prohibit the disabling of the vehicle, a licensee shall use a method to disable the vehicle or trailer when not under direct control and constant surveillance by the licensee. A licensee shall not rely on the removal of an ignition key to meet this requirement.
DHS 157.114 Security program review.
(1)
Each licensee shall be responsible for the continuing effectiveness of the security program. Each licensee shall
review the security program
to confirm compliance with the requirements of this subchapter and
to ensure
that comprehensive actions are taken to correct any noncompliance. The
licensee shall
review the radioactive material security program content and implementation periodically,
and
at least annually.
(2)
The licensee shall document the results of the review, along with any recommendations,
identify conditions that are adverse to the proper performance of the security program, the cause of the condition, and, when appropriate, recommend corrective actions, and corrective actions taken. A licensee shall review the
results of the review
and take any additional corrective actions necessary to preclude repetition of
adverse
condition
s
, including
further review.
(3)
A licensee shall maintain the review documentation for 3 years.
DHS 157.115 Reporting events.
(1)
A licensee shall immediately notify the LLEA after determining that an unauthorized entry resulted in an actual or attempted theft, sabotage, or
diversion of a category 1 or category 2 quantity of radioactive material.
A
licensee shall notify the department by telephone
a
s
soon as possible after initiating a response, but not at the expense of causing delay or interfering with the LLEA response to the event. In no case shall the notification to the department be later than 4 hours after the discovery of any attempted or actual theft, sabotage, or diversion.
(2)
A licensee shall assess any suspicious activity related to possible theft, sabotage, or diversion of category 1 or category 2 quantities of radioactive material and notify the LLEA as appropriate.
A
licensee shall notify the department by telephone
a
s
soon as possible but not later than 4 hours after notifying the LLEA.
(3)
Within 30 days of the initial notification
by phone
required in subs. (1) and (2)
,
the licensee
shall
also submit
a written
report to
the department. The
written
report shall include sufficient information for department analysis and evaluation, including identification of any necessary corrective actions to prevent future instances.
Note:
The department may be contacted at: Department of Health Services, Radiation Protection Section, P.O. Box 2659, Madison, WI, 53701−2659. Telephone contact is: 608−267−4797 during normal business hours or 608−258−0099 after hours.
DHS 157.116 Additional requirements for transfer of category 1 and category 2 quantities of radioactive material.
A licensee transferring a category 1 or category 2 quantity of radioactive material to a licensee of the department, the
N
RC
, or another
agreement state
shall meet all
of
the following license verification provisions instead of those listed in s.
DHS 157.13
(15)
(d)
:
(1)
Before
transferring a
category 1
quantity
of radioactive material, the licensee making the transfer
shall verify with the NRC’s license verification system or the license issuing authority that the transferee’s license authorizes the receipt of the type, form, and quantity of radioactive material to be transferred and that the
transferee
is authorized to receive radioactive material at the location requested for delivery. If the verification is conducted by contacting the license issuing authority, the
licensee making the transfer
shall document the verification.
Verification is not needed for
transfers within the same organization.
(2)
Before
transferring a
category 2
quantity
of radioactive material, the licensee making the transfer
shall verify with the NRC’s license verification system or the license issuing authority that the transferee’s license authorizes the receipt of the type, form, and quantity of radioactive material to be transferred. If the verification is conducted by contacting the license issuing authority, the transferor shall document the verification.
Verification is not needed for
transfers within the same organization.
(3)
In an emergency where a licensee
making the transfer
cannot reach the license issuing authority and the license verification system is nonfunctional, a licensee may accept a written certification by the transferee that it is authorized by license to receive the type, form, and quantity of radioactive material to be transferred. The certification shall include the
transferee’s
license number, current revision number, issuing agency, expiration date, and for a category 1
shipment
,
the authorized address.
The
licensee
making the transfer
shall keep a copy of the certification
and
shall confirm the
certification
through
the NRC’s license verification system or by contacting the license issuing authority by the end of the next business day.
(4)
The
licensee transferring the
radioactive material
shall keep a copy of the verification documentation as a record for 3 years.
(2)
For shipments of category 2 quantities of radioactive material, each shipping licensee shall comply with the requirements for physical protection contained in ss.
DHS 157.118 (2)
to
(5)
,
157.120 (1) (b)
and
(c)
,
(2) (b)
, and
(3)
,
157.121 (2)
,
(4)
, and
(6)
to
(8)
. For those shipments of category 2 quantities of radioactive material that meet the criteria of s.
DHS 157.94 (5) (b)
, the shipping licensee shall also comply with the advance notification provisions of s.
DHS 157.94 (5)
.
(3)
The shipping licensee shall be responsible for meeting the requirements of this subchapter unless the receiving licensee has agreed in writing to
implement the
physical protection
requirements
under this subchapter
for materials in transit
.
DHS 157.118
Preplanning and coordination
of shipments
.
(1)
Any licensee that plans to transport, or deliver to a carrier for transport, licensed material that is a category 1 quantity of radioactive material outside the confines of the licensee’s facility or other place of use or storage shall complete all
of
the following:
(a)
Preplan and coordinate shipment arrival and departure times with the receiving licensee.
(b)
Preplan and coordinate shipment information with the governor or the governor’s designee of any state through which the shipment will pass to discuss the state’s intention to provide law enforcement escorts and identify safe havens.
(c)
Document the preplanning and coordination activities.
(2)
Any licensee that plans to transport, or deliver to a carrier for transport, licensed material that is a category 2 quantity of radioactive material outside the confines of the licensee’s facility or other place of use or storage shall coordinate the shipment no-later-than arrival time and the expected shipment arrival with the receiving licensee. A licensee shall document the coordination activities.
(3)
Any licensee who receives a shipment of a category 2 quantity of radioactive material shall confirm receipt of the shipment with the originator. If the shipment has not arrived by the no-later-than arrival time, the receiving licensee shall notify the originator.
(4)
Any licensee who transports or plans to transport a shipment of a category 2 quantity of radioactive material, and determines that the shipment will arrive after the no-later-than arrival time provided under sub. (2
),
shall promptly notify the receiving licensee of the new no-later-than arrival time.
(5)
A licensee shall retain a copy of the documentation for preplanning and coordination, and any revision thereof, as a record for 3 years.
DHS 157.119
Advance notification of shipment
.
A
licensee shall provide advanced notification
, as provided in subs. (1) and (2)
,
of
the shipment of licensed material in a category 1 quantity,
to, within,
or across the boundary of the state, before the
shipment
, or
before
delivery to a carrier for
shipment
of the licensed material outside the confines of the licensee’s facility or other place of use or storage.
(1)
Procedures for Submitting Advance Notification
.
(a)
The notification shall be made to the department and to the office of each governor or governor’s designee
of
any state to, within, or
through which the material is shipped
. The contact information, including telephone and mailing addresses, of governors and governors’ designees, is available on the U.S. Nuclear Regulatory Commission website at http://
http://scp.nrc.gov/special/designee.pdf
. A list of the contact information is also available upon request from the Director, Division of Material Safety, State, Tribal, and Rulemaking Programs, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commissi
on, Washington, DC 20555–0001.
(b)
A notification delivered by mail shall be postmarked at least 7 days before transport of the shipment commences at the shipping facility.
(c)
A notification delivered by any means other than mail shall reach the department at least 4 days before the transport of the shipment commences and shall reach the office of
any
governor or the governor's designee at least 4 days before transport of a shipment
to,
within
,
or through the state.
Note: The department may be contacted at: Department of Health Services, Radiation Protection Section, P.O. Box 2659, Madison, WI, 53701−2659. Telephone contact is: 608−267−4797 during normal business hours or 608−258−0099 after hours.
(2)
Information To Be Furnished in Advance Notification
.
Each advance notification of shipment of category 1 quantities of radioactive material shall contain all
of
the following information, if available at the time of notification:
(a)
The name, address, and telephone number of the shipper, carrier, and receiver of the category 1 radioactive material.
(b)
The license numbers of the shipper and receiver.
(c)
A description of the radioactive material contained in the shipment, including the radionuclides and quantity.
(d)
The point of origin of the shipment and the estimated time and date that shipment will commence.
(e)
The estimated time and date that the shipment is expected to enter each state along the route.
(f)
The estimated time and date of arrival of the shipment at the destination.
(g)
A point of contact, with a telephone number, for current shipment information.
(3)
Revision Notice
. (a)
A licensee shall provide any information not previously available at the time of the initial notification, as soon as the information becomes available but not later than commencement of the shipment, to the governor of the state or the governor’s designee and to the department.
(b)
A licensee shall promptly notify the governor of the state or the governor’s designee of any changes to the information provided under subs. (1) and
(3) (a). A licensee shall also
immediately notify the department of any such changes.
(4)
Cancellation Notice
.
Any licensee who cancels a shipment for which advance notification has been sent shall send a cancellation notice to the
department and to the
governor of each state or to the governor’s designee previously notified.
The licensee shall send the cancellation notice before the shipment would have commenced or as soon thereafter as possible. The licensee shall state in the notice that it is a cancellation and identify the advance notification that is being cancelled.
(5)
Records
.
A licensee shall retain a copy of the advance notification and any revision and cancellation notices as a record for 3 years.
(6)
Protection of Information
.
State officials, state employees, and other individuals, whether or not licensees of the Commission or an Agreement State, who receive schedule information of the kind specified in sub.
(2)
shall
protect that information against unauthorized disclosure as specified in s.
DHS 157.108 (4)
.
DHS 157.120
Physical protection during shipment.
(1)
Shipments by Road
.
(a)
Any licensee who transports, or delivers to a carrier for transport, in a single shipment, a category 1 quantity of radioactive material
by road
shall do all the following:
1.
Ensure that movement control centers are established
to
maintain position information
of the shipment
from a remote location. These
movement
control centers shall monitor shipments
at all times
, and have the ability to
immediately
communicate
with the appropriate law enforcement agencies
in an emergency
.
2.
Ensure that redundant communications are established that allow the transport
er
to contact the escort vehicle and movement control center at all times. Redundant communications
shall
not be subject to the same interference factors as the primary communication.
3.
Ensure that shipments are continuously and actively monitored by a telemetric position monitoring system or an alternative tracking system reporting to a movement control center. A movement control center shall provide positive confirmation of the location, status, and control over the shipment.
The movement control center shall be prepared to promptly implement preplanned procedures in response to deviations from the authorized route or a notification of actual, attempted, or suspicious activities related to the theft, loss, or diversion of a shipment. These procedures will include, but not be limited to, the identification of and contact information for the appropriate LLEA along the shipment route.
4.
Provide an individual to accompany the driver for highway shipments with a driving time period greater than the maximum number of allowable hours of service in a 24-hour duty day as established by the U.S. department of transportation federal motor carrier safety administration. The accompanying individual may be another driver.
5.
Develop written normal and contingency procedures to address all the following:
a.
Notifications to the communication center and law enforcement agencies.
b.
Communication protocols. Communication protocols shall include a strategy for the use of authentication codes and duress codes and provisions for refueling or other stops, detours, and locations where communication is expected to be temporarily lost.
c.
Loss of communications.
d.
Responses to an actual or attempted theft or diversion of a shipment.
6.
E
nsure that drivers, accompanying personnel, and movement control center personnel have access to the normal and contingency procedures.
(b)
Any licensee that transports category 2 quantities of radioactive material shall maintain constant control or surveillance or both during transit and have the capability for immediate communication to summon appropriate response or assistance.
(c)
Any licensee who delivers to a carrier for transport, in a single shipment, a category 2 quantity of radioactive material shall do all
of
the following:
1.
Use carriers that have established package tracking systems. An established package tracking system is a documented, proven, and reliable system routinely used to transport objects of value. In order for a package tracking system to maintain constant control or surveillance or both, the package tracking system shall allow the shipper or transporter to identify when and where the package was last and when it should arrive at the next point of control.
2.
Use carriers that maintain constant control or surveillance or both during transit and have the capability for immediate communication to summon appropriate response or assistance; and
3.
Use carriers that have established tracking systems that require an authorized signature before releasing the package for delivery or return.
(2)
SHIPMENTS BY RAIL.
(a)
Any licensee who transports, or delivers to a carrier for transport, in a single shipment, a category 1 quantity of radioactive material
by rail
shall do all the following:
1.
Ensure that rail shipments are monitored by a telemetric position monitoring system or an alternative tracking system
that reports
to the licensee, third party, or railroad communications center. The communications center shall provide positive confirmation of the location of the shipment and its status. The communications center shall implement preplanned procedures in response to deviations from the authorized route or to a notification of actual, attempted, or suspicious activities related to the theft or diversion of a shipment. These procedures will include, but not be limited to, the identification of and contact information for the appropriate LLEA along the shipment route.
2.
Ensure that periodic reports to the communications center are made at preset intervals.
(b)
Any licensee who transports, or delivers to a carrier for transport, in a single shipment, a category 2 quantity of radioactive material
by rail
shall do all the following:
1.
Use carriers that have established package tracking systems. An established package tracking system is a documented, proven, and reliable system routinely used to transport objects of value. In order for a package tracking system to maintain constant control or surveillance or both, the package tracking system shall allow the shipper or transporter to identify when and where the package was last reported and when it should arrive at the next point of control.
2.
Use carriers that maintain constant control or surveillance or both during transit and have the capability for immediate communication to summon appropriate response or assistance
.
3.
Use carriers that have established tracking systems that require an authorized signature before releasing the package for delivery or return.
(3)
Investigations
.
Any licensee who makes arrangements for the shipment of category 1 quantities of radioactive material
shall immediately conduct an investigation upon the discovery that a category 1 shipment is lost or missing. Any licensee who makes arrangements for the shipment of category 2 quantities of radioactive material shall immediately conduct an investigation, in coordination with the receiving licensee, of any shipment that has not arrived by the designated no-later-than arrival time.
DHS 157.121 Reporting of events during shipping.
(1)
The
shipping
licensee shall notify the LLEA
in the area of the shipment’s last confirmed location
and the department by telephone
within
one
hour of its determination that a shipment of category 1 quantities of radioactive material is lost or missing. During the investigation required by s.
DHS 157.120 (3)
, the shipping licensee
shall
provide agreed upon updates to the department on the status of the investigation.
(2)
The shipping licensee shall
initially
notify the department by telephone within 4 hours of the shipping licensee’s determination that a shipment of category 2 quantities of radioactive material is lost or missing.
The licensee shall further notify the department, if
the radioactive material has not been located and secured
after 24 hours of
the initial
determination that the shipment is lost or missing.
(3)
The shipping licensee shall notify the designated LLEA along the shipment route as soon as possible upon discovery of any actual or attempted theft or diversion of a shipment or suspicious activities related to the theft or diversion of a shipment of a category 1 quantity of radioactive material. As soon as possible after notifying the LLEA, the licensee shall notify the department by telephone upon discovery of any actual or attempted theft or diversion of a shipment, or any suspicious activity related to the shipment of category 1 radioactive material.
(4)
The shipping licensee shall notify the department by telephone as soon as possible upon discovery of any actual or attempted theft or diversion of a shipment, or any suspicious activity related to the shipment, of a category 2 quantity of radioactive material.
(5)
The shipping licensee shall notify the department by telephone and the LLEA as soon as possible upon recovery of any lost or missing category 1 quantities of radioactive material.
(6)
The shipping licensee shall notify the department by telephone as soon as possible upon recovery of any lost or missing category 2 quantities of radioactive material.
(7)
The licensee shall submit a written report to the department within 30 days of providing the telephone notification to an LLEA or the department of the discovery of any actual or attempted theft or diversion of a shipment under subs. (1) to (4). A written report is not required for notifications of suspicious activities related to a shipment.
The report shall set forth all the following information:
(a)
A description of the licensed material involved, including kind, quantity, and chemical and physical form.
(b)
A description of the circumstances under which the loss or theft occurred.
(c)
A statement of disposition, or probable disposition, of the licensed material involved.
(d
)
Actions that have been taken, or will be taken, to recover the material.
(e)
Procedures or measures that have been, or will be, adopted to ensure against a recurrence of the loss or theft of licensed material.
(8)
After filing the written report
under sub. (7)
, a licensee shall report to the department any additional substantive information on the loss or theft
of
the category 1 or category 2 quantity of radioactive material
within 30 days after the licensee learns of such information.
Note:
The department may be contacted at: Department of Health Services, Radiation Protection Section, P.O. Box 2659, Madison, WI, 53701−2659. Telephone contact is: 608−267−4797 during normal business hours or 608−258−0099 after hours.
DHS 157.122
Record requir
e
ments for the p
hysical protection of
Category
1 and 2 quantities of radioactive material.
(1)
Form of Records
.
Each record required by this subchapter shall be legible throughout the retention period specified
under
sub. (2).
The
record may be the original or a reproduced copy or a microform, provided that the copy or microform is authenticated by authorized personnel and that the microform is capable of producing a clear copy throughout the required retention period. The record may also be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period.
Records such as letters, drawings, and specifications shall include all pertinent information such as stamps, initials, and signatures. A licensee shall maintain adequate safeguards against tampering with and loss of records.
(2)
Record Retention
. A licensee shall maintain the records that are required
under
this subchapter for the period specified by the
applicable provision
.
If a retention period is not otherwise specified, records shall be retained until the department terminates the facility’s license. All records related to this subchapter may be destroyed upon the department’s term
ination of the facility license.
SECTION
97
.
DHS 157
Appendix A is
repealed and recreated
to read:
APPENDIX A
(See PDF for image)
Exempt Concentrations
|
Element (atomic number)
|
Radionuclide
|
Column I
Gas concentration
µCi/ml 1/
|
Column II Liquid
and solid concentration
µCi/ml 2/
|
Antimony (51)
|
Sb−122
|
|
3X10
−4
|
Arsenic (33)
|
As−73
|
|
5X10
−3
|
Barium (56)
|
Ba−131
|
|
2X10
−3
|
Beryllium (4)
|
Be−7
|
|
2X10
−2
|
Bismuth (83)
|
Bi−206
|
|
4X10
−4
|
Bromine (35)
|
Br−82
|
4X10
−7
|
3X10
−3
|
Cadmium (48)
|
Cd−109
|
|
2X10
−3
|
Calcium (20)
|
Ca−45
|
|
9X10
−5
|
Carbon (6)
|
C−14
|
1X10
−6
|
8X10
−3
|
Cerium (58)
|
Ce−141
|
|
9X10
−4
|
Cesium (55)
|
Cs−131
|
|
2X10
−2
|
Chlorine (17)
|
Cl−38
|
9X10
−7
|
4X10
−3
|
Chromium (24)
|
Cr−51
|
|
2X10
−2
|
Cobalt (27)
|
Co−57
|
|
5X10
−3
|
Copper (29)
|
Cu−64
|
|
3X10
−3
|
Dysprosium (66)
|
Dy−165
|
|
4X10
−3
|
Erbium (68)
|
Er−169
|
|
9X10
−4
|
Europium (63)
|
Eu−152(9.2 h)
|
|
6X10
−4
|
Fluorine (9)
|
F−18
|
2X10
−6
|
8X10
−3
|
1/ Values are given in Column I only for those materials normally used as gases.
2/
µ
Ci/g for solids
|
Element (atomic number)
|
Radionuclide
|
Column I
Gas concentration
µ
Ci/ml 1/
|
Column II Liquid
and
solid concentration
µ
Ci/ml 2/
|
Gadolinium (
64)
|
Gd−153
|
|
2X10
−3
|
Gallium (31)
|
Ga−72
|
|
4X10
−4
|
Germanium (32)
|
Ge−71
|
|
2X10
−2
|
Hafnium (72)
|
Hf−181
|
|
7X10
−4
|
Hydrogen (1)
|
H−3
|
5X10
−6
|
3X10
−2
|
Indium (49)
|
In−113m
|
|
1X10
−2
|
Iodine (53)
|
I−126
|
3X10
−9
|
2X10
−5
|
Iridium (77)
|
Ir−190
|
|
2X10
−3
|
Krypton (36)
|
Kr−85m
|
1X10
−6
|
|
Lanthanum (57)
|
La−140
|
|
2X10
−4
|
Lead (82)
|
Pb−203
|
|
4X10
−
3
|
Lutetium (71)
|
Lu−177
|
|
1X10
−3
|
Manganese (25)
|
Mn−52
|
|
3X10
−4
|
Mercury (80)
|
Hg−197m
|
|
2X10
−3
|
Molybdenum (42)
|
Mo−99
|
|
2X10
−3
|
Neodymium (60)
|
Nd−147
|
|
6X10
−4
|
Nickel (28)
|
Ni−65
|
|
1X10
−3
|
Niobium (Columbium) (41)
|
Nb−95
|
|
1X10
−3
|
Osmium (76)
|
Os−185
|
|
7X10
−4
|
Palladium (46)
|
Pd−103
|
|
3X10
−3
|
Phosphorus (15)
|
P−32
|
|
2X10
−4
|
Platinum (78)
|
Pt−191
|
|
1X10
−3
|
1/ Values are given in Column I only for those materials normally used as gases.
2/ µCi/g for solids
|
Element (atomic number)
|
Radionuclide
|
Column I
Gas concentration
µ
Ci/ml 1/
|
Column II Liquid
and
solid concentration
µ
Ci/ml 2/
|
Potassium (19)
|
K−42
|
|
3X10
−3
|
Praseodymium (59)
|
Pr−142
|
|
3X10
−4
|
Promethium (61)
|
Pm−147
|
|
2X10
−3
|
Rhenium (75)
|
Re−183
|
|
6X10
−3
|
Rhodium (45)
|
Rh−103m
|
|
1X10
−1
|
Rubidium (37)
|
Rb−86
|
|
7X10
−4
|
Ruthenium (44)
|
Ru−97
|
|
4X10
−3
|
Samarium (62)
|
Sm−153
|
|
8X10
−4
|
Scandium (21)
|
Sc−46
|
|
4X10
−4
|
Selenium (34)
|
Se−75
|
|
3X10
−3
|
Silicon (14)
|
Si−31
|
|
9X10
−3
|
Silver (47)
|
Ag−105
|
|
1X10
−3
|
Sodium (11)
|
Na−24
|
|
2X10
−3
|
Strontium
(38)
|
Sr−85
|
|
1X10
−3
|
Sulfur (16)
|
S−35
|
9X10
−8
|
6X10
−4
|
Tantalum (73)
|
Ta−182
|
|
4X10
−4
|
Technetium (43)
|
Tc−96m
|
|
1X10
−1
|
Tellurium (52)
|
Te−125m
|
|
2X10
−3
|
Terbium (65)
|
Tb−160
|
|
4X10
−4
|
Thallium (81)
|
Tl−200
|
|
4X10
−3
|
Thulium (69)
|
Tm−170
|
|
5X10
−4
|
1/ Values are given in Column I only for those materials normally used as gases.
2/ µCi/g for solids
|
Element (atomic number)
|
Radionuclide
|
Column I
Gas concentration
µCi/ml 1/
|
Column II Liquid
and solid concentration
µCi/ml 2/
|
T
in (50)
|
Sn−
1
13
|
|
9X1
0
−
4
|
T
ungsten (
W
olfram) (74)
|
W−181
|
|
4X1
0
−
3
|
V
anadium (23)
|
V-48
|
|
3X1
0
−
4
|
Xenon (54)
|
Xe−131m
|
4X1
0
−
6
|
|
Ytterbium (70)
|
Yb−175
|
|
1X1
0
−
3
|
Yttrium (39)
|
Y−90
|
|
2X1
0
−
4
|
Zinc (30)
|
Zn−65
|
|
1X1
0
−
3
|
Zirconium (40)
|
Zr−95
|
|
6X1
0
−
4
|
Beta
−
an
d
gamma−emitting
radioactive material not listed
abov
e
wit
h
half−life
of
less than 3 years.
|
|
1X1
0
−
10
|
1X1
0
−
6
|
Note 1:
Many radionuclides transform into other radionuclides. In expressing the concentrations in Appendix A, the activity stated is that of the parent radionuclide and takes into account the radioactive decay products.
Note 2:
For purposes of s.
DHS 157.09 (2)
where there is involved a combination of radionuclides, the limit for the combination should be derived as follows: Determine for each radionuclide in the product the ratio between the radioactivity concentration present in the product and the exempt radioactivity concentration established in Appendix A for the specific radionuclide when not in combination. The sum of such ratios may not exceed “1”.
Example:
Concentration of Radionuclide A in Product
+
Exempt concentration of Radionuclide A
Concentration of Radionuclide B in Product
<
1
Exempt concentration of Radionuclide B
Note 3:
To convert
µ
Ci/ml to SI units of
megabecquerels
per liter multiply the above values by 37.
Example: Zirconium (40) Zr−97 (2x10
−4
µ
Ci/ml multiplied by 37 is equivalent to 74 x 10
−4
MBq
/l).
1/ Values are given in Column I only for those materials normally used as gases.
2/
µ
Ci/g for solids.
SECTION
9
8
.
DHS 157 Appendix B is
repealed and recreated
to read:
(See PDF for image)
(See PDF for image)
Chapter
DHS 157
APPENDIX B
Exempt Quantities
Radioactive Material
|
Microcuries
|
|
Radioactive Material
|
Microcuries
|
Antimony−122 (Sb 122)
|
100
|
|
Gallium−67 (Ga 67)
|
100
|
Antimony−124 (Sb 124)
|
10
|
|
Gallium−72 (Ga 72)
|
10
|
Antimony−125 (Sb 125)
|
10
|
|
Germanium−68 (Ge 68)
|
10
|
Arsenic−73 (As 73)
|
100
|
|
Germanium−71 (Ge 71)
|
100
|
Arsenic−74 (As 74)
|
10
|
|
Gold−195 (Au 195)
|
10
|
Arsenic−76 (As 76)
|
10
|
|
Gold−198 (Au 198)
|
100
|
Arsenic−77 (As 77)
|
100
|
|
Gold−199 (Au 199)
|
100
|
Barium−131 (Ba 131)
|
10
|
|
Hafnium−181 (
Hf
181)
|
10
|
Barium−133 (Ba 133)
|
10
|
|
Holmium−166 (Ho 166)
|
100
|
Barium−140 (Ba 140)
|
10
|
|
Hydrogen−3 (H 3)
|
1,000
|
Bismuth−210 (Bi 210)
|
1
|
|
Indium−111 (In 111)
|
100
|
Bromine−82 (Br 82)
|
10
|
|
Indium−113m (In 113m)
|
100
|
Cadmium−109 (Cd 109)
|
10
|
|
Indium−114m (In 114
m)
|
10
|
Cadmium−115m (Cd 115m)
|
10
|
|
Indium−115m (In 115m)
|
100
|
Cadmium−115 (Cd 115)
|
100
|
|
Indium−115 (In 115)
|
10
|
Calcium−45 (Ca 45)
|
10
|
|
Iodine−123 (I 123)
|
100
|
Calcium−47 (Ca 47)
|
10
|
|
Iodine−125 (I 125)
|
1
|
Carbon−14 (C 14)
|
100
|
|
Iodine−126 (I 126)
|
1
|
Cerium−141 (Ce 141)
|
100
|
|
Iodine−129 (I 129)
|
0.1
|
Cerium−143 (Ce 143)
|
100
|
|
Iodine−131 (I 131)
|
1
|
Cerium−144 (Ce 144)
|
1
|
|
Iodine−132 (I 132)
|
10
|
Cesium−129 (Cs 129)
|
100
|
|
Iodine−133 (I 133)
|
1
|
Cesium−131 (Cs 131)
|
1,000
|
|
Iodine−134 (I 134)
|
10
|
Cesium−134m (Cs 134m)
|
100
|
|
Iodine−135 (I 135)
|
10
|
Cesium−134 (Cs 134)
|
1
|
|
Iridium−192 (
Ir
192)
|
10
|
Cesium−135 (Cs 135)
|
10
|
|
Iridium−194 (
Ir
194)
|
100
|
Cesium−136 (Cs 136)
|
10
|
|
Iron−52 (Fe 52)
|
10
|
Cesium−137 (Cs 137)
|
10
|
|
Iron−55 (Fe 55)
|
100
|
Chlorine−36 (Cl 36)
|
10
|
|
Iron−59 (Fe 59)
|
10
|
Chlorine−38 (Cl 38)
|
10
|
|
Krypton−85 (Kr 85)
|
100
|
Chromium−51 (Cr 51)
|
1,000
|
|
Krypton−87 (Kr 87)
|
10
|
Cobalt−57 (Co 57)
|
100
|
|
Lanthanum−140 (La 140)
|
10
|
Cobalt−58m (Co 58m)
|
10
|
|
Lutetium−177 (Lu 177)
|
100
|
Cobalt−58 (Co 58)
|
10
|
|
Manganese−52 (
Mn
52)
|
10
|
Cobalt−60 (Co 60)
|
1
|
|
Manganese−54 (
Mn
54)
|
10
|
Copper−64 (Cu 64)
|
100
|
|
Mang
anese−56 (
Mn
56)
|
10
|
Dysprosium−165 (
Dy
165)
|
10
|
|
Mercury−197m (Hg 197m)
|
100
|
Dysprosium−166 (
Dy
166)
|
100
|
|
Mercury−197 (Hg 197)
|
100
|
Erbium−169 (
Er
169)
|
100
|
|
Mercury−203 (Hg 203)
|
10
|
Erbium−171 (
Er
171)
|
100
|
|
Molybdenum−99 (Mo 99)
|
100
|
Europium−
152 (
Eu
152)9.2h
|
100
|
|
Neodymium−147 (
Nd
147)
|
100
|
Europium−152 (
Eu
152)13
yr
|
1
|
|
Neodymium−149 (
Nd
149)
|
100
|
Europium−154 (
Eu
154)
|
1
|
|
Nickel−59 (Ni 59)
|
100
|
Europium−155 (
Eu
155)
|
10
|
|
Nickel−63 (Ni 63)
|
10
|
Fluorine−18 (F 18)
|
1,000
|
|
Nickel−65 (Ni 65)
|
100
|
Gadolinium−153 (
Gd
153)
|
10
|
|
Niobium−
93m (
Nb
93m)
|
10
|
Gadolinium−159 (
Gd
159)
|
100
|
|
Niobium−95 (
Nb
95)
|
10
|
|
Radioactive Material
|
Microcuries
|
|
Radioactive Material
|
Microcuries
|
Osmium−185 (
Os
185)
|
10
|
|
Technetium−96 (Tc 96)
|
10
|
Osmium−191m (
Os
191m)
|
100
|
|
Technetium−97m (Tc 97m)
|
100
|
Osmium−191 (
Os
191)
|
100
|
|
Technetium−97 (Tc 97)
|
100
|
Osmium−193 (
Os
193)
|
100
|
|
Technetium−99m (Tc 99m)
|
100
|
Palladium−103 (
Pd
103)
|
100
|
|
Technetium−99 (Tc 99)
|
10
|
Palladium−109 (
Pd
109)
|
100
|
|
Tellurium−125m (
Te
125m)
|
10
|
Phosphorus−32 (P 32
)
|
10
|
|
Tellurium−127m (
Te
127m)
|
10
|
Platinum−191 (Pt 191)
|
100
|
|
Tellurium−127 (
Te
127)
|
100
|
Platinum−193m (Pt 193m)
|
100
|
|
Tellurium−129m (
Te
129m)
|
10
|
Platinum−193 (Pt 193)
|
100
|
|
Tellurium−129 (
Te
129)
|
100
|
Platinum−197m (Pt 197m)
|
100
|
|
Tellurium−131m (
Te
131m)
|
10
|
Platinum−197 (Pt 197)
|
100
|
|
Tellurium−132 (
Te
132)
|
10
|
Polonium−210 (Po 210)
|
0.1
|
|
Terbium−160 (Tb 160)
|
10
|
Potassium−42 (K 42)
|
10
|
|
Thallium−200 (Tl 200)
|
100
|
Potassium−43 (K 43)
|
10
|
|
Thallium−201 (Tl 201)
|
100
|
Praseodymium−142 (
Pr
142)
|
100
|
|
Thallium−202 (Tl 202)
|
100
|
Praseodymium−14
3 (
Pr
143)
|
100
|
|
Thallium−204 (Tl 2
04)
|
10
|
Promethium−147 (Pm 147)
|
10
|
|
Thulium−170 (Tm 170)
|
10
|
Promethium−149 (Pm 149)
|
10
|
|
Thulium−171 (Tm 171)
|
10
|
Rhenium−186 (Re 186)
|
100
|
|
Tin−113 (Sn 113)
|
10
|
Rhenium−188 (Re 188)
|
100
|
|
Tin−125 (Sn 125)
|
10
|
Rhodium−103m (Rh 103m)
|
100
|
|
Tungsten−181 (W 181)
|
10
|
Rhodium−105 (Rh 105)
|
100
|
|
Tungsten−185 (W 185)
|
10
|
Rubidium−81 (
Rb
81)
|
10
|
|
Tungsten−187 (W 187)
|
100
|
Rubidium−86 (
Rb
86)
|
10
|
|
Vanadium−48 (V 48)
|
10
|
Rubidium−87 (
Rb
87)
|
10
|
|
Xenon−131m (
Xe
131m)
|
1,000
|
Ruthenium−
97 (Ru 97)
|
100
|
|
Xenon−133 (
Xe
133)
|
100
|
Ruthenium−103 (Ru 103)
|
10
|
|
Xenon−
135 (
Xe
135)
|
100
|
Ruthenium−105 (Ru 105)
|
10
|
|
Ytterbium−175 (
Yb
175)
|
100
|
Ruthenium−106 (Ru 106)
|
1
|
|
Yttrium−87 (Y 87)
|
10
|
Samarium−151 (Sm 151)
|
10
|
|
Yttrium−88 (Y 88)
|
10
|
Samarium−153 (Sm 153)
|
100
|
|
Yttrium−90 (Y 90)
|
10
|
Scandium−46 (
Sc
46)
|
10
|
|
Yttrium−91 (Y 91)
|
10
|
Scandium−47 (
Sc
47)
|
100
|
|
Yttrium−92 (Y 92)
|
100
|
Scandium−48 (
Sc
48)
|
10
|
|
Yttrium−93 (Y 93)
|
100
|
Selenium−75 (Se 75)
|
10
|
|
Zinc−65 (Zn 65)
|
10
|
Silicon−31 (Si 31)
|
100
|
|
Zinc−69m (Zn 69m)
|
100
|
Silver−105 (Ag 105)
|
10
|
|
Zinc−69 (Zn 69)
|
1,000
|
Silver−110m (Ag 110m)
|
1
|
|
Zirconium−93 (
Zr
93)
|
10
|
Silver−111 (Ag 111)
|
100
|
|
Zirconium−95 (
Zr
95)
|
10
|
Sodium−22 (Na 22)
|
10
|
|
Zirconium−97 (
Zr
97)
|
10
|
Sodium−24 (Na 24)
|
10
|
|
Any radioactive material not listed above other than alpha-emitting radioactive material
|
0.1
|
Strontium−90 (
Sr
90)
|
0.1
|
|
Any alpha−emitting radioactive material not listed above other than transuranic radioactive material
|
0.01
|
Note 1:
To convert
microcuries
(
µ
Ci) to SI units of
kilobecquerels
(
kBq
), multiply the above values by 37.
Example: Zirconium−97 (10
µ
Ci multiplied by 37 is equivalent to 370
kBq
).
SECTION
99
.
DHS 157 Appendix E is
repealed and recreated
to read:
APPENDIX E
Annual Limits on Intake (ALI) and Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure; Effluent Concentrations;
Concentrations for Release to Sanitary Sewerage
Introduction
For each radionuclide, Table I indicates the chemical form which is to be used for selecting the appropriate ALI or DAC value. The ALIs and DACs for inhalation are given for an aerosol with an activity median aerodynamic diameter (AMAD) of 1
(
micron), and for the D, W and Y classes of radioactive material, which refer to their retention in the pulmonary region of the lung. This classification applies to a range of clearance half−times for D if less than 10 days, for W from 10 to 100 days, and for Y greater than 100 days. The D, W or Y class given in the column headed “Class” applies only to the inhalation ALIs and DACs given in Table I, column 2 and 3. Table II provides concentration limits for airborne and liquid effluents released to the general environment. Table III provides concentration limits for discharges to sanitary
sewerage
.
Note: The values in Tables I, II, and III are presented in the computer “E” notation. In this notation a value of 6E−02 represents a value of 6 x 10
−2
or 0.06, 6E+2 represents 6 x 1O
2
or 600, and 6E+0
represents
6 x 10
0
or 6.
Table I “Occupational Values”
Note that the columns in Table I of this appendix captioned “Oral Ingestion ALI,” “Inhalation ALI” and “DAC” are applicable to occupational exposure to radioactive material. The ALIs in this appendix are the annual intakes of given radionuclide by “reference man” which would result in either (1) a committed effective dose equivalent of 0.05
Sv
(5 rem), stochastic ALI, or (2) a committed dose equivalent of 0.5
Sv
(50 rem) to an organ or tissue, non−stochastic ALI. The stochastic ALIs were derived to result in a risk, due to irradiation of organs and tissues, comparable to the risk associated with deep dose equivalent to the whole body of 0.05
Sv
(5 rem). The derivation includes multiplying the committed dose equivalent to an organ or tissue by a weighting factor,
w
T
.
This weighting factor is the proportion of the risk of stochastic effects resulting from irradiation of the organ or tissue, T, to the total risk of stochastic effects when the whole body is irradiated uniformly. The values of
w
T
are
listed under the definition of weighting factor in s.
DHS 157.03
. The non−stochastic ALIs were derived to avoid non−stochastic effects, such as prompt damage to tissue or reduction in organ function.
Note: A description of the reference man is contained in the International Commission on Radiological Protection report, ICRP Publication 23,
Reference Man: Anatomical
Physiological and Metabolic Characteristics
,
Pergamon
Press, Oxford (1975). The publication may be ordered from the web−site
http://www.icrp.org/publications.asp
.
A value of
w
T
= 0.06 is applicable to each of the 5 organs or tissues in the “remainder” category receiving the highest dose equivalents, and the dose equivalents of all other remaining tissues may be disregarded. The following portions of the GI tract -stomach, small intestine, upper large intestine, and lower large intestine - are to be treated as 4 separate organs. Note that the dose equivalents for an extremity, skin and lens of the eye are not considered in computing the committed effective dose equivalent, but are subject to limits that must be met separately.
When an ALI is defined by the stochastic dose limit, this value alone is given. When an ALI is determined by the non−stochastic dose limit to an organ, the organ or tissue to which the limit applies is shown, and the ALI for the stochastic limit is shown in parentheses.
Abbreviated organ or tissue designations are used:
LLI wall = lower large intestine wall;
St
wall
= stomach wall;
Blad
wall = bladder wall; and
Bone surf = bone surface.
The use of the ALIs listed first, the more limiting of the stochastic and non−stochastic
ALIs,
will ensure that non−stochastic effects are avoided and that the risk of stochastic effects is limited to an acceptably low value. If, in a particular situation involving a radionuclide for which the non−stochastic ALI is limiting, use of that non−stochastic ALI is considered unduly conservative, the licensee may use the stochastic ALI to determine
the committed
effective dose equivalent. However, the
licensee shall
also ensure that the 0.5
Sv
(50 rem) dose equivalent limit for any organ or tissue is not exceeded by the sum of the external deep dose equivalent plus the internal committed dose equivalent to that organ, not the effective dose. For the case where there is no external dose contribution, this would be demonstrated if the sum of the fractions of the
nonstochastic
ALIs that contribute to the committed dose equivalent to the organ receiving the
highest dose does not exceed unity, that is, intake of each radionuclide/
ALI
ns
=
<
1.0. If there is an external deep dose equivalent contribution of
H
d
, then this sum must be less than 1 − (
H
d
/50), instead of
=
<
1.0.
The derived air concentration (DAC) values are derived limits intended to control chronic occupational exposures.
The relationship between the DAC and the ALI is given by:
DAC = ALI
(
µ
Ci
)
/(2000 hours per working year x 60 minutes/ hour x 2 x 10
4
ml per minute) = [ALI/2.4 x 10
9
]
µ
Ci/ml
,
where
2 x 10
4
ml is the volume of air breathed per minute at work by reference man under working conditions of light work.
The DAC values relate to 1 of 2 modes of exposure: either external submersion or the internal committed dose equivalents resulting from inhalation of radioactive materials. DACs based upon submersion are for immersion in a semi−infinite cloud of uniform concentration and apply to each radionuclide separately. The ALI and DAC values include contributions to exposure by the single radionuclide named and any in−growth of daughter radionuclides produced in the body by decay of the parent. However, intakes that include both the parent and daughter radionuclides should be treated by the general method appropriate for mixtures.
The values of ALI and DAC do not apply directly when the individual both ingests and inhales a radionuclide, when the individual is exposed to a mixture of radionuclides by either inhalation or ingestion or both or when the individual is exposed to both internal and external irradiation. See s.
DHS 157.22 (2)
. When an individual is exposed to radioactive materials that fall under several of the translocation classifications of the same radionuclide, such as Class D, Class W or Class Y, the exposure may be evaluated as if it were a mixture of different radionuclides.
It should be noted that the classification of a compound as Class D, W, or Y is based on the chemical form of the compound and does not take into account the radiological half−life of different radionuclides. For this reason, values are given for Class D, W, and Y compounds, even for very short−lived radionuclides.
Table II “
Effluent
C
oncentrations
”
The columns in Table II of this appendix captioned “Effluents,” “Air” and “Water” are applicable to the assessment and control of dose to the public, particularly in the implementation of the provisions of s.
DHS 157.23 (2)
. The concentration values given in Columns 1 and 2 of Table II are equivalent to the radionuclide concentrations which, if inhaled or ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.5
mSv
(0.05 rem)
.
Consideration of non−stochastic limits has not been included in deriving the air and water effluent concentration limits because non−stochastic effects are presumed not to occur at or below the dose levels established for individual members of the public. For radionuclides, where the non−stochastic limit was governing in deriving the occupational DAC, the stochastic ALI was used in deriving the corresponding airborne
effluent limit in Table II. For this reason, the DAC and airborne effluent limits are not always proportional
.
The air concentration values listed in Table II, Column 1 were derived by one of 2 methods. For those radionuclides for which the stochastic limit is governing, the occupational stochastic inhalation ALI was divided by 2.4 x 10
9
ml, relating the inhalation ALI to the DAC, as explained above, and then divided by a factor of 300. The factor of 300 includes the following components: a factor of 50 to relate the 0.05
Sv
(5 rem) annual occupational dose limit to the 1
mSv
(0.1 rem) limit for members of the public, a factor of 3 to adjust for the difference in exposure time and the inhalation rate for a worker and that for members of the public; and a factor of 2 to adjust the occupational values, derived for adults, so that they are applicable to other age groups.
For those radionuclides for which submersion, that is external dose, is limiting, the occupational DAC in Table I, Column 3 was divided by 219. The factor of 219 is composed of a factor of 50, as described above, and a factor of 4.38 relating occupational exposure for 2,000 hours of
a
8,760 hour full−time exposure per year. Note that an additional factor of 2 for age considerations is not warranted in the submersion case.
The water concentrations were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x 10
7
. The factor of 7.3 x 10
7
ml includes the following components: the factors of 50 and 2 described above and a factor of 7.3 x 10
5
ml which is the annual water intake of reference man.
Note 2 of this appendix
provides
groupings of radionuclides which are applicable to unknown mixtures of radionuclides. These groupings, including occupational inhalation ALIs and DACs, air and water effluent concentrations and releases to sewer, require demonstrating that the most limiting radionuclides in successive classes are absent. The limit for the unknown mixture is defined when the presence of one of the listed radionuclides cannot be definitely excluded as being present either from knowledge of the radionuclide composition of the source or from actual measurements.
Table III “Releases to Sewers”
The monthly average concentrations for release to sanitary sewerage are applicable to the provisions in s.
DHS 157.30 (3)
. The concentration values were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x 10
6
ml. The factor of 7.3 x 10
6
ml is composed of a factor of 7.3 x 10
5
ml, the annual water intake by reference man, and a factor of 10, such that the concentrations, if the sewage released by the licensee were the only source of water ingested by a reference man during a year, would result in a committed effective dose
equivalent
of 5
mSv
(0.5 rem).
List of Elements
|
|
List of Elements (Cont.)
|
Name
|
Symbol
|
Atomic Number
|
|
Name
|
Symbol
|
Atomic Number
|
Actinium
|
Ac
|
89
|
|
Mercury
|
Hg
|
80
|
Aluminum
|
A
|
13
|
|
Molybdenum
|
Mo
|
42
|
Americium
|
Am
|
95
|
|
Neodymium
|
Nd
|
60
|
Antimony
|
Sb
|
51
|
|
Neptunium
|
Np
|
93
|
Arsenic
|
As
|
33
|
|
Niobium
|
Nb
|
41
|
Astatine
|
At
|
85
|
|
Nitrogen
|
N
|
7
|
Barium
|
Ba
|
56
|
|
Osmium
|
Os
|
76
|
Berkelium
|
Bk
|
97
|
|
Oxygen
|
O
|
8
|
Beryllium
|
Be
|
4
|
|
Palladium
|
Pd
|
46
|
Bismuth
|
Bi
|
83
|
|
Phosphorus
|
P
|
15
|
Bromine
|
Br
|
35
|
|
Platinum
|
Pt
|
78
|
Cadmium
|
Cd
|
48
|
|
Plutonium
|
Pu
|
94
|
Calcium
|
Ca
|
20
|
|
Polonium
|
Po
|
84
|
Californium
|
Cf
|
98
|
|
Potassium
|
K
|
19
|
Carbon
|
C
|
6
|
|
Praseodymium
|
Pr
|
59
|
Cerium
|
Ce
|
58
|
|
Promethium
|
Pm
|
61
|
Cesium
|
Cs
|
55
|
|
Protactinium
|
Pa
|
91
|
Chlorine
|
Cl
|
17
|
|
Radium
|
Ra
|
88
|
Chromium
|
Cr
|
24
|
|
Radon
|
Rn
|
86
|
Cobalt
|
Co
|
27
|
|
Rhenium
|
Re
|
75
|
Copper
|
Cu
|
29
|
|
Rhodium
|
Rh
|
45
|
Curium
|
Cm
|
96
|
|
Rubidium
|
Rb
|
37
|
Dysprosium
|
Dy
|
66
|
|
Ruthenium
|
Ru
|
44
|
Einsteinium
|
Es
|
99
|
|
Samarium
|
Sm
|
62
|
Erbium
|
Er
|
68
|
|
Scandium
|
Sc
|
21
|
Europium
|
Eu
|
63
|
|
Selenium
|
Se
|
34
|
Fermium
|
Fm
|
100
|
|
Silicon
|
Si
|
14
|
Fluorine
|
F
|
9
|
|
Silver
|
Ag
|
47
|
Francium
|
Fr
|
87
|
|
Sodium
|
Na
|
11
|
Gadolinium
|
Gd
|
64
|
|
Strontium
|
Sr
|
38
|
Gallium
|
Ga
|
31
|
|
Sulfur
|
S
|
16
|
Germanium
|
Ge
|
32
|
|
Tantalum
|
Ta
|
73
|
Gold
|
Au
|
79
|
|
Technetium
|
Tc
|
43
|
Hafnium
|
Hf
|
72
|
|
Tellurium
|
Te
|
52
|
Holmium
|
Ho
|
67
|
|
Terbium
|
Tv
|
65
|
Hydrogen
|
H
|
1
|
|
Thallium
|
Tl
|
81
|
Indium
|
In
|
49
|
|
Thorium
|
Th
|
90
|
Iodine
|
I
|
53
|
|
Thulium
|
Tm
|
69
|
Iron
|
Fe
|
26
|
|
Titanium
|
Ti
|
22
|
Krypton
|
Kr
|
36
|
|
Tungsten
|
W
|
74
|
Lanthanum
|
La
|
57
|
|
Uranium
|
U
|
92
|
Lutetium
|
Lu
|
71
|
|
Xenon
|
Xe
|
54
|
Magnesium
|
Mg
|
12
|
|
Ytterbium
|
Yb
|
70
|
Manganese
|
Mn
|
25
|
|
Yttrium
|
Y
|
39
|
Mendelevium
|
Md
|
101
|
|
Zinc
|
Zn
|
30
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
1
|
Hydrogen−3
|
Water, DAC includes skin absorption
|
8E+4
|
8E+4
|
2E−5
|
1E−7
|
1E−3
|
1E−2
|
|
|
|
Gas (HT or T
2
)
Submersion
a
/:
|
Use above values as HT & T
2
oxidize in air & in the body to HTO.
|
4
|
Beryllium−7
|
4 W, all compounds except those given for Y
|
4E+4
|
2E+4
|
9E−6
|
3E−8
|
6E−4
|
6E−3
|
|
|
|
Y, oxides, halides, and nitrates
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
4
|
Beryllium−10
|
W, see
7
Be
|
1E+3
|
2E+2
|
6E−8
|
2E−10
|
−
|
−
|
|
|
|
Y, see
7
Be
|
−
|
1E+1
|
6E−9
|
2E−11
|
−
|
−
|
6
|
Carbon−11
b/
|
Monoxide
|
−
|
1E+6
|
5E−4
|
2E−6
|
−
|
−
|
|
|
|
Dioxide
|
−
|
6E+5
|
3E−4
|
9E−7
|
−
|
−
|
|
|
|
Compounds
|
4E+5
|
4E+5
|
2E−4
|
6E−7
|
6E−3
|
6E−2
|
6
|
Carbon−14
|
Monoxide
|
−
|
2E+6
|
7E−4
|
2E−6
|
−
|
−
|
|
|
|
Dioxide
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
Compounds
|
2E+3
|
2E+3
|
1E-6
|
3E-9
|
3E-5
|
3E-4
|
7
|
Nitrogen−13
b
|
Submersion
a
|
|
4E−6
|
2E−8
|
|
|
|
8
|
Oxygen−15
b
|
Submersion
a
|
|
4E−6
|
2E−8
|
|
|
|
9
|
Fluorine-18
b/
|
D, fluorides of H, Li, Na, K,
Rb
, Cs, and Fr
|
5E+4
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
W, fluorides of Be, Mg, Ca,
Sr
, Ba, Ra, Al, Ga, In, Tl, As, Sb, Bi, Fe, Ru,
Os
, Co, Ni,
Pd
, Pt, Cu, Ag, Au, Zn, Cd, Hg,
Sc
, Y,
Ti
,
Zr
, V,
Nb
, Ta,
Mn
, Tc, and Re
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
Y, lanthanum fluoride
|
−
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
11
|
Sodium−22
|
D, all compounds
|
4E+2
|
6E+2
|
3E−7
|
9E−10
|
6E−6
|
6E−5
|
11
|
Sodium−24
|
D, all compounds
|
4E+3
|
5E+3
|
2E−6
|
7E−9
|
5E−5
|
5E-4
|
12
|
Magnesium−28
|
D, all compounds except those given for W
|
7E+2
|
2E+3
|
7E−7
|
2E−9
|
9E−6
|
9E−5
|
|
|
|
W, oxides, hydroxides, carbides, halides, and nitrates
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
13
|
Aluminum−26
|
D, all compounds except those given for W
|
4E+2
|
6E+1
|
3E−8
|
9E−11
|
6E−6
|
6E−5
|
|
|
|
W, oxides, hydroxides, carbides, halides, and nitrates
|
−
|
9E+1
|
4E−8
|
1E−10
|
−
|
−
|
14
|
Silicon−31
|
D, all compounds except those given for W and Y
|
9E+3
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
|
|
|
W, oxides, hydroxides,= carbides, and nitrates
|
−
|
3E+4
|
1E−5
|
5E−8
|
−
|
−
|
|
|
|
Y,
aluminosilicate
glass
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
14
|
Silicon-32
|
D, see
31
Si
|
2E+3
|
2E+2
|
1E−7
|
3E−10
|
−
|
−
|
|
|
|
W, see
31
Si
|
−
|
1E+2
|
5E-8
|
2E-10
|
−
|
−
|
|
|
|
Y, see
31
Si
|
−
|
5E+0
|
2E-9
|
7E-12
|
−
|
−
|
15
|
Phosphorus−32
|
D, all compounds except phosphates given for W
|
6E+2
|
9E+2
|
4E−7
|
1E−9
|
9E−6
|
9E−5
|
|
|
|
W, phosphates of Zn
2+
, S
3+
, Mg
2+
, Fe
3+
, Bi
3+
, and lanthanides
|
−
|
4E+2
|
2E−7
|
5E−10
|
−
|
−
|
15
|
Phosphorus−33
|
D, see
32
P
|
6E+3
|
8E+3
|
4E−6
|
1E−8
|
8E−5
|
8E−4
|
|
|
|
W, see
32
P
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
16
|
Sulfur−35
|
Vapor
|
−
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
|
|
|
D, sulfides and sulfates except those given for W
|
1E+4
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
|
|
|
sulfides of
Sr
, Ba, Ge, Sn,
Pb
, As, Sb, Bi, Cu, Ag, Au, Zn, Cd, Hg, W, and Mo. Sulfates of Ca,
Sr
, Ba, Ra, As, Sb, and Bi
|
−
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
17
|
Chlorine−36
|
D, chlorides of H, Li, Na, K,
Rb
, Cs, and Fr
|
2E+3
|
2E+3
|
1E−6
|
3E−9
|
2E−5
|
2E−4
|
|
|
|
W, chlorides of lanthanides, Be, Mg, Ca,
Sr
, Ba, Ra, Al, Ga, In, Tl, Ge, Sn,
Pb
, As, Sb, Bi, Fe, Ru,
Os
, Co, Rh,
Ir
, Ni,
Pd
, Pt, Cu, Ag, Au, Zn, Cd, Hg,
Sc
, Y,
Ti
,
Zr
,
Hf
, V,
Nb
, Ta, Cr, Mo, W,
Mn
, Tc, and Re
|
−
|
2E+2
|
1E−7
|
3E−10
|
−
|
−
|
17
|
Chlorine−38
b/
|
D, see
36
Cl
|
2E+4
|
4E+4
|
6E−8
|
6E−8
|
−
|
−
|
|
|
|
W, see
36
Cl
|
−
|
5E+4
|
2E−5
|
6E−8
|
−
|
−
|
17
|
Chlorine−39
b/
|
D, see
36
Cl
|
2E+4
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
|
|
|
W, see 36Cl
|
−
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
18
|
Argon−37
|
Submersion
a
/
|
−
|
−
|
1E+0
|
6E−3
|
−
|
−
|
18
|
Argon−39
|
Submersion
a
/
|
−
|
−
|
2E−4
|
8E−7
|
−
|
−
|
18
|
Argon−41
|
Submersion
a
/
|
−
|
−
|
3E−6
|
1E−8
|
−
|
−
|
19
|
Potassium−40
|
D, all compounds
|
3E+2
|
4E+2
|
2E−7
|
6E−10
|
4E−6
|
4E−5
|
19
|
Potassium−42
|
D, all compounds
|
5E+3
|
5E+3
|
2E−6
|
7E−9
|
6E−5
|
6E−4
|
19
|
Potassium−43
|
D, all compounds
|
6E+3
|
9E+3
|
4E−6
|
1E−8
|
9E−5
|
9E−4
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
19
|
Potassium−44
b/
|
D, all compounds
|
2E+4
|
7E+4
|
3E-5
|
9E-8
|
−
|
−
|
19
|
Potassium−45
b/
|
D, all compounds
|
3E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
20
|
Calcium−41
|
W, all compounds
|
3E+3
|
4E+3
|
2E−6
|
−
|
−
|
−
|
|
|
|
|
(4E+3)
|
(4E+3)
|
−
|
5E−9
|
6E−5
|
6E−4
|
20
|
Calcium−45
|
W, all compounds
|
2E+3
|
8E+2
|
4E−7
|
1E−9
|
2E−5
|
2E−4
|
20
|
Calcium−47
|
W, all compounds
|
8E+2
|
9E+2
|
4E−7
|
1E−9
|
1E−5
|
1E−4
|
21
|
Scandium−43
|
Y, all compounds
|
7E+3
|
2E+4
|
9E−6
|
3E−8
|
1E−4
|
1E−3
|
21
|
Scandium−44m
|
Y, all compounds
|
5E+2
|
7E+2
|
3E−7
|
1E−9
|
7E−6
|
7E−5
|
21
|
Scandium−44
|
Y, all compounds
|
4E+3
|
1E+4
|
5E−6
|
2E−8
|
5E−5
|
5E−4
|
21
|
Scandium−46
|
Y, all compounds
|
9E+2
|
2E+2
|
1E−7
|
3E−10
|
1E−5
|
1E−4
|
21
|
Scandium−47
|
Y, all compounds
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
21
|
Scandium−48
|
Y, all compounds
|
8E+2
|
1E+3
|
6E−7
|
2E−9
|
1E−5
|
1E−4
|
21
|
Scandium−49
b/
|
Y, all compounds
|
2E+4
|
5E+4
|
2E−5
|
8E−8
|
3E−4
|
3E−3
|
22
|
Titanium−44
|
D, all compounds except those given for W and Y
|
3E+2
|
1E+1
|
5E−9
|
2E−11
|
4E−6
|
4E−5
|
|
|
|
W, oxides, hydroxides, carbides, halides, and nitrates
|
−
|
3E+1
|
1E−8
|
4E−11
|
−
|
−
|
|
|
|
Y, SrTi0
|
−
|
6E+0
|
2E−9
|
8E−12
|
−
|
−
|
22
|
Titanium−45
|
D, see
44
Ti
|
9E+3
|
3E+4
|
1E−5
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
44
Ti
|
−
|
4E+4
|
1E−5
|
5E−8
|
−
|
−
|
|
|
|
Y, see
44
Ti
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
23
|
Vanadium−47
b/
|
D, all compounds except those given for W
|
3E+4
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
W, oxides, hydroxides, carbides, and halides
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
23
|
Vanadium−48
|
D, see
47
V
|
6E+2
|
1E+3
|
5E−7
|
2E−9
|
9E−6
|
9E−5
|
|
|
|
W, see
47
V
|
−
|
6E+2
|
3E−7
|
9E−10
|
−
|
−
|
23
|
Vanadium−49
|
D, see
47
V
|
7E+4
|
3E+4
|
1E−5
|
−
|
−
|
−
|
|
|
|
|
(9E+4)
|
(3E+4)
|
−
|
5E−8
|
1E−3
|
1E−2
|
|
|
|
W, see
47
V
|
−
|
2E+4
|
8E−6
|
2E−8
|
−
|
−
|
24
|
Chromium−48
|
D, all compounds except those given for W and Y
|
6E+3
|
1E+4
|
5E−6
|
2E−8
|
8E−5
|
8E−4
|
|
|
|
W, halides and nitrates
|
−
|
7E+3
|
3E−6
|
1E−8
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
7E+3
|
3E−6
|
1E−8
|
−
|
−
|
24
|
Chromium−49
b/
|
D, see
48
Cr
|
3E+4
|
8E+4
|
4E−5
|
1E−7
|
4E−4
|
4E−3
|
|
|
|
W, see
48
Cr
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
Y, see
48
Cr
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
24
|
Chromium−51
|
D, see
48
Cr
|
4E+4
|
5E+4
|
2E−5
|
6E−8
|
5E−4
|
5E−3
|
|
|
|
W, see
48
Cr
|
−
|
2E+4
|
1E−5
|
3E−8
|
−
|
−
|
|
|
|
Y, see
48
Cr
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
25
|
Manganese−51
b/
|
D, all compounds except those given for W
|
2E+4
|
5E+4
|
2E-5
|
7E-8
|
3E−4
|
3E−3
|
|
|
|
W, oxides, hydroxides,
halides, and nitrates
|
−
|
6E+4
|
3E−5
|
8E−8
|
−
|
−
|
25
|
Manganese−52m
b/
|
D, see
51
Mn
|
3E+4
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
W, see
51
Mn
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
25
|
Manganese−52
|
D, see
51
Mn
|
7E+2
|
1E+3
|
5E−7
|
2E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
51
Mn
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
25
|
Manganese−53
|
D, see
51
Mn
|
5E+4
|
1E+4
|
5E−6
|
−
|
7E−4
|
7E−3
|
|
|
|
W, see
51
Mn
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
25
|
Manganese−54
|
D, see
51
Mn
|
2E+3
|
9E+2
|
4E−7
|
1E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
51
Mn
|
−
|
8E+2
|
3E−7
|
1E−9
|
−
|
−
|
25
|
Manganese−56
|
D, see
51
Mn
|
5E+3
|
2E+4
|
6E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
51
Mn
|
−
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
26
|
Iron−52
|
D, all compounds except those given for W
|
9E+2
|
3E+3
|
1E−6
|
4E−9
|
1E−5
|
1E−4
|
|
|
|
W, oxides, hydroxides, and halides
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
26
|
Iron−55
|
D, see
52
Fe
|
9E+3
|
2E+3
|
8E−7
|
3E−9
|
1E−4
|
1E−3
|
|
|
|
W, see
52
Fe
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
26
|
Iron−59
|
D, see
52
Fe
|
8E+2
|
3E+2
|
1E−7
|
5E−10
|
1E−5
|
1E−4
|
|
|
|
W, see
52
Fe
|
−
|
5E+2
|
2E−7
|
7E−10
|
−
|
−
|
26
|
Iron-60
|
D, see
52
Fe
|
3E+1
|
6E+0
|
3E−9
|
9E−12
|
4E−7
|
4E−6
|
|
|
|
W, see
52
Fe
|
−
|
2E+1
|
8E−9
|
3E−11
|
−
|
−
|
27
|
Cobalt−55
|
W, all compounds except those given for Y
|
1E+3
|
3E+3
|
1E−6
|
4E−9
|
2E−5
|
2E−4
|
|
|
|
Y, oxides, hydroxides, halides, and nitrates
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
27
|
Cobalt−56
|
W, see
55
Co
|
5E+2
|
3E+2
|
1E−7
|
4E−10
|
6E−6
|
6E−5
|
|
|
|
Y, see
55
Co
|
4E+2
|
2E+2
|
8E−8
|
3E−10
|
−
|
−
|
27
|
Cobalt−57
|
W, see
55
Co
|
8E+3
|
3E+3
|
1E−6
|
4E−9
|
6E−5
|
6E−4
|
|
|
|
Y, see
55
Co
|
4E+3
|
7E+2
|
3E−7
|
9E−10
|
−
|
−
|
27
|
Cobalt−58m
|
W, see
55
Co
|
6E+4
|
9E+4
|
4E−5
|
1E−7
|
8E−4
|
8E−3
|
|
|
|
Y, see
55
Co
|
−
|
6E+4
|
3E−5
|
9E−8
|
−
|
−
|
27
|
Cobalt−58
|
W, see
55
Co
|
2E+3
|
1E+3
|
5E−7
|
2E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
55
Co
|
1E+3
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
27
|
Cobalt−60m
b/
|
W, see
55
Co
|
1E+6
|
4E+6
|
2E−3
|
6E−6
|
−
|
−
|
|
|
|
Y, see
55
Co
|
−
|
3E+6
|
1E−3
|
4E−6
|
−
|
−
|
27
|
Cobalt−60
|
W, see
55
Co
|
5E+2
|
2E+2
|
7E−8
|
2E−10
|
3E−6
|
3E−5
|
|
|
|
Y, see
55
Co
|
2E+2
|
3E+1
|
1E−8
|
5E−11
|
−
|
−
|
27
|
Cobalt−61
b/
|
W, see
55
Co
|
2E+4
|
6E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
|
|
|
Y, see
55
Co
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
27
|
Cobalt−62m
b/
|
W, see
55
Co
|
4E+4
|
2E+5
|
7E-5
|
2E-7
|
−
|
−
|
|
|
|
Y, see
55
Co
|
−
|
2E+5
|
6E-5
|
2E-7
|
−
|
−
|
28
|
Nickel−56
|
D, all compounds except those given for W
|
1E+3
|
2E+3
|
8E−7
|
3E−9
|
2E−5
|
2E−4
|
|
|
|
W, oxides, hydroxides, and carbides
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
|
|
|
Vapor
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
28
|
Nickel−57
|
D, see
56
Ni
|
2E+3
|
5E+3
|
2E−6
|
7E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
56
Ni
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Vapor
|
−
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
28
|
Nickel−59
|
D, see
56
Ni
|
2E+4
|
4E+3
|
2E−6
|
5E−9
|
3E−4
|
3E−3
|
|
|
|
W, see
56
Ni
|
−
|
7E+3
|
3E−6
|
1E−6
|
−
|
−
|
|
|
|
Vapor
|
−
|
E+3
|
8E−7
|
3E−9
|
−
|
−
|
28
|
Nickel−63
|
D, see
56
Ni
|
9E+3
|
2E+3
|
7E−7
|
2E−9
|
1E−4
|
1E−3
|
|
|
|
W, see
56
Ni
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Vapor
|
−
|
8E+2
|
3E−7
|
1E−9
|
−
|
−
|
28
|
Nickel−65
|
D, see
56
Ni
|
8E+3
|
2E+4
|
1E−5
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
56
Ni
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
|
|
|
Vapor
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
28
|
Nickel−66
|
D, see
56
Ni
|
4E+2
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
|
|
|
W, see
56
Ni
|
−
|
6E+2
|
3E−7
|
9E−10
|
−
|
−
|
|
|
|
Vapor
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
29
|
Copper−60
b/
|
D, all compounds except those given for W and Y
|
3E+4
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
W, sulfides, halides, and nitrates
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
29
|
Copper−61
|
D, see
60
Cu
|
1E+4
|
3E+4
|
1E−5
|
4E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
60
Cu
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
|
|
|
Y, see
60
Cu
|
−
|
4E+4
|
1E−5
|
5E−8
|
−
|
−
|
29
|
Copper−64
|
D, see
60
Cu
|
1E+4
|
3E+4
|
1E−5
|
4E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
60
Cu
|
−
|
2E+4
|
1E−5
|
3E−8
|
−
|
−
|
|
|
|
Y, see
60
Cu
|
−
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
29
|
Copper−67
|
D, see
60
Cu
|
5E+3
|
8E+3
|
3E−6
|
1E−8
|
6E−5
|
6E−4
|
|
|
|
W, see
60
Cu
|
−
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
|
|
|
Y, see
60
Cu
|
−
|
5E+3
|
2E−6
|
6E−9
|
−
|
−
|
30
|
Zinc−62
|
Y, all compounds
|
1E+3
|
3E+3
|
1E−6
|
4E−9
|
2E−5
|
2E−4
|
30
|
Zinc−63
b/
|
Y, all compounds
|
2E+4
|
7E+4
|
3E−5
|
9E−8
|
−
|
−
|
30
|
Zinc−65
|
Y, all compounds
|
4E+2
|
3E+2
|
1E−7
|
4E−10
|
5E−6
|
5E−5
|
30
|
Zinc−69m
|
Y, all compounds
|
4E+3
|
7E+3
|
3E−6
|
1E−8
|
6E−5
|
6E−4
|
30
|
Zinc−69
b/
|
Y, all compounds
|
6E+4
|
1E+5
|
6E−5
|
2E−7
|
8E−4
|
8E−3
|
30
|
Zinc−71m
|
Y, all compounds
|
6E+3
|
2E+4
|
7E−6
|
2E−8
|
8E−5
|
8E−4
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
30
|
Zinc−72
|
Y, all compounds
|
1E+3
|
1E+3
|
5E−7
|
2E−9
|
1E−5
|
1E−4
|
31
|
Gallium−65
b/
|
D, all compounds except those given for W
|
5E+4
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
|
|
|
W, oxides, hydroxides, carbides, halides, and nitrates
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
31
|
Gallium−66
|
D, see
65
Ga
|
1E+3
|
4E+3
|
1E−6
|
5E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
65
Ga
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
31
|
Gallium−67
|
D, see
65
Ga
|
7E+3
|
1E+4
|
6E−6
|
2E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
65
Ga
|
−
|
1E+4
|
4E−6
|
1E−8
|
−
|
−
|
31
|
Gallium−68
b/
|
D, see
65
Ga
|
2E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
65
Ga
|
−
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
31
|
Gallium−70b/
|
D, see
65
Ga
|
5E+4
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
|
|
|
W, see 65Ga
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
31
|
Gallium−72
|
D, see
65
Ga
|
1E+3
|
4E+3
|
1E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
65
Ga
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
31
|
Gallium−73
|
D, see
65
Ga
|
5E+3
|
2E+4
|
6E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
65
Ga
|
−
|
2E+4
|
6E−6
|
2E−8
|
−
|
−
|
32
|
Germanium−66
|
D, all compounds except those given for W
|
2E+4
|
3E+4
|
1E−5
|
4E−8
|
3E−4
|
3E−3
|
|
|
|
W, oxides, sulfides, and halides
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
32
|
Germanium−67
b/
|
D, see
66
Ge
|
3E+4
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
W, see
66
Ge
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
32
|
Germanium−68
|
D, see
66
Ge
|
5E+3
|
4E+3
|
2E−6
|
5E−9
|
6E−5
|
6E−4
|
|
|
|
W, see
66
Ge
|
−
|
1E+2
|
4E−8
|
1E−10
|
−
|
−
|
32
|
Germanium−69
|
D, see
66
Ge
|
1E+4
|
2E+4
|
6E−6
|
2E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
66
Ge
|
−
|
8E+3
|
3E−6
|
1E−8
|
−
|
−
|
32
|
Germanium−71
|
D, see
66
Ge
|
5E+5
|
4E+5
|
2E−4
|
6E−7
|
7E−3
|
7E−2
|
|
|
|
W, see
66
Ge
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
32
|
Germanium−75
b/
|
D, see
66
Ge
|
4E+4
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
W, see
66
Ge
|
−
|
8E+4
|
4E−5
|
1E−7
|
−
|
−
|
32
|
Germanium−77
|
D, see
66
Ge
|
9E+3
|
1E+4
|
4E−6
|
1E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
66
Ge
|
−
|
6E+3
|
2E−6
|
8E−9
|
−
|
−
|
32
|
Germanium−78
b/
|
D, see
66
Ge
|
2E+4
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
|
|
|
W, see
66
Ge
|
−
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
33
|
Arsenic−69
b/
|
W, all compounds
|
3E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
33
|
Arsenic−70
b/
|
W, all compounds
|
1E+4
|
5E+4
|
2E−5
|
7E−8
|
2E−4
|
2E−3
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
33
|
Arsenic−71
|
W, all compounds
|
4E+3
|
5E+3
|
2E−6
|
6E−9
|
5E−5
|
5E−4
|
33
|
Arsenic−72
|
W, all compounds
|
9E+2
|
1E+3
|
6E−7
|
2E−9
|
1E−5
|
1E−4
|
33
|
Arsenic−73
|
W, all compounds
|
8E+3
|
2E+3
|
7E−7
|
2E−9
|
1E−4
|
1E−3
|
33
|
Arsenic−74
|
W, all compounds
|
1E+3
|
8E+2
|
3E−7
|
1E−9
|
2E−5
|
2E−4
|
33
|
Arsenic−76
|
W, all compounds
|
1E+3
|
1E+3
|
6E−7
|
2E−9
|
1E−5
|
1E−4
|
33
|
Arsenic−77
|
W, all compounds
|
4E+3
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
33
|
Arsenic−78
b/
|
W, all compounds
|
8E+3
|
2E+4
|
9E−6
|
3E−8
|
1E−4
|
1E−3
|
34
|
Selenium−70
b/
|
D, all compounds except those given for W
|
2E+4
|
4E+4
|
2E−5
|
5E−8
|
1E−4
|
1E−3
|
|
|
|
W, oxides, hydroxides,
carbides, and elemental Se
|
1E+4
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
34
|
Selenium−73m
b/
|
D, see
70
Se
|
6E+4
|
2E+5
|
6E−5
|
2E−7
|
4E−4
|
4E−3
|
|
|
|
W, see
70
Se
|
3E+4
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
34
|
Selenium−73
|
D, see
70
Se
|
3E+3
|
1E+4
|
5E−6
|
2E−8
|
4E−5
|
4E−4
|
|
|
|
W, see
70
Se
|
-
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
34
|
Selenium−75
|
D, see
70
Se
|
5E+2
|
7E+2
|
3E−7
|
1E−9
|
7E−6
|
7E−5
|
|
|
|
W, see
70
Se
|
−
|
6E+2
|
3E−7
|
8E−10
|
−
|
−
|
34
|
Selenium−79
|
D, see
70
Se
|
6E+2
|
8E+2
|
3E−7
|
1E−9
|
8E−6
|
8E−5
|
|
|
|
W, see
70
Se
|
−
|
6E+2
|
2E−7
|
8E−10
|
−
|
−
|
34
|
Selenium−81m
b/
|
D, see
70
Se
|
4E+4
|
7E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
70
Se
|
2E+4
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
34
|
Selenium−81
b/
|
D, see
70
Se
|
6E+4
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
W, see
70
Se
|
−
|
2E+5
|
1E−4
|
3E−7
|
−
|
−
|
34
|
Selenium−83
b/
|
D, see
70
Se
|
4E+4
|
1E+5
|
5E−5
|
2E−7
|
4E−4
|
4E−3
|
|
|
|
W, see
70
Se
|
3E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
35
|
Bromine−74m
b/
|
D, bromides of H, Li, Na, K,
Rb
, Cs, and Fr
|
1E+4
|
4E+4
|
2E−5
|
5E−8
|
−
|
−
|
|
|
|
W, bromides of lanthanides, Be, Mg, Ca,
Sr
, Ba, Ra, Al, Ga, In, Tl, Ge, Sn,
Pb
, As, Sb, Bi, Fe, Ru,
Os
, Co, Rh,
Ir
, Ni,
Pd
, Pt, Cu, Ag, Au, Zn, Cd, Hg,
Sc
, Y,
Ti
,
Zr
,
Hf
, V,
Nb
, Ta,
Mn
, Tc, and Re
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
35
|
Bromine−74
b/
|
D, see
74m
Br
|
2E+4
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
W, see
74m
Br
|
−
|
8E+4
|
4E−5
|
1E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
35
|
Bromine−75
b/
|
D, see
74m
Br
|
3E+4
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
|
|
|
W, see
74m
Br
|
−
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
35
|
Bromine−76
|
D, see
74m
Br
|
4E+3
|
5E+3
|
2E−6
|
7E−9
|
5E−5
|
5E−4
|
|
|
|
W, see
74m
Br
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
35
|
Bromine−77
|
D, see
74m
Br
|
2E+4
|
2E+4
|
1E−5
|
3E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
74m
Br
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
35
|
Bromine−80m
|
D, see
74m
Br
|
2E+4
|
2E+4
|
7E−6
|
2E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
74m
Br
|
−
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
35
|
Bromine−80
b/
|
D, see
74m
Br
|
5E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
|
|
|
W, see
74m
Br
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
35
|
Bromine−82
|
D, see
74m
Br
|
3E+3
|
4E+3
|
2E−6
|
6E−9
|
4E−5
|
4E−4
|
|
|
|
W, see
74m
Br
|
−
|
4E+3
|
2E−6
|
5E−9
|
−
|
−
|
35
|
Bromine−83
|
D, see
74m
Br
|
5E+4
|
6E+4
|
3E−5
|
9E−8
|
−
|
−
|
|
|
|
W, see
74m
Br
|
−
|
6E+4
|
3E−5
|
9E−8
|
−
|
−
|
35
|
Bromine−84
b/
|
D, see
74m
Br
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
|
|
|
W, see
74m
Br
|
−
|
6E+4
|
3E−5
|
9E−8
|
−
|
−
|
36
|
Krypton−74
b/
|
Submersion
a
/
|
−
|
−
|
3E-6
|
1E-8
|
−
|
−
|
36
|
Krypton−76
|
Submersion
a
/
|
−
|
−
|
9E-6
|
4E-8
|
−
|
−
|
36
|
Krypton−77
b/
|
Submersion
a
/
|
−
|
−
|
4E-6
|
2E-8
|
−
|
−
|
36
|
Krypton−79
|
Submersion
a
/
|
−
|
−
|
2E-5
|
7E-8
|
−
|
−
|
36
|
Krypton−81
|
Submersion
a
/
|
−
|
−
|
7E-4
|
3E-6
|
−
|
−
|
36
|
Krypton−83m
b/
|
Submersion
a
/
|
−
|
−
|
1E-2
|
5E-5
|
−
|
−
|
36
|
Krypton−85m
|
Submersion
a
/
|
−
|
−
|
2E-5
|
1E-7
|
−
|
−
|
36
|
Krypton−85
|
Submersion
a
/
|
−
|
−
|
1E-4
|
7E-7
|
−
|
−
|
36
|
Krypton−87
b/
|
Submersion
a
/
|
−
|
−
|
5E-6
|
2E-8
|
−
|
−
|
36
|
Krypton−88
|
Submersion
a
/
|
−
|
−
|
2E-6
|
9E-9
|
−
|
−
|
37
|
Rubidium−79
b/
|
D, all compounds
|
4E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
37
|
Rubidium−81m
b/
|
D, all compounds
|
2E+5
|
3E+5
|
1E−4
|
5E−7
|
−
|
−
|
37
|
Rubidium−81
|
D, all compounds
|
4E+4
|
5E+4
|
2E−5
|
7E−8
|
5E−4
|
5E−3
|
37
|
Rubidium−82m
|
D, all compounds
|
1E+4
|
2E+4
|
7E−6
|
2E−8
|
2E−4
|
2E−3
|
37
|
Rubidium−83
|
D, all compounds
|
6E+2
|
1E+3
|
4E−7
|
1E−9
|
9E−6
|
9E−5
|
37
|
Rubidium−84
|
D, all compounds
|
5E+2
|
8E+2
|
3E−7
|
1E−9
|
7E−6
|
7E−5
|
37
|
Rubidium−86
|
D, all compounds
|
5E+2
|
8E+2
|
3E−7
|
1E−9
|
7E−6
|
7E−5
|
37
|
Rubidium−87
|
D, all compounds
|
1E+2
|
2E+3
|
6E−7
|
2E−9
|
1E−5
|
1E−4
|
37
|
Rubidium−88
b/
|
D, all compounds
|
2E+4
|
6E+4
|
2E−5
|
9E−8
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
37
|
Rubidium−89
b/
|
D, all compounds
|
4E+4
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
38
|
Strontium−80
b/
|
D, all soluble compounds except SrTiO
3
|
4E+3
|
1E+4
|
5E−6
|
2E−8
|
6E−5
|
6E−4
|
|
|
|
Y, all insoluble compounds and SrTi0
3
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
38
|
Strontium−81
b/
|
D, see
80
Sr
|
3E+4
|
8E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
|
|
|
Y, see
80
Sr
|
2E+4
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
38
|
Strontium−82
|
D, see
80
Sr
|
3E+2
|
4E+2
|
2E−7
|
6E−10
|
−
|
−
|
|
|
|
Y, see
80
Sr
|
2E+2
|
9E+1
|
4E−8
|
1E−10
|
−
|
−
|
38
|
Strontium−83
|
D, see
80
Sr
|
3E+3
|
7E+3
|
3E−6
|
1E−8
|
3E−5
|
3E−4
|
|
|
|
Y, see
80
Sr
|
2E+3
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
38
|
Strontium−85m
b/
|
D, see
80
Sr
|
2E+5
|
6E+5
|
3E−4
|
9E−7
|
3E−3
|
3E−2
|
|
|
|
Y, see
80
Sr
|
−
|
8E+5
|
4E−4
|
1E−6
|
−
|
−
|
38
|
Strontium−85
|
D, see
80
Sr
|
3E+3
|
3E+3
|
1E−6
|
4E−9
|
4E−5
|
4E−4
|
|
|
|
Y, see
80
Sr
|
−
|
2E+3
|
6E−7
|
2E−9
|
−
|
−
|
38
|
Strontium−87m
|
D, see
80
Sr
|
5E+4
|
1E+5
|
5E−5
|
2E−7
|
6E−4
|
6E−3
|
|
|
|
Y, see
80
Sr
|
4E+4
|
2E+5
|
6E−5
|
2E−7
|
−
|
−
|
38
|
Strontium−89
|
D, see
80
Sr
|
6E+2
|
8E+2
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
80
Sr
|
5E+2
|
1E+2
|
6E−8
|
2E−10
|
−
|
−
|
38
|
Strontium−90
|
D, see
80
Sr
|
3E+1
|
2E+1
|
8E−9
|
|
−
|
−
|
|
|
|
|
(4E+1)
|
(2E+1)
|
−
|
3E−11
|
5E−7
|
5E−6
|
|
|
|
Y, see
80
Sr
|
−
|
4E+0
|
2E−9
|
6E−12
|
−
|
−
|
38
|
Strontium−91
|
D, see
80
Sr
|
2E+3
|
|
|
|
|
|
|
|
|
Y, see
80
Sr
|
−
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
38
|
Strontium−92
|
D, see
80
Sr
|
3E+3
|
9E+3
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
Y, see
80
Sr
|
−
|
7E+3
|
3E−6
|
9E−9
|
−
|
−
|
39
|
Yttrium−86m
b/
|
W, all compounds except those given for Y
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
3E−4
|
3E−3
|
|
|
|
Y, oxides and hydroxides
|
−
|
5E+4
|
2E−5
|
8E−8
|
−
|
−
|
39
|
Yttrium−86
|
W, see
86m
Y
|
1E+3
|
3E+3
|
1E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
86m
Y
|
−
|
3E+3
|
1E−6
|
5E−9
|
−
|
−
|
39
|
Yttrium−87
|
W, see
86m
Y
|
2E+3
|
3E+3
|
1E−6
|
5E−9
|
3E−5
|
3E−4
|
|
|
|
Y, see
86m
Y
|
−
|
3E+3
|
1E−6
|
5E−9
|
−
|
−
|
39
|
Yttrium−88
|
W, see
86m
Y
|
1E+3
|
3E+2
|
1E−7
|
3E−10
|
1E−5
|
1E−4
|
|
|
|
Y, see
86m
Y
|
−
|
2E+2
|
1E−7
|
3E−10
|
−
|
−
|
39
|
Yttrium−90m
|
W, see
86m
Y
|
8E+3
|
1E+4
|
5E−6
|
2E−8
|
1E−4
|
1E−3
|
|
|
|
Y, see
86m
Y
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
39
|
Yttrium−90
|
W, see
86m
Y
|
4E+2
|
7E+2
|
3E−7
|
9E−10
|
−
|
−
|
|
|
|
Y, see
86m
Y
|
−
|
6E+2
|
3E−7
|
9E−10
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
39
|
Yttrium−91m
b/
|
W, see
86m
Y
|
1E+5
|
2E+5
|
1E−4
|
3E−7
|
2E−3
|
2E−2
|
|
|
|
Y, see
86m
Y
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
39
|
Yttrium−91
|
W, see
86m
Y
|
5E+2
|
2E+2
|
7E−8
|
2E−10
|
−
|
−
|
|
|
|
Y, see
86m
Y
|
−
|
1E+2
|
5E−8
|
2E−10
|
−
|
−
|
39
|
Yttrium−92
|
W, see
86m
Y
|
3E+3
|
9E+3
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
Y, see
86m
Y
|
−
|
8E+3
|
3E−6
|
1E−8
|
−
|
−
|
39
|
Yttrium−93
|
W, see
86m
Y
|
1E+3
|
3E+3
|
1E−6
|
4E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
86m
Y
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
39
|
Yttrium−94
b/
|
W, see
86m
Y
|
2E+4
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
Y, see
86m
Y
|
−
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
39
|
Yttrium−95
b/
|
W, see
86m
Y
|
4E+4
|
2E+5
|
6E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
86m
Y
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
40
|
Zirconium−86
|
D, all compounds except those given for W and Y
|
1E+3
|
4E+3
|
2E−6
|
6E−9
|
2E−5
|
2E−4
|
|
|
|
W, oxides, hydroxides, halides, and nitrates
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Y, carbide
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
40
|
Zirconium−88
|
D, see
86
Zr
|
4E+3
|
2E+2
|
9E−8
|
3E−10
|
5E−5
|
5E−4
|
|
|
|
W, see
86
Zr
|
−
|
5E+2
|
2E−7
|
7E−10
|
−
|
−
|
|
|
|
Y, see
86
Zr
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
40
|
Zirconium−89
|
D, see
86
Zr
|
2E+3
|
4E+3
|
1E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
86
Zr
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
|
|
|
Y, see
86
Zr
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
40
|
Zirconium−93
|
D, see
86
Zr
|
1E+3
|
6E+0
|
3E−9
|
−
|
−
|
−
|
|
|
|
|
(3E+3)
|
(2E+1)
|
−
|
2E−11
|
4E−5
|
4E−4
|
|
|
|
Y, see
86
Zr
|
−
|
6E+1
|
2E−8
|
−
|
−
|
−
|
40
|
Zirconium−95
|
D, see
86
Zr
|
1E+3
|
1E+2
|
5E−8
|
−
|
2E−5
|
2E−4
|
|
|
|
W, see
86
Zr
|
−
|
4E+2
|
2E−7
|
5E−10
|
−
|
−
|
|
|
|
Y, see
86
Zr
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
40
|
Zirconium−97
|
D, see
86
Zr
|
6E+2
|
2E+3
|
8E−7
|
3E−9
|
9E−6
|
9E−5
|
|
|
|
W, see
86
Zr
|
−
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
86
Zr
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
41
|
Niobium−88
b/
|
W, all compounds except those given for Y
|
5E+4
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
41
|
Niobium−89
b/
|
W, see
88
Nb
|
1E+4
|
4E+4
|
2E−5
|
6E−8
|
1E−4
|
1E−3
|
|
|
|
Y, see
88
Nb
|
−
|
4E+4
|
2E−5
|
5E−8
|
−
|
−
|
41
|
Niobium−89
|
W, see
88
Nb
|
5E+3
|
2E+4
|
8E−6
|
3E−8
|
7E−5
|
7E−4
|
|
|
|
Y, see
88
Nb
|
−
|
2E+4
|
6E−6
|
2E−8
|
−
|
−
|
41
|
Niobium−90
|
W, see
88
Nb
|
1E+3
|
3E+3
|
1E−6
|
4E−9
|
1E−5
|
1E−4
|
|
|
|
Y, see
88
Nb
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
41
|
Niobium−93m
|
W, see
88
Nb
|
9E+3
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
|
|
|
Y, see
88
Nb
|
−
|
2E+2
|
7E−8
|
2E−10
|
−
|
−
|
41
|
Niobium−94
|
W, see
88
Nb
|
9E+2
|
2E+2
|
8E−8
|
3E−10
|
1E−5
|
1E−4
|
|
|
|
Y, see
88
Nb
|
−
|
2E+1
|
6E−9
|
2E−11
|
−
|
−
|
41
|
Niobium−95m
|
W, see
88
Nb
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Y, see
88
Nb
|
−
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
41
|
Niobium−95
|
W, see
88
Nb
|
2E+3
|
1E+3
|
5E−7
|
2E−9
|
3E−5
|
3E−4
|
|
|
|
Y, see
88
Nb
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
41
|
Niobium−96
|
W, see
88
Nb
|
1E+3
|
3E+3
|
1E−6
|
4E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
88
Nb
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
41
|
Niobium−97
b/
|
W, see
88
Nb
|
2E+4
|
8E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
|
|
|
Y, see
88
Nb
|
−
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
41
|
Niobium−98
b/
|
W, see
88
Nb
|
1E+4
|
5E+4
|
2E−5
|
8E−8
|
2E−4
|
2E−3
|
|
|
|
Y, see
88
Nb
|
−
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
42
|
Molybdenum−90
|
D, all compounds except those given for Y
|
4E+3
|
7E+3
|
3E−6
|
1E−8
|
3E−5
|
3E−4
|
|
|
|
Y, oxides, hydroxides, and MoS
2
|
2E+3
|
5E+3
|
2E−6
|
6E−9
|
−
|
−
|
42
|
Molybdenum−93m
|
D, see
90
Mo
|
9E+3
|
2E+4
|
7E−6
|
2E−8
|
6E−5
|
6E−4
|
|
|
|
Y, see
90
Mo
|
4E+3
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
42
|
Molybdenum−93
|
D, see
90
Mo
|
4E+3
|
5E+3
|
2E−6
|
8E−9
|
5E−5
|
5E−4
|
|
|
|
Y, see
90
Mo
|
2E+4
|
2E+2
|
8E−8
|
2E−10
|
−
|
−
|
42
|
Molybdenum−99
|
D, see
90
Mo
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Y, see
90
Mo
|
1E+3
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
42
|
Molybdenum−101
b/
|
D, see
90
Mo
|
4E+4
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
90
Mo
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
43
|
Technetium−93m
b/
|
D, all compounds except those given for W
|
7E+4
|
2E+5
|
6E−5
|
2E−7
|
1E−3
|
1E−2
|
|
|
|
W, oxides, hydroxides, halides, and nitrates
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
43
|
Technetium−93
|
D, see
93m
Tc
|
3E+4
|
7E+4
|
3E−5
|
1E−7
|
4E−4
|
4E−3
|
|
|
|
W, see
93m
Tc
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
43
|
Technetium−94m
b/
|
D, see
93m
Tc
|
2E+4
|
4E+4
|
2E−5
|
6E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
93m
Tc
|
−
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
43
|
Technetium−94
|
D, see
93m
Tc
|
9E+3
|
2E+4
|
8E−6
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
93m
Tc
|
−
|
2E+4
|
1E−5
|
3E−8
|
−
|
−
|
43
|
Technetium−95m
|
D, see
93m
Tc
|
4E+3
|
5E+3
|
2E−6
|
8E−9
|
5E−5
|
5E−4
|
|
|
|
W, see
93m
Tc
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
43
|
Technetium−95
|
D, see
93m
Tc
|
1E+4
|
2E+4
|
9E−6
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
93m
Tc
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
43
|
Technetium−96m
b/
|
D, see
93m
Tc
|
2E+5
|
3E+5
|
1E−4
|
4E−7
|
2E−3
|
2E−2
|
|
|
|
W, see
93m
Tc
|
−
|
2E+5
|
1E−4
|
3E−7
|
−
|
−
|
43
|
Technetium−96
|
D, see
93m
Tc
|
2E+3
|
3E+3
|
1E−6
|
5E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
93m
Tc
|
−
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
43
|
Technetium−97m
|
D, see
93m
Tc
|
5E+3
|
7E+3
|
3E−6
|
−
|
6E−5
|
6E−4
|
|
|
|
W, see
93m
Tc
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
43
|
Technetium−97
|
D, see
93m
Tc
|
4E+4
|
5E+4
|
2E−5
|
7E−8
|
5E−4
|
5E−3
|
|
|
|
W, see
93m
Tc
|
−
|
6E+3
|
2E−6
|
8E−9
|
−
|
−
|
43
|
Technetium−98
|
D, see
93m
Tc
|
1E+3
|
2E+3
|
7E−7
|
2E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
93m
Tc
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
43
|
Technetium−99m
|
D, see
93m
Tc
|
8E+4
|
2E+5
|
6E−5
|
2E−7
|
1E−3
|
1E−2
|
|
|
|
W, see
93m
Tc
|
−
|
2E+5
|
1E−4
|
3E−7
|
−
|
−
|
43
|
Technetium−99
|
D, see
93m
Tc
|
4E+3
|
5E+3
|
2E−6
|
−
|
6E−5
|
6E−4
|
|
|
|
|
−
|
−
(6E+3)
|
−
|
−
(8E
−9)
|
−
|
−
|
|
|
|
W, see
93m
Tc
|
−
|
7E+2
|
3E−7
|
9E−10
|
−
|
−
|
43
|
Technetium−101
b/
|
D, see
93m
Tc
|
9E+4
|
3E+5
|
1E−4
|
5E−7
|
−
|
−
|
|
|
|
W, see
93m
Tc
|
−
|
4E+5
|
2E−4
|
5E−7
|
−
|
−
|
43
|
Technetium−104
b/
|
D, see
93m
Tc
|
2E+4
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
W, see
93m
Tc
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
44
|
Ruthenium−94
b/
|
D, all compounds except those given for W and Y
|
2E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, halides
|
−
|
6E+4
|
3E−5
|
9E−8
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
44
|
Ruthenium−97
|
D, see
94
Ru
|
8E+3
|
2E+4
|
8E−6
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
94
Ru
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
|
|
|
Y, see
94
Ru
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
44
|
Ruthenium−103
|
D, see
94
Ru
|
2E+3
|
2E+3
|
7E−7
|
2E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
94
Ru
|
−
|
1E+3
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
94
Ru
|
−
|
6E+2
|
3E−7
|
9E−10
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
44
|
Ruthenium−105
|
D, see
94
Ru
|
5E+3
|
1E+4
|
6E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
94
Ru
|
−
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
|
|
|
Y, see
94
Ru
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
44
|
Ruthenium−106
|
D, see
94
Ru
|
2E+2
|
9E+1
|
4E−8
|
1E−10
|
−
|
−
|
|
|
|
W, see
94
Ru
|
−
|
5E+1
|
2E−8
|
8E−11
|
−
|
−
|
|
|
|
Y, see
94
Ru
|
−
|
1E+1
|
5E−9
|
2E−11
|
−
|
−
|
45
|
Rhodium−99m
|
D, all compounds except those given for W and Y
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
2E−4
|
2E−3
|
|
|
|
W, halides
|
−
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
7E+4
|
3E−5
|
9E−8
|
−
|
−
|
45
|
Rhodium−101m
|
D, see
99m
Rh
|
6E+3
|
1E+4
|
5E−6
|
2E−8
|
8E−5
|
8E−4
|
|
|
|
W, see
99m
Rh
|
−
|
8E+3
|
4E−6
|
1E−8
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
8E+3
|
3E−6
|
1E−8
|
−
|
−
|
45
|
Rhodium−101
|
D, see
99m
Rh
|
2E+3
|
5E+2
|
2E−7
|
7E−10
|
3E−5
|
3E−4
|
|
|
|
W, see
99m
Rh
|
−
|
8E+2
|
3E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
2E+2
|
6E−8
|
2E−10
|
−
|
−
|
45
|
Rhodium−99
|
D, see
99m
Rh
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
99m
Rh
|
−
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
|
|
|
W, see
99m
Rh
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
4E+3
|
2E−6
|
5E−9
|
−
|
−
|
45
|
Rhodium−102m
|
D, see
99m
Rh
|
1E+3
|
5E+2
|
2E−7
|
7E−10
|
−
|
−
|
|
|
|
W, see
99m
Rh
|
−
|
4E+2
|
2E−7
|
5E−10
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
1E+2
|
5E−8
|
2E−10
|
−
|
−
|
45
|
Rhodium−102
|
D, see
99m
Rh
|
6E+2
|
9E+1
|
4E−8
|
1E−10
|
8E−6
|
8E−5
|
|
|
|
W, see
99m
Rh
|
−
|
2E+2
|
7E−8
|
2E−10
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
6E+1
|
2E−8
|
8E−11
|
−
|
−
|
45
|
Rhodium−103m
b/
|
D, see
99m
Rh
|
4E+5
|
1E+6
|
5E−4
|
2E−6
|
6E−3
|
6E−2
|
|
|
|
W, see
99m
Rh
|
−
|
1E+6
|
5E−4
|
2E−6
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
1E+6
|
5E−4
|
2E−6
|
−
|
−
|
45
|
Rhodium−105
|
D, see
99m
Rh
|
4E+3
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
|
|
|
W, see
99m
Rh
|
−
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
6E+3
|
2E−6
|
8E−9
|
−
|
−
|
45
|
Rhodium−106m
|
D, see
99m
Rh
|
8E+3
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
99m
Rh
|
−
|
4E+4
|
2E−5
|
5E−8
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
4E+4
|
1E−5
|
5E−8
|
−
|
−
|
45
|
Rhodium−107
b/
|
D, see
99m
Rh
|
7E+4
|
2E+5
|
1E−4
|
3E−7
|
−
|
−
|
|
|
|
W, see
99m
Rh
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
|
|
|
Y, see
99m
Rh
|
−
|
3E+5
|
1E−4
|
3E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
46
|
Palladium−100
|
D, all compound44s except those given for W and4 Y
|
1E+3
|
1E+3
|
6E−7
|
2E−9
|
2E−5
|
2E−4
|
|
|
|
W, nitrates
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
46
|
Palladium−101
|
D, see
100
Pd
|
1E+4
|
3E+4
|
1E−5
|
5E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
100
Pd
|
−
|
3E+4
|
1E−5
|
5E−8
|
−
|
−
|
|
|
|
Y, see
100
Pd
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
46
|
Palladium−103
|
D, see
100
Pd
|
6E+3
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
|
|
|
W, see
100
Pd
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
|
|
|
Y, see
100
Pd
|
−
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
46
|
Palladium−107
|
D, see
100
Pd
|
3E+4
|
2E+4
|
9E−6
|
−
|
−
|
−
|
|
|
|
|
(4E+4)
|
(2E+4)
|
−
|
3E−8
|
5E−4
|
5E−3
|
|
|
|
W, see
100
Pd
|
−
|
7E+3
|
3E−6
|
1E−8
|
−
|
−
|
|
|
|
Y, see
100
Pd
|
−
|
4E+2
|
2E−7
|
6E−10
|
−
|
−
|
46
|
Palladium−109
|
D, see
100
Pd
|
2E+3
|
6E+3
|
3E−6
|
9E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
100
Pd
|
−
|
5E+3
|
2E−6
|
8E−9
|
−
|
−
|
|
|
|
Y, see
100
Pd
|
−
|
5E+3
|
2E−6
|
6E−9
|
−
|
−
|
47
|
Silver−102
b/
|
D, all compounds except those given for W and Y
|
5E+4
|
2E+5
|
8E−5
|
2E−7
|
−
|
−
|
|
|
|
W, nitrates and sulfides
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
47
|
Silver−103
b/
|
D, see
102
Ag
|
4E+4
|
1E+5
|
4E−5
|
1E−7
|
5E−4
|
5E−3
|
|
|
|
W, see
102
Ag
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
47
|
Silver−104m
b/
|
D, see
102
Ag
|
3E+4
|
9E+4
|
4E−5
|
1E−7
|
4E−4
|
4E−3
|
|
|
|
W, see
102
Ag
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
47
|
Silver−104
b/
|
D, see
102
Ag
|
2E+4
|
7E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
|
|
|
W, see
102
Ag
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
47
|
Silver−105
|
D, see
102
Ag
|
3E+3
|
1E+3
|
4E−7
|
1E−9
|
4E−5
|
4E−4
|
|
|
|
W, see
102
Ag
|
−
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
47
|
Silver−106m
|
D, see
102
Ag
|
8E+2
|
7E+2
|
3E−7
|
1E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
102
Ag
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
47
|
Silver−106
b/
|
D, see
102
Ag
|
6E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
|
|
|
W, see
102
Ag
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
47
|
Silver−108m
|
D, see
102
Ag
|
6E+2
|
2E+2
|
8E−8
|
3E−10
|
9E−6
|
9E−5
|
|
|
|
W, see
102
Ag
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
2E+1
|
1E−8
|
3E−11
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
47
|
Silver−110m
|
D, see
102
Ag
|
5E+2
|
1E+2
|
5E−8
|
2E−10
|
6E−6
|
6E−5
|
|
|
|
W, see
102
Ag
|
−
|
2E+2
|
8E−8
|
3E−10
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
9E+1
|
4E−8
|
1E−10
|
−
|
−
|
47
|
Silver−111
|
D, see
102
Ag
|
9E+2
|
2E+3
|
6E−7
|
−
|
−
|
−
|
|
|
|
|
(1E+3)
|
(2E+3)
|
−
|
2E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
102
Ag
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
47
|
Silver−112
|
D, see
102
Ag
|
3E+3
|
8E+3
|
3E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
W, see
102
Ag
|
−
|
1E+4
|
4E−6
|
1E−8
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
9E+3
|
4E−6
|
1E−8
|
−
|
−
|
47
|
Silver−115
b/
|
D, see
102
Ag
|
3E+4
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
W, see
102
Ag
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
Y, see
102
Ag
|
−
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
48
|
Cadmium−104
b/
|
D, all compounds except those given for W and Y
|
2E+4
|
7E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
|
|
|
W, sulfides, halides, and nitrates
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
48
|
Cadmium−107
|
D, see
104
Cd
|
2E+4
|
5E+4
|
2E−5
|
8E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
104
Cd
|
−
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
48
|
Cadmium−109
|
D, see
104
Cd
|
3E+2
|
4E+1
|
1E−8
|
−
|
−
|
−
|
|
|
|
|
(4E+2)
|
(5E+1)
|
−
|
7E−11
|
6E−6
|
6E−5
|
|
|
|
W, see
104
Cd
|
−
|
1E+2
|
5E−8
|
−
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
1E+2
|
5E−8
|
2E−10
|
−
|
−
|
48
|
Cadmium−113m
|
D, see
104
Cd
|
2E+1
|
2E+0
|
1E−9
|
−
|
−
|
−
|
|
|
|
|
(4E+1)
|
(4E+0)
|
−
|
5E−12
|
5E−7
|
5E−6
|
|
|
|
W, see
104
Cd
|
−
|
8E+0
|
4E−9
|
−
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
1E+1
|
5E−9
|
2E−11
|
−
|
−
|
48
|
Cadmium−113
|
D, see
104
Cd
|
2E+1
|
2E+0
|
9E−10
|
−
|
−
|
−
|
|
|
|
|
(3E+1)
|
(3E+0)
|
−
|
5E−12
|
4E−7
|
4E−6
|
|
|
|
W, see
104
Cd
|
−
|
8E+0
|
3E−9
|
−
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
1E+1
|
6E−9
|
2E−11
|
−
|
−
|
48
|
Cadmium−115m
|
D, see
104
Cd
|
3E+2
|
5E+1
|
2E−8
|
−
|
4E−6
|
4E−5
|
|
|
|
W, see
104
Cd
|
−
|
1E+2
|
5E−8
|
2E−10
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
1E+2
|
6E−8
|
2E−10
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
48
|
Cadmium−115
|
D, see
104
Cd
|
9E+2
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
|
|
|
W, see
104
Cd
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
48
|
Cadmium−117m
|
D, see
104
Cd
|
5E+3
|
1E+4
|
5E−6
|
2E−8
|
6E−5
|
6E−4
|
|
|
|
W, see
104
Cd
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
48
|
Cadmium−117
|
D, see
104
Cd
|
5E+3
|
1E+4
|
5E−6
|
2E−8
|
6E−5
|
6E−4
|
|
|
|
W, see
104
Cd
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
|
|
|
Y, see
104
Cd
|
−
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
49
|
Indium−109
|
D, all compounds except those given for W
|
2E+4
|
4E+4
|
2E−5
|
6E−8
|
3E−4
|
3E−3
|
|
|
|
W, oxides, hydroxides, halides, and nitrates
|
−
|
6E+4
|
3E−5
|
9E−8
|
−
|
−
|
49
|
Indium−110
b/
|
D, see
109
In
|
2E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
(69.1 min)
|
W, see
109
In
|
−
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
49
|
Indium−110
|
D, see
109
In
|
5E+3
|
2E+4
|
7E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
(4.9 h)
|
W, see
109
In
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
49
|
Indium−111
|
D, see
109
In
|
4E+3
|
6E+3
|
3E−6
|
9E−9
|
6E−5
|
6E−4
|
|
|
|
W, see
109
In
|
−
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
49
|
Indium−112
b/
|
D, see
109
In
|
2E+5
|
6E+5
|
3E−4
|
9E−7
|
2E−3
|
2E−2
|
|
|
|
W, see
109
In
|
−
|
7E+5
|
3E−4
|
1E−6
|
−
|
−
|
49
|
Indium−113m
b/
|
D, see
109
In
|
5E+4
|
1E+5
|
6E−5
|
2E−7
|
7E−4
|
7E−3
|
|
|
|
W, see
109
In
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
49
|
Indium−114m
|
D, see
109
In
|
3E+2
|
6E+1
|
3E−8
|
9E−11
|
−
|
−
|
|
|
|
W, see
109
In
|
−
|
1E+2
|
4E−8
|
1E−10
|
−
|
−
|
49
|
Indium−115m
|
D, see
109
In
|
1E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
109
In
|
−
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
49
|
Indium−115
|
D, see
109
In
|
4E+1
|
1E+0
|
6E−10
|
2E−12
|
5E−7
|
5E−6
|
|
|
|
W, see
109
In
|
−
|
5E+0
|
2E−9
|
8E−12
|
−
|
−
|
49
|
Indium−116m
b/
|
D, see
109
In
|
2E+4
|
8E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
|
|
|
W, see
109
In
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
49
|
Indium−117m
b/
|
D, see
109
In
|
1E+4
|
3E+4
|
1E−5
|
5E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
109
In
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
49
|
Indium−117
b/
|
D, see
109
In
|
6E+4
|
2E+5
|
7E−5
|
2E−7
|
8E−4
|
8E−3
|
|
|
|
W, see
109
In
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
49
|
Indium−119m
b/
|
D, see
109
In
|
4E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
|
|
|
W, see
109
In
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
50
|
Tin−110
|
D, all compounds except those given for W
|
4E+3
|
1E+4
|
5E−6
|
2E−8
|
5E−5
|
5E−4
|
|
|
|
W, sulfides, oxides, hydroxides, halides, nitrates, and stannic phosphate
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
50
|
Tin−111
b/
|
D, see
110
Sn
|
7E+4
|
2E+5
|
9E−5
|
3E−7
|
1E−3
|
1E−2
|
|
|
|
W, see
110
Sn
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
50
|
Tin−113
|
D, see
110
Sn
|
2E+3
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
|
|
|
W, see
110
Sn
|
−
|
5E+2
|
2E−7
|
8E−10
|
−
|
−
|
50
|
Tin−117m
|
D, see
110
Sn
|
2E+3
|
1E+3
|
5E−7
|
−
|
−
|
−
|
|
|
|
|
(2E+3)
|
(2E+3)
|
−
|
3E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
110
Sn
|
−
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
50
|
Tin−119m
|
D, see
110
Sn
|
3E+3
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
|
|
|
W, see
110
Sn
|
−
|
1E+3
|
4E−7
|
1E−9
|
−
|
−
|
50
|
Tin−121m
|
D, see
110
Sn
|
3E+3
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
W, see
110
Sn
|
−
|
5E+2
|
2E−7
|
8E−10
|
−
|
−
|
50
|
Tin−121
|
D, see
110
Sn
|
6E+3
|
2E+4
|
6E−6
|
2E−8
|
−
|
−
|
|
|
|
W, see
110
Sn
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
50
|
Tin−123m
b/
|
D, see
110
Sn
|
5E+4
|
1E+5
|
5E−5
|
2E−7
|
7E−4
|
7E−3
|
|
|
|
W, see
110
Sn
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
50
|
Tin−123
|
D, see
110
Sn
|
5E+2
|
6E+2
|
3E−7
|
9E−10
|
−
|
−
|
|
|
|
W, see
110
Sn
|
−
|
2E+2
|
7E−8
|
2E−10
|
−
|
−
|
50
|
Tin−125
|
D, see
110
Sn
|
4E+2
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
W, see
110
Sn
|
−
|
4E+2
|
1E−7
|
5E−10
|
−
|
−
|
50
|
Tin−126
|
D, see
110
Sn
|
3E+2
|
6E+1
|
2E−8
|
8E−11
|
4E−6
|
4E−5
|
|
|
|
W, see
110
Sn
|
−
|
7E+1
|
3E−8
|
9E−11
|
−
|
−
|
50
|
Tin−127
|
D, see
110
Sn
|
7E+3
|
2E+4
|
8E−6
|
3E−8
|
9E−5
|
9E−4
|
|
|
|
W, see
110
Sn
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
50
|
Tin−128
b/
|
D, see
110
Sn
|
9E+3
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
110
Sn
|
−
|
4E+4
|
1E−5
|
5E−8
|
−
|
−
|
51
|
Antimony−115
b/
|
D, all compounds except those given for W
|
8E+4
|
2E+5
|
1E−4
|
3E−7
|
1E−3
|
1E−2
|
|
|
|
W, oxides, hydroxides, halides, sulfides, sulfates, and nitrates
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
51
|
Antimony−116m
b/
|
D, see
115
Sb
|
2E+4
|
7E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
|
|
|
W, see
115
Sb
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
51
|
Antimony−116
b/
|
D, see
115
Sb
|
7E+4
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
|
|
|
W, see
115
Sb
|
−
|
3E+5
|
1E−4
|
5E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
51
|
Antimony−117
|
D, see
115
Sb
|
7E+4
|
2E+5
|
9E−5
|
3E−7
|
9E−4
|
9E−3
|
|
|
|
W, see
115
Sb
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
51
|
Antimony−118m
|
D, see
115
Sb
|
6E+3
|
2E+4
|
8E−6
|
3E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
115
Sb
|
5E+3
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
51
|
Antimony−119
|
D, see
115
Sb
|
2E+4
|
5E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
115
Sb
|
2E+4
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
51
|
Antimony−120
b/
|
D, see
115
Sb
|
1E+5
|
4E+5
|
2E−4
|
6E−7
|
−
|
−
|
|
|
|
W, see
115
Sb
|
−
|
5E+5
|
2E−4
|
7E−7
|
−
|
−
|
51
|
Antimony−120
|
D, see
115
Sb
|
1E+3
|
2E+3
|
9E−7
|
3E−9
|
1E−5
|
1E−4
|
|
|
(5.76 d)
|
W, see
115
Sb
|
9E+2
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
51
|
Antimony−122
|
D, see
115
Sb
|
8E+2
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
|
|
|
W, see
115
Sb
|
7E+2
|
1E+3
|
4E−7
|
2E−9
|
−
|
−
|
51
|
Antimony−124m
b/
|
D, see
115
Sb
|
3E+5
|
8E+5
|
4E−4
|
1E−6
|
3E−3
|
3E−2
|
|
|
|
W, see
115
Sb
|
2E+5
|
6E+5
|
2E−4
|
8E−7
|
−
|
−
|
51
|
Antimony−124
|
D, see
115
Sb
|
6E+2
|
9E+2
|
4E−7
|
1E−9
|
7E−6
|
7E−5
|
|
|
|
W, see
115
Sb
|
5E+2
|
2E+2
|
1E−7
|
3E−10
|
−
|
−
|
51
|
Antimony−125
|
D, see
115
Sb
|
2E+3
|
2E+3
|
1E−6
|
3E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
115
Sb
|
−
|
5E+2
|
2E−7
|
7E−10
|
−
|
−
|
51
|
Antimony−126m
b/
|
D, see
115
Sb
|
5E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
|
|
|
W, see
115
Sb
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
51
|
Antimony−126
|
D, see
115
Sb
|
6E+2
|
1E+3
|
5E−7
|
2E−9
|
7E−6
|
7E−5
|
|
|
|
W, see
115
Sb
|
5E+2
|
5E+2
|
2E−7
|
7E−10
|
−
|
−
|
51
|
Antimony−127
|
D, see
115
Sb
|
8E+2
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
|
|
|
W, see
115
Sb
|
7E+2
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
51
|
Antimony−128
b/
|
D, see
115
Sb
|
8E+4
|
4E+5
|
2E−4
|
5E−7
|
−
|
−
|
|
|
|
W, see
115
Sb
|
−
|
4E+5
|
2E−4
|
6E−7
|
−
|
−
|
51
|
Antimony−128
|
D, see
115
Sb
|
1E+3
|
4E+3
|
2E−6
|
6E−9
|
2E−5
|
2E−4
|
|
|
(9.01 h)
|
W, see
115
Sb
|
−
|
3E+3
|
1E−6
|
5E−9
|
−
|
−
|
51
|
Antimony−129
|
D, see
115
Sb
|
3E+3
|
9E+3
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
W, see
115
Sb
|
−
|
9E+3
|
4E−6
|
1E−8
|
−
|
−
|
51
|
Antimony−130
b/
|
D, see
115
Sb
|
2E+4
|
6E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
115
Sb
|
−
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
51
|
Antimony−131
b/
|
D, see 115Sb
|
1E+4
|
2E+4
|
1E−5
|
−
|
−
|
−
|
|
|
|
|
(2E+4)
|
(4E+4)
|
−
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
115
Sb
|
−
|
2E+4
|
1E−5
|
−
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
52
|
Tellurium−116
|
D, all compounds except those given for W
|
8E+3
|
2E+4
|
9E−6
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, oxides, hydroxides, and nitrates
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
52
|
Tellurium−121m
|
D, see
116
Te
|
5E+2
|
2E+2
|
8E−8
|
−
|
−
|
−
|
|
|
|
|
(7E+2)
|
(4E+2)
|
−
|
5E−10
|
1E−5
|
1E−4
|
|
|
|
W, see
116
Te
|
−
|
4E+2
|
2E−7
|
6E−10
|
−
|
−
|
52
|
Tellurium−121
|
D, see
116
Te
|
3E+3
|
4E+3
|
2E−6
|
6E−9
|
4E−5
|
4E−4
|
|
|
|
W, see
116
Te
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
52
|
Tellurium−123m
|
D, see
116
Te
|
6E+2
|
2E+2
|
9E−8
|
−
|
−
|
−
|
|
|
|
|
(1E+3)
|
(5E+2)
|
−
|
8E−10
|
1E−5
|
1E−4
|
|
|
|
W, see
116
Te
|
−
|
5E+2
|
2E−7
|
8E−10
|
−
|
−
|
52
|
Tellurium−123
|
D, see
116
Te
|
5E+2
|
2E+2
|
8E−8
|
−
|
−
|
−
|
|
|
|
|
(1E+3)
|
(5E+2)
|
−
|
7E−10
|
2E−5
|
2E−4
|
|
|
|
W, see
116
Te
|
−
|
4E+2
|
2E−7
|
−
|
−
|
−
|
52
|
Tellurium−125m
|
D, see
116
Te
|
1E+3
|
4E+2
|
2E−7
|
−
|
−
|
−
|
|
|
|
|
(1E+3)
|
(1E+3)
|
−
|
1E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
116
Te
|
−
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
52
|
Tellurium−127m
|
D, see
116
Te
|
6E+2
|
3E+2
|
1E−7
|
−
|
9E−6
|
9E−5
|
|
|
|
W, see
116
Te
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
52
|
Tellurium−127
|
D, see
116
Te
|
7E+3
|
2E+4
|
9E−6
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
116
Te
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
52
|
Tellurium−129m
|
D, see
116
Te
|
5E+2
|
6E+2
|
3E−7
|
9E−10
|
7E−6
|
7E−5
|
|
|
|
W, see
116
Te
|
−
|
2E+2
|
1E−7
|
3E−10
|
−
|
−
|
52
|
Tellurium−129
b/
|
D, see
116
Te
|
3E+4
|
6E+4
|
3E−5
|
9E−8
|
4E−4
|
4E−3
|
|
|
|
W, see
116
Te
|
−
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
52
|
Tellurium−131m
|
D, see
116
Te
|
3E+2
|
4E+2
|
2E−7
|
−
|
−
|
−
|
|
|
|
|
(6E+2)
|
(1E+3)
|
−
|
2E−9
|
8E−6
|
8E−5
|
|
|
|
W, see
116
Te
|
−
|
4E+2
|
2E−7
|
−
|
−
|
−
|
52
|
Tellurium−131
b/
|
D, see
116
Te
|
3E+3
|
5E+3
|
2E−6
|
−
|
−
|
−
|
|
|
|
|
(6E+3)
|
(1E+4)
|
−
|
2E−8
|
8E−5
|
8E−4
|
|
|
|
W, see
116
Te
|
−
|
5E+3
|
2E−6
|
−
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
52
|
Tellurium−132
|
D, see
116
Te
|
2E+2
|
2E+2
|
9E−8
|
−
|
−
|
−
|
|
|
|
|
(7E+2)
|
(8E+2)
|
−
|
1E−9
|
9E−6
|
9E−5
|
|
|
|
W, see
116
Te
|
−
|
2E+2
|
9E−8
|
−
|
−
|
−
|
52
|
Tellurium−133m
b/
|
D, see
116
Te
|
3E+3
|
5E+3
|
2E−6
|
−
|
−
|
−
|
|
|
|
|
(6E+3)
|
(1E+4)
|
−
|
2E−8
|
9E−5
|
9E−4
|
|
|
|
W, see
116
Te
|
−
|
5E+3
|
2E−6
|
−
|
−
|
−
|
52
|
Tellurium−133
b/
|
D, see
116
Te
|
1E+4
|
2E+4
|
9E−6
|
−
|
−
|
−
|
|
|
|
|
(3E+4)
|
(6E+4)
|
−
|
8E−8
|
4E−4
|
4E−3
|
|
|
|
W, see
116
Te
|
−
|
2E+4
|
9E−6
|
−
|
−
|
−
|
52
|
Tellurium−134
b/
|
D, see
116
Te
|
2E+4
|
2E+4
|
1E−5
|
−
|
−
|
−
|
|
|
|
|
(2E+4)
|
(5E+4)
|
−
|
7E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
116
Te
|
−
|
2E+4
|
1E−5
|
−
|
−
|
−
|
53
|
Iodine−120m
b/
|
D, all compounds
|
1E+4
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
53
|
Iodine−120
b/
|
D, all compounds
|
4E+3
|
9E+3
|
4E−6
|
−
|
−
|
−
|
|
|
|
|
(8E+3)
|
(1E+4)
|
−
|
2E−8
|
1E−4
|
1E−3
|
53
|
Iodine−121
|
D, all compounds
|
1E+4
|
2E+4
|
8E−6
|
−
|
−
|
−
|
|
|
|
|
(3E+4)
|
(5E+4)
|
−
|
7E−8
|
4E−4
|
4E−3
|
53
|
Iodine−123
|
D, all compounds
|
3E+3
|
6E+3
|
3E−6
|
−
|
−
|
−
|
|
|
|
|
(1E+4)
|
(2E+4)
|
−
|
2E−8
|
1E−4
|
1E−3
|
53
|
Iodine−124
|
D, all compounds
|
5E+1
|
8E+1
|
3E−8
|
−
|
−
|
−
|
|
|
|
|
(2E+2)
|
(3E+2)
|
−
|
4E−10
|
2E−6
|
2E−5
|
53
|
Iodine−125
|
D, all compounds
|
4E+1
|
6E+1
|
3E−8
|
−
|
−
|
−
|
|
|
|
|
(1E+2)
|
(2E+2)
|
−
|
3E−10
|
2E−6
|
2E−5
|
53
|
Iodine−126
|
D, all compounds
|
2E+1
|
4E+1
|
1E−8
|
−
|
−
|
−
|
|
|
|
|
(7E+1)
|
(1E+2)
|
−
|
2E−10
|
1E−6
|
1E−5
|
53
|
Iodine−128
b/
|
D, all compounds
|
4E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
53
|
Iodine−129
|
D, all compounds
|
5E+0
|
9E+0
|
4E−9
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(3E+1)
|
−
|
4E−11
|
2E−7
|
2E−6
|
53
|
Iodine−130
|
D, all compounds
|
4E+2
|
7E+2
|
3E−7
|
−
|
−
|
−
|
|
|
|
|
(1E+3)
|
(2E+3)
|
−
|
3E−9
|
2E−5
|
2E−4
|
53
|
Iodine−131
|
D, all compounds
|
3E+1
|
5E+1
|
2E−8
|
−
|
−
|
−
|
|
|
|
|
(9E+1)
|
(2E+2)
|
−
|
2E−10
|
1E−6
|
1E−5
|
53
|
Iodine−
132m
b/
|
D, all compounds
|
4E+3
|
8E+3
|
4E−6
|
−
|
−
|
−
|
|
|
|
|
(1E+4)
|
(2E+4)
|
−
|
3E−8
|
1E−4
|
1E−3
|
53
|
Iodine−
132
|
D, all compounds
|
4E+3
|
8E+3
|
3E−6
|
−
|
−
|
−
|
|
|
|
|
(9E+3)
|
(1E+4)
|
−
|
2E−8
|
1E−4
|
1E−3
|
53
|
Iodine−
133
|
D, all compounds
|
1E+2
|
3E+2
|
1E−7
|
−
|
−
|
−
|
|
|
|
|
(5E+2)
|
(9E+2)
|
−
|
1E−9
|
7E−6
|
7E−5
|
53
|
Iodine−
134
b/
|
D, all compounds
|
2E+4
|
5E+4
|
2E−5
|
6E−8
|
−
|
−
|
53
|
Iodine−
135
|
D, all compounds
|
8E+2
|
2E+3
|
7E−7
|
−
|
−
|
−
|
|
|
|
|
(3E+3)
|
(4E+3)
|
−
|
6E−9
|
3E−5
|
3E−4
|
54
|
Xenon−120
b/
|
Submersion
a
/
|
−
|
−
|
1E−5
|
4E−8
|
−
|
−
|
54
|
Xenon−121
b/
|
Submersion
a
/
|
−
|
−
|
2E−6
|
1E−8
|
−
|
−
|
54
|
Xenon−122
|
Submersion
a
/
|
−
|
−
|
7E−5
|
3E−7
|
−
|
−
|
54
|
Xenon−123
|
Submersion
a
/
|
−
|
−
|
6E−6
|
3E−8
|
−
|
−
|
54
|
Xenon−125
|
Submersion
a
/
|
−
|
−
|
2E−5
|
7E−8
|
−
|
−
|
54
|
Xenon−127
|
Submersion
a
/
|
−
|
−
|
1E−5
|
6E−8
|
−
|
−
|
54
|
Xenon−129m
|
Submersion
a
/
|
−
|
−
|
2E−4
|
9E−7
|
−
|
−
|
54
|
Xenon−131m
|
Submersion
a
/
|
−
|
−
|
4E−4
|
2E−6
|
−
|
−
|
54
|
Xenon−133m
|
Submersion
a
/
|
−
|
−
|
1E−4
|
6E−7
|
−
|
−
|
54
|
Xenon−133
|
Submersion
a
/
|
−
|
−
|
1E−4
|
5E−7
|
−
|
−
|
54
|
Xenon−135m
b/
|
Submersion
a
/
|
−
|
−
|
9E−6
|
4E−8
|
−
|
−
|
54
|
Xenon−135
|
Submersion
a
/
|
−
|
−
|
1E−5
|
7E−8
|
−
|
−
|
54
|
Xenon−138
b/
|
Submersion
a
/
|
−
|
−
|
4E−6
|
2E−8
|
−
|
−
|
55
|
Cesium−125
b/
|
D, all compounds
|
5E+4
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
55
|
Cesium−127
|
D, all compounds
|
6E+4
|
9E+4
|
4E−5
|
1E−7
|
9E−4
|
9E−3
|
55
|
Cesium−129
|
D, all compounds
|
2E+4
|
3E+4
|
1E−5
|
5E−8
|
3E−4
|
3E−3
|
55
|
Cesium−130
b/
|
D, all compounds
|
6E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
55
|
Cesium−131
|
D, all compounds
|
2E+4
|
3E+4
|
1E−5
|
4E−8
|
3E−4
|
3E−3
|
55
|
Cesium−132
|
D, all compounds
|
3E+3
|
4E+3
|
2E−6
|
6E−9
|
4E−5
|
4E−4
|
55
|
Cesium−134m
|
D, all compounds
|
1E+5
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
55
|
Cesium−134
|
D, all compounds
|
7E+1
|
1E+2
|
4E−8
|
2E−10
|
9E−7
|
9E−6
|
55
|
Cesium−135m
b/
|
D, all compounds
|
1E+5
|
2E+5
|
8E−5
|
3E−7
|
1E−3
|
1E−2
|
55
|
Cesium−135
|
D, all compounds
|
7E+2
|
1E+3
|
5E−7
|
2E−9
|
1E−5
|
1E−4
|
55
|
Cesium−136
|
D, all compounds
|
4E+2
|
7E+2
|
3E−7
|
9E−10
|
6E−6
|
6E−5
|
55
|
Cesium−137
|
D, all compounds
|
1E+2
|
2E+2
|
6E−8
|
2E−10
|
1E−6
|
1E−5
|
55
|
Cesium−138
b/
|
D, all compounds
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
56
|
Barium−126
b/
|
D, all compounds
|
6E+3
|
2E+4
|
6E−6
|
2E−8
|
8E−5
|
8E−4
|
56
|
Barium−128
|
D, all compounds
|
5E+2
|
2E+3
|
7E−7
|
2E−9
|
7E−6
|
7E−5
|
56
|
Barium−131m
b/
|
D, all compounds
|
4E+5
|
1E+6
|
6E−4
|
2E−6
|
−
|
−
|
56
|
Barium−131
|
D, all compounds
|
3E+3
|
8E+3
|
3E−6
|
1E−8
|
4E−5
|
4E−4
|
56
|
Barium−133m
|
D, all compounds
|
2E+3
|
9E+3
|
4E−6
|
1E−8
|
−
|
−
|
56
|
Barium−135m
|
D, all compounds
|
3E+3
|
1E+4
|
5E−6
|
2E−8
|
4E−5
|
4E−4
|
56
|
Barium−139
b/
|
D, all compounds
|
1E+4
|
3E+4
|
1E−5
|
4E−8
|
2E−4
|
2E−3
|
56
|
Barium−140
|
D, all compounds
|
5E+2
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
56
|
Barium−141
b/
|
D, all compounds
|
2E+4
|
7E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
56
|
Barium−142
b/
|
D, all compounds
|
5E+4
|
1E+5
|
6E−5
|
2E−7
|
7E−4
|
7E−3
|
57
|
Lanthanum−131
b/
|
D, all compounds except those given for W
|
5E+4
|
1E+5
|
5E−5
|
2E−7
|
6E−4
|
6E−3
|
|
|
|
W, oxides and hydroxides
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
57
|
Lanthanum−132
|
D, see
131
La
|
3E+3
|
1E+4
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
W, see
131
La
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
57
|
Lanthanum−135
|
D, see
131
La
|
4E+4
|
1E+5
|
4E−5
|
1E−7
|
5E−4
|
5E−3
|
|
|
|
W, see
131
La
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
57
|
Lanthanum−137
|
D, see
131
La
|
1E+4
|
6E+1
|
3E−8
|
−
|
2E−4
|
2E−3
|
|
|
|
W, see
131
La
|
−
|
3E+2
|
1E−7
|
−
|
−
|
−
|
57
|
Lanthanum−138
|
D, see
131
La
|
9E+2
|
4E+0
|
1E−9
|
5E−12
|
1E−5
|
1E−4
|
|
|
|
W, see
131
La
|
−
|
1E+1
|
6E−9
|
2E−11
|
−
|
−
|
57
|
Lanthanum−140
|
D, see
131
La
|
6E+2
|
1E+3
|
6E−7
|
2E−9
|
9E−6
|
9E−5
|
|
|
|
W, see
131
La
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
57
|
Lanthanum−141
|
D, see
131
La
|
4E+3
|
9E+3
|
4E−6
|
1E−8
|
5E−5
|
5E−4
|
|
|
|
W, see
131
La
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
57
|
Lanthanum−142
b/
|
D, see
131
La
|
8E+3
|
2E+4
|
9E−6
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
131
La
|
−
|
3E+4
|
1E−5
|
5E−8
|
−
|
−
|
57
|
Lanthanum−143
b/
|
D, see
131
La
|
4E+4
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
|
|
|
W, see
131
La
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
58
|
Cerium−134
|
W, all compounds except those given for Y
|
5E+2
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, oxides, hydroxides, and fluorides
|
−
|
7E+2
|
3E−7
|
9E−10
|
−
|
−
|
58
|
Cerium−135
|
W, see
134
Ce
|
2E+3
|
4E+3
|
2E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
134
Ce
|
−
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
58
|
Cerium−137m
|
W, see
134
Ce
|
2E+3
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
|
|
|
Y, see
134
Ce
|
−
|
4E+3
|
2E−6
|
5E−9
|
−
|
−
|
58
|
Cerium−137
|
W, see
134
Ce
|
5E+4
|
1E+5
|
6E−5
|
2E−7
|
7E−4
|
7E−3
|
|
|
|
Y, see
134
Ce
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
58
|
Cerium−139
|
W, see
134
Ce
|
5E+3
|
8E+2
|
3E−7
|
1E−9
|
7E−5
|
7E−4
|
|
|
|
Y, see
134
Ce
|
−
|
7E+2
|
3E−7
|
9E−10
|
−
|
−
|
58
|
Cerium−141
|
W, see
134
Ce
|
2E+3
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
134
Ce
|
−
|
6E+2
|
2E−7
|
8E−10
|
−
|
−
|
58
|
Cerium−143
|
W, see
134
Ce
|
1E+3
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
|
|
|
Y, see
134
Ce
|
−
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
58
|
Cerium−144
|
W, see
134
Ce
|
2E+2
|
3E+1
|
1E−8
|
4E−11
|
−
|
−
|
|
|
|
Y, see
134
Ce
|
−
|
1E+1
|
6E−9
|
2E−11
|
−
|
−
|
59
|
Praseodymium−136
b/
|
W, all compounds except those given for Y
|
5E+4
|
2E+5
|
1E−4
|
3E−7
|
−
|
−
|
|
|
|
Y, oxides, hydroxides, carbides, and fluorides
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
59
|
Praseodymium−137
b/
|
W, see
136
Pr
|
4E+4
|
2E+5
|
6E−5
|
2E−7
|
|
|
|
|
|
Y, see
136
Pr
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
59
|
Praseodymium−138m
|
W, see
136
Pr
|
1E+4
|
5E+4
|
2E−5
|
8E−8
|
1E−4
|
1E−3
|
|
|
|
Y, see
136
Pr
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
59
|
Praseodymium−139
|
W, see
136
Pr
|
4E+4
|
1E+5
|
5E−5
|
2E−7
|
6E−4
|
6E−3
|
|
|
|
Y, see
136
Pr
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
59
|
Praseodymium−142m
b/
|
W, see
136
Pr
|
8E+4
|
2E+5
|
7E−5
|
2E−7
|
1E−3
|
1E−2
|
|
|
|
Y, see
136
Pr
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
59
|
Praseodymium−142
|
W, see
136
Pr
|
1E+3
|
2E+3
|
9E−7
|
3E−9
|
1E−5
|
1E−4
|
|
|
|
Y, see
136
Pr
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
59
|
Praseodymium−143
|
W, see
136
Pr
|
9E+2
|
8E+2
|
3E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
136
Pr
|
−
|
7E+2
|
3E−7
|
9E−10
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
59
|
Praseodymium−144
b/
|
W, see
136
Pr
|
3E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
136
Pr
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
59
|
Praseodymium−145
|
W, see
136
Pr
|
3E+3
|
9E+3
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
Y, see
136
Pr
|
−
|
8E+3
|
3E−6
|
1E−8
|
−
|
−
|
59
|
Praseodymium−147
b/
|
W, see
136
Pr
|
5E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, see
136
Pr
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
60
|
Neodymium−136
b/
|
W, all compounds except those given for Y
|
1E+4
|
6E+4
|
2E−5
|
8E−8
|
2E−4
|
2E−3
|
|
|
|
Y, oxides, hydroxides, carbides, and fluorides
|
−
|
5E+4
|
2E−5
|
8E−8
|
−
|
−
|
60
|
Neodymium−138
|
W, see
136
Nd
|
2E+3
|
6E+3
|
3E−6
|
9E−9
|
3E−5
|
3E−4
|
|
|
|
Y, see
136
Nd
|
−
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
60
|
Neodymium−139m
|
W, see
136
Nd
|
5E+3
|
2E+4
|
7E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
|
Y, see
136
Nd
|
−
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
60
|
Neodymium−139
b/
|
W, see
136
Nd
|
9E+4
|
3E+5
|
1E−4
|
5E−7
|
1E−3
|
1E−2
|
|
|
|
Y, see
136
Nd
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
60
|
Neodymium−141
|
W, see
136
Nd
|
2E+5
|
7E+5
|
3E−4
|
1E−6
|
2E−3
|
2E−2
|
|
|
|
Y, see
136
Nd
|
−
|
6E+5
|
3E−4
|
9E−7
|
−
|
−
|
60
|
Neodymium−147
|
W, see
136
Nd
|
1E+3
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
136
Nd
|
−
|
8E+2
|
4E−7
|
1E−9
|
−
|
−
|
60
|
Neodymium−149
b/
|
W, see
136
Nd
|
1E+4
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
|
|
|
Y, see
136
Nd
|
−
|
2E+4
|
1E−5
|
3E−8
|
−
|
−
|
60
|
Neodymium−151
b/
|
W, see
136
Nd
|
7E+4
|
2E+5
|
8E−5
|
3E−7
|
9E−4
|
9E−3
|
|
|
|
Y, see
136
Nd
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
61
|
Promethium−141
b/
|
W, all compounds except those given for Y
|
5E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, oxides, hydroxides, carbides, and fluorides
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
61
|
Promethium−143
|
W, see
141
Pm
|
5E+3
|
6E+2
|
2E−7
|
8E−10
|
7E−5
|
7E−4
|
|
|
|
Y, see
141
Pm
|
−
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
61
|
Promethium−144
|
W, see
141
Pm
|
1E+3
|
1E+2
|
5E−8
|
2E−10
|
2E−5
|
2E−4
|
|
|
|
Y, see
141
Pm
|
−
|
1E+2
|
5E−8
|
2E−10
|
−
|
−
|
61
|
Promethium−145
|
W, see
141
Pm
|
1E+4
|
2E+2
|
7E−8
|
−
|
1E−4
|
1E−3
|
|
|
|
Y, see
141
Pm
|
−
|
2E+2
|
8E−8
|
3E−10
|
−
|
−
|
61
|
Promethium−146
|
W, see
141
Pm
|
2E+3
|
5E+1
|
2E−8
|
7E−11
|
2E−5
|
2E−4
|
|
|
|
Y, see
141
Pm
|
−
|
4E+1
|
2E−8
|
6E−11
|
−
|
−
|
61
|
Promethium−147
|
W, see
141
Pm
|
4E+3
|
1E+2
|
5E−8
|
−
|
−
|
−
|
|
|
|
|
(5E+3)
|
(2E+2)
|
−
|
3E−10
|
7E−5
|
7E−4
|
|
|
|
Y, see
141
Pm
|
−
|
1E+2
|
6E−8
|
2E−10
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
61
|
Promethium−148m
|
W, see
141
Pm
|
7E+2
|
3E+2
|
1E−7
|
4E−10
|
1E−5
|
1E−4
|
|
|
|
Y, see
141
Pm
|
−
|
3E+2
|
1E−7
|
5E−10
|
−
|
−
|
61
|
Promethium−148
|
W, see
141
Pm
|
4E+2
|
5E+2
|
2E−7
|
8E−10
|
−
|
−
|
|
|
|
Y, see
141
Pm
|
−
|
5E+2
|
2E−7
|
7E−10
|
−
|
−
|
61
|
Promethium−149
|
W, see
141
Pm
|
1E+3
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
|
|
|
Y, see
141
Pm
|
−
|
2E+3
|
8E−7
|
2E−9
|
−
|
−
|
61
|
Promethium−150
|
W, see
141
Pm
|
5E+3
|
2E+4
|
8E−6
|
3E−8
|
7E−5
|
7E−4
|
|
|
|
Y, see
141
Pm
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
61
|
Promethium−151
|
W, see
141
Pm
|
2E+3
|
4E+3
|
1E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
141
Pm
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
62
|
Samarium−141m
b/
|
W, all compounds
|
3E+4
|
1E+5
|
4E−5
|
1E−7
|
4E−4
|
4E−3
|
62
|
Samarium−141
b/
|
W, all compounds
|
5E+4
|
2E+5
|
8E−5
|
2E−7
|
−
|
−
|
62
|
Samarium−142
b/
|
W, all compounds
|
8E+3
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
62
|
Samarium−145
|
W, all compounds
|
6E+3
|
5E+2
|
2E−7
|
7E−10
|
8E−5
|
8E−4
|
62
|
Samarium−146
|
W, all compounds
|
1E+1
|
4E−2
|
1E−11
|
−
|
−
|
−
|
|
|
|
|
(3E+1)
|
(6E−2)
|
−
|
9E−14
|
3E−7
|
3E−6
|
62
|
Samarium−147
|
W, all compounds
|
2E+1
|
4E−2
|
2E−11
|
−
|
−
|
−
|
|
|
|
|
(3E+1)
|
(7E−2)
|
−
|
1E−13
|
4E−7
|
4E−6
|
62
|
Samarium−151
|
W, all compounds
|
1E+4
|
1E+2
|
4E−8
|
−
|
−
|
−
|
|
|
|
|
(1E+4)
|
(2E+2)
|
−
|
2E−10
|
2E−4
|
2E−3
|
62
|
Samarium−153
|
W, all compounds
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
62
|
Samarium−155
b/
|
W, all compounds
|
6E+4
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
62
|
Samarium−156
|
W, all compounds
|
5E+3
|
9E+3
|
4E−6
|
1E−8
|
7E−5
|
7E−4
|
63
|
Europium−145
|
W, all compounds
|
2E+3
|
2E+3
|
8E−7
|
3E−9
|
2E−5
|
2E−4
|
63
|
Europium−146
|
W, all compounds
|
1E+3
|
1E+3
|
5E−7
|
2E−9
|
1E−5
|
1E−4
|
63
|
Europium−147
|
W, all compounds
|
3E+3
|
2E+3
|
7E−7
|
2E−9
|
4E−5
|
4E−4
|
63
|
Europium−148
|
W, all compounds
|
1E+3
|
4E+2
|
1E−7
|
5E−10
|
1E−5
|
1E−4
|
63
|
Europium−149
|
W, all compounds
|
1E+4
|
3E+3
|
1E−6
|
4E−9
|
2E−4
|
2E−3
|
63
|
Europium−150
|
W, all compounds
|
3E+3
|
8E+3
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
63
|
Europium−150
|
W, all compounds
|
8E+2
|
2E+1
|
8E−9
|
3E−11
|
1E−5
|
1E−4
|
63
|
Europium−152m
|
W, all compounds
|
3E+3
|
6E+3
|
3E−6
|
9E−9
|
4E−5
|
4E−4
|
63
|
Europium−152
|
W, all compounds
|
8E+2
|
2E+1
|
1E−8
|
3E−11
|
1E−5
|
1E−4
|
63
|
Europium−154
|
W, all compounds
|
5E+2
|
2E+1
|
8E−9
|
3E−11
|
7E−6
|
7E−5
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
63
|
Europium−155
|
W, all compounds
|
4E+3
|
9E+1
|
4E−8
|
−
|
5E−5
|
5E−4
|
63
|
Europium−156
|
W, all compounds
|
6E+2
|
5E+2
|
2E−7
|
6E−10
|
8E−6
|
8E−5
|
63
|
Europium−157
|
W, all compounds
|
2E+3
|
5E+3
|
2E−6
|
7E−9
|
3E−5
|
3E−4
|
63
|
Europium−158
b/
|
W, all compounds
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
3E−4
|
3E−3
|
64
|
Gadolinium−145
b/
|
D, all compounds except those given for W
|
5E+4
|
2E+5
|
6E−5
|
2E−7
|
−
|
−
|
|
|
|
W, oxides, hydroxides, and fluorides
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
64
|
Gadolinium−146
|
D, see
145
Gd
|
1E+3
|
1E+2
|
5E−8
|
2E−10
|
2E−5
|
2E−4
|
|
|
|
W, see
145
Gd
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
64
|
Gadolinium−147
|
D, see
145
Gd
|
2E+3
|
4E+3
|
2E−6
|
6E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
145
Gd
|
−
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
64
|
Gadolinium−148
|
D, see
145
Gd
|
1E+1
|
8E+3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(2E−2)
|
−
|
2E−14
|
3E−7
|
3E−6
|
|
|
|
W, see
145
Gd
|
−
|
3E−2
|
1E−11
|
−
|
−
|
−
|
64
|
Gadolinium−149
|
D, see
145
Gd
|
3E+3
|
2E+3
|
9E−7
|
3E−9
|
4E−5
|
4E−4
|
|
|
|
W, see
145
Gd
|
−
|
2E+3
|
1E−6
|
3E−9
|
−
|
−
|
64
|
Gadolinium−151
|
D, see
145
Gd
|
6E+3
|
4E+2
|
2E−7
|
−
|
9E−5
|
9E−4
|
|
|
|
W, see
145
Gd
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
−
|
64
|
Gadolinium−152
|
D, see
145
Gd
|
2E+1
|
1E−2
|
4E−12
|
−
|
−
|
−
|
|
|
|
|
(3E+1)
|
(2E−2)
|
−
|
3E−14
|
4E−7
|
4E−6
|
|
|
|
W, see
145
Gd
|
−
|
4E−2
|
2E−11
|
−
|
−
|
−
|
64
|
Gadolinium−153
|
D, see
145
Gd
|
5E+3
|
1E+2
|
6E−8
|
−
|
6E−5
|
6E−4
|
|
|
|
W, see
145
Gd
|
−
|
6E+2
|
2E−7
|
8E−10
|
−
|
−
|
64
|
Gadolinium−159
|
D, see
145
Gd
|
3E+3
|
8E+3
|
3E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
W, see
145
Gd
|
−
|
6E+3
|
2E−6
|
8E−9
|
−
|
−
|
65
|
Terbium−147
b/
|
W, all compounds
|
9E+3
|
3E+4
|
1E−5
|
5E−8
|
1E−4
|
1E−3
|
65
|
Terbium−149
|
W, all compounds
|
5E+3
|
7E+2
|
3E−7
|
1E−9
|
7E−5
|
7E−4
|
65
|
Terbium−150
|
W, all compounds
|
5E+3
|
2E+4
|
9E−6
|
3E−8
|
7E−5
|
7E−4
|
65
|
Terbium−151
|
W, all compounds
|
4E+3
|
9E+3
|
4E−6
|
1E−8
|
5E−5
|
5E−4
|
65
|
Terbium−153
|
W, all compounds
|
5E+3
|
7E+3
|
3E−6
|
1E−8
|
7E−5
|
7E−4
|
65
|
Terbium−154
|
W, all compounds
|
2E+3
|
4E+3
|
2E−6
|
6E−9
|
2E−5
|
2E−4
|
65
|
Terbium−155
|
W, all compounds
|
6E+3
|
8E+3
|
3E−6
|
1E−8
|
8E−5
|
8E−4
|
65
|
Terbium−156m
|
W, all compounds
|
2E+4
|
3E+4
|
1E−5
|
4E−8
|
2E−4
|
2E−3
|
65
|
Terbium−156
|
W, all compounds
|
1E+3
|
1E+3
|
6E−7
|
2E−9
|
1E−5
|
1E−4
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
65
|
Terbium−157
|
W, all compounds
|
5E+4
|
3E+2
|
1E−7
|
−
|
−
|
−
|
|
|
|
|
(5E+4)
|
(6E+2)
|
−
|
8E−10
|
7E−4
|
7E−3
|
65
|
Terbium−158
|
W, all compounds
|
1E+3
|
2E+1
|
8E−9
|
3E−11
|
2E−5
|
2E−4
|
65
|
Terbium−160
|
W, all compounds
|
8E+2
|
2E+2
|
9E−8
|
3E−10
|
1E−5
|
1E−4
|
65
|
Terbium−161
|
W, all compounds
|
2E+3
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
66
|
Dysprosium−155
|
W, all compounds
|
9E+3
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
66
|
Dysprosium−157
|
W, all compounds
|
2E+4
|
6E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
66
|
Dysprosium−159
|
W, all compounds
|
1E+4
|
2E+3
|
1E−6
|
3E−9
|
2E−4
|
2E−3
|
66
|
Dysprosium−165
|
W, all compounds
|
1E+4
|
5E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
66
|
Dysprosium−166
|
W, all compounds
|
6E+2
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
67
|
Holmium−155
b/
|
W, all compounds
|
4E+4
|
2E+5
|
6E−5
|
2E−7
|
6E−4
|
6E−3
|
67
|
Holmium−157
b/
|
W, all compounds
|
3E+5
|
1E+6
|
6E−4
|
2E−6
|
4E−3
|
4E−2
|
67
|
Holmium−159
b/
|
W, all compounds
|
2E+5
|
1E+6
|
4E−4
|
1E−6
|
3E−3
|
3E−2
|
67
|
Holmium−161
|
W, all compounds
|
1E+5
|
4E+5
|
2E−4
|
6E−7
|
1E−3
|
1E−2
|
67
|
Holmium−162m
b/
|
W, all compounds
|
5E+4
|
3E+5
|
1E−4
|
4E−7
|
7E−4
|
7E−3
|
67
|
Holmium−162
b/
|
W, all compounds
|
5E+5
|
2E+6
|
1E−3
|
3E−6
|
−
|
−
|
67
|
Holmium−164m
b/
|
W, all compounds
|
1E+5
|
3E+5
|
1E−4
|
4E−7
|
1E−3
|
1E−2
|
67
|
Holmium−164
b/
|
W, all compounds
|
2E+5
|
6E+5
|
3E−4
|
9E−7
|
−
|
−
|
67
|
Holmium−166m
|
W, all compounds
|
6E+2
|
7E+0
|
3E−9
|
9E−12
|
9E−6
|
9E−5
|
67
|
Holmium−166
|
W, all compounds
|
9E+2
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
67
|
Holmium−167
|
W, all compounds
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
2E−4
|
2E−3
|
68
|
Erbium−161
|
W, all compounds
|
2E+4
|
6E+4
|
3E−5
|
9E−8
|
2E−4
|
2E−3
|
68
|
Erbium−165
|
W, all compounds
|
6E+4
|
2E+5
|
8E−5
|
3E−7
|
9E−4
|
9E−
|
68
|
Erbium−169
|
W, all compounds
|
3E+3
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
68
|
Erbium−171
|
W, all compounds
|
4E+3
|
1E+4
|
4E−6
|
1E−8
|
5E−5
|
5E−4
|
68
|
Erbium−172
|
W, all compounds
|
1E+3
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
69
|
Thulium−162
b/
|
W, all compounds
|
7E+4
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
69
|
Thulium−166
|
W, all compounds
|
4E+3
|
1E+4
|
6E−6
|
2E−8
|
6E−5
|
6E−4
|
69
|
Thulium−167
|
W, all compounds
|
2E+3
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
69
|
Thulium−170
|
W, all compounds
|
8E+2
|
2E+2
|
9E−8
|
3E−10
|
−
|
−
|
69
|
Thulium−171
|
W, all compounds
|
1E+4
|
3E+2
|
1E−7
|
−
|
−
|
−
|
|
|
|
|
(1E+4)
|
(6E+2)
|
−
|
8E−10
|
2E−4
|
2E−3
|
69
|
Thulium−172
|
W, all compounds
|
7E+2
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
69
|
Thulium−173
|
W, all compounds
|
4E+3
|
1E+4
|
5E−6
|
2E−8
|
6E−5
|
6E−4
|
69
|
Thulium−175
b/
|
W, all compounds
|
7E+4
|
3E+5
|
2E−4
|
4E−7
|
−
|
−
|
70
|
Ytterbium−162
b/
|
W, all compounds except those given for Y
|
7E+4
|
3E+5
|
1E−4
|
4E−7
|
1E−3
|
1E−2
|
|
|
|
Y, oxides, hydroxides, and fluorides
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
70
|
Ytterbium−166
|
W, see
162
Yb
|
1E+3
|
2E+3
|
8E−7
|
3E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
162
Yb
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
70
|
Ytterbium−167
b/
|
W, see
162
Yb
|
3E+5
|
8E+5
|
3E−4
|
1E−6
|
4E−3
|
4E−2
|
|
|
|
Y, see
162
Yb
|
−
|
7E+5
|
3E−4
|
1E−6
|
−
|
−
|
70
|
Ytterbium−169
|
W, see
162
Yb
|
2E+3
|
8E+2
|
4E−7
|
1E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
162
Yb
|
−
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
70
|
Ytterbium−175
|
W, see
162
Yb
|
3E+3
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
|
|
|
Y, see
162
Yb
|
−
|
3E+3
|
1E−6
|
5E−9
|
−
|
−
|
70
|
Ytterbium−177
b/
|
W, see
162
Yb
|
2E+4
|
5E+4
|
2E−5
|
7E−8
|
2E−4
|
2E−3
|
|
|
|
Y, see
162
Yb
|
−
|
5E+4
|
2E−5
|
6E−8
|
−
|
−
|
70
|
Ytterbium−178
b/
|
W, see
162
Yb
|
1E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
Y, see
162
Yb
|
−
|
4E+4
|
2E−5
|
5E−8
|
−
|
−
|
71
|
Lutetium−169
|
W, all compounds except those given for Y
|
3E+3
|
4E+3
|
2E−6
|
6E−9
|
3E−5
|
3E−4
|
|
|
|
Y, oxides, hydroxides, and fluorides
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
71
|
Lutetium−170
|
W, see
169
Lu
|
1E+3
|
2E+3
|
9E−7
|
3E−9
|
2E−5
|
2E−4
|
|
|
|
Y, see
169
Lu
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
71
|
Lutetium−171
|
W, see
169
Lu
|
2E+3
|
2E+3
|
8E−7
|
3E−9
|
3E−5
|
3E−4
|
|
|
|
Y, see
169
Lu
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
71
|
Lutetium−172
|
W, see
169
Lu
|
1E+3
|
1E+3
|
5E−7
|
2E−9
|
1E−5
|
1E−4
|
|
|
|
Y, see
169
Lu
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
71
|
Lutetium−173
|
W, see
169
Lu
|
5E+3
|
3E+2
|
1E−7
|
−
|
7E−5
|
7E−4
|
|
|
|
Y, see
169
Lu
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
71
|
Lutetium−174m
|
W, see
169
Lu
|
2E+3
|
2E+2
|
1E−7
|
−
|
−
|
−
|
|
|
|
|
(3E+3)
|
(3E+2)
|
−
|
5E−10
|
4E−5
|
4E−4
|
|
|
|
Y, see
169
Lu
|
−
|
2E+2
|
9E−8
|
3E−10
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
71
|
Lutetium−176
|
W, see
169
Lu
|
7E+2
|
5E+0
|
2E−9
|
−
|
1E−5
|
1E−4
|
|
|
|
Y, see
169
Lu
|
−
|
8E+0
|
3E−9
|
1E−11
|
−
|
−
|
71
|
Lutetium−177m
|
W, see
169
Lu
|
7E+2
|
1E+2
|
5E−8
|
−
|
1E−5
|
1E−4
|
|
|
|
Y, see
169
Lu
|
−
|
8E+1
|
3E−8
|
1E−10
|
−
|
−
|
71
|
Lutetium−177
|
W, see
169
Lu
|
2E+3
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
|
|
|
Y, see
169
Lu
|
−
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
71
|
Lutetium−178m
b/
|
W, see
169
Lu
|
5E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, see
169
Lu
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
71
|
Lutetium−178
b/
|
W, see
169
Lu
|
4E+4
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
169
Lu
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
71
|
Lutetium−179
|
W, see
169
Lu
|
6E+3
|
2E+4
|
8E−6
|
3E−8
|
9E−5
|
9E−4
|
|
|
|
Y, see
169
Lu
|
−
|
2E+4
|
6E−6
|
3E−8
|
−
|
−
|
72
|
Hafnium−170
|
D, all compounds except those given for W
|
3E+3
|
6E+3
|
2E−6
|
8E−9
|
4E−5
|
4E−4
|
|
|
|
W, oxides, hydroxides, carbides, and nitrates
|
−
|
5E+3
|
2E−6
|
6E−9
|
−
|
−
|
72
|
Hafnium−172
|
D, see
170
Hf
|
1E+3
|
9E+0
|
4E−9
|
−
|
2E−5
|
2E−4
|
|
|
|
W, see
170
Hf
|
−
|
4E+1
|
2E−8
|
−
|
−
|
−
|
72
|
Hafnium−173
|
D, see
170
Hf
|
5E+3
|
1E+4
|
5E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
170
Hf
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
72
|
Hafnium−175
|
D, see
170
Hf
|
3E+3
|
9E+2
|
4E−7
|
−
|
4E−5
|
4E−4
|
|
|
|
W, see
170
Hf
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
72
|
Hafnium−177m
b/
|
D, see
170
Hf
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
170
Hf
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
72
|
Hafnium−178m
|
D, see
170
Hf
|
3E+2
|
1E+0
|
5E−10
|
−
|
3E−6
|
3E−5
|
|
|
|
W, see
170
Hf
|
−
|
5E+0
|
2E−9
|
−
|
−
|
−
|
72
|
Hafnium−179m
|
D, see
170
Hf
|
1E+3
|
3E+2
|
1E−7
|
−
|
1E−5
|
1E−4
|
|
|
|
W, see
170
Hf
|
−
|
6E+2
|
3E−7
|
8E−10
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
72
|
Hafnium−180m
|
D, see
170
Hf
|
7E+3
|
2E+4
|
9E−6
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
170
Hf
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
72
|
Hafnium−181
|
D, see
170
Hf
|
1E+3
|
2E+2
|
7E−8
|
−
|
2E−5
|
2E−4
|
|
|
|
W, see
170
Hf
|
−
|
4E+2
|
2E−7
|
6E−10
|
−
|
−
|
72
|
Hafnium−182m
b/
|
D, see
170
Hf
|
4E+4
|
9E+4
|
4E−5
|
1E−7
|
5E−4
|
5E−3
|
|
|
|
W, see
170
Hf
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
72
|
Hafnium−182
|
D, see
170
Hf
|
2E+2
|
8E−1
|
3E−10
|
−
|
−
|
−
|
|
|
|
|
(4E+2)
|
(2E+0)
|
−
|
2E−12
|
5E−6
|
5E−5
|
|
|
|
W, see
170
Hf
|
−
|
3E+0
|
1E−9
|
−
|
−
|
−
|
72
|
Hafnium−183
b/
|
D, see
170
Hf
|
2E+4
|
5E+4
|
2E−5
|
6E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
170
Hf
|
−
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
72
|
Hafnium−184
|
D, see
170
Hf
|
2E+3
|
8E+3
|
3E−6
|
1E−8
|
3E−5
|
3E−4
|
|
|
|
W, see
170
Hf
|
−
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
73
|
Tantalum−172
b/
|
W, all compounds except those given for Y
|
4E+4
|
1E+5
|
5E−5
|
2E−7
|
5E−4
|
5E−3
|
|
|
|
Y, elemental Ta, oxides, hydroxides, halides, carbides, nitrates, and nitrides
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
71
|
Lutetium−174
|
W, see
169
Lu
|
5E+3
|
1E+2
|
5E−8
|
−
|
7E−5
|
7E−4
|
|
|
|
Y, see
169
Lu
|
−
|
2E+2
|
6E−8
|
2E−10
|
−
|
−
|
71
|
Lutetium−176m
|
W, see
169
Lu
|
8E+3
|
3E+4
|
1E−5
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
Y, see
169
Lu
|
−
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
73
|
Tantalum−173
|
W, see
172
Ta
|
7E+3
|
2E+4
|
8E−6
|
3E−8
|
9E−5
|
9E−4
|
|
|
|
Y, see
172
Ta
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
73
|
Tantalum−174
b/
|
W, see
172
Ta
|
3E+4
|
1E+5
|
4E−5
|
1E−7
|
4E−4
|
4E−3
|
|
|
|
Y, see
172
Ta
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
73
|
Tantalum−175
|
W, see
172
Ta
|
6E+3
|
2E+4
|
7E−6
|
2E−8
|
8E−5
|
8E−4
|
|
|
|
Y, see
172
Ta
|
−
|
1E+4
|
6E−6
|
2E−8
|
−
|
−
|
73
|
Tantalum−176
|
W, see
172
Ta
|
4E+3
|
1E+4
|
5E−6
|
2E−8
|
5E−5
|
5E−4
|
|
|
|
Y, see
172
Ta
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
73
|
Tantalum−177
|
W, see
172
Ta
|
1E+4
|
2E+4
|
8E−6
|
3E−8
|
2E−4
|
2E−3
|
|
|
|
Y, see
172
Ta
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
73
|
Tantalum−178
|
W, see
172
Ta
|
2E+4
|
9E+4
|
4E−5
|
1E−7
|
2E−4
|
2E−3
|
|
|
|
Y, see
172
Ta
|
−
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
73
|
Tantalum−179
|
W, see
172
Ta
|
2E+4
|
5E+3
|
2E−6
|
8E−9
|
3E−4
|
3E−3
|
|
|
|
Y, see
172
Ta
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
73
|
Tantalum−180m
|
W, see
172
Ta
|
2E+4
|
7E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
|
|
|
Y, see
172
Ta
|
−
|
6E+4
|
2E−5
|
8E−8
|
−
|
−
|
73
|
Tantalum−180
|
W, see
172
Ta
|
1E+3
|
4E+2
|
2E−7
|
6E−10
|
2E−5
|
2E−4
|
|
|
|
Y, see
172
Ta
|
−
|
2E+1
|
1E−8
|
3E−11
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
73
|
Tantalum−182m
b/
|
W, see
172
Ta
|
2E+5
|
5E+5
|
2E−4
|
8E−7
|
−
|
−
|
|
|
|
Y, see
172
Ta
|
−
|
4E+5
|
2E−4
|
6E−7
|
−
|
−
|
73
|
Tantalum−182
|
W, see
172
Ta
|
8E+2
|
3E+2
|
1E−7
|
5E−10
|
1E−5
|
1E−4
|
|
|
|
Y, see
172
Ta
|
−
|
1E+2
|
6E−8
|
2E−10
|
−
|
−
|
73
|
Tantalum−183
|
W, see
172
Ta
|
9E+2
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
172
Ta
|
−
|
1E+3
|
4E−7
|
1E−9
|
−
|
−
|
73
|
Tantalum−184
|
W, see
172
Ta
|
2E+3
|
5E+3
|
2E−6
|
8E−9
|
3E−5
|
3E−4
|
|
|
|
Y, see
172
Ta
|
−
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
73
|
Tantalum−185
b
/
|
W, see
172
Ta
|
3E+4
|
7E+4
|
3E−5
|
1E−7
|
4E−4
|
4E−3
|
|
|
|
Y, see
172
Ta
|
−
|
6E+4
|
3E−5
|
9E−8
|
−
|
−
|
73
|
Tantalum−186
b/
|
W, see
172
Ta
|
5E+4
|
2E+5
|
1E−4
|
3E−7
|
−
|
−
|
|
|
|
Y, see
172
Ta
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
74
|
Tungsten−176
|
D, all compounds
|
1E+4
|
5E+4
|
2E−5
|
7E−8
|
1E−4
|
1E−3
|
74
|
Tungsten−177
|
D, all compounds
|
2E+4
|
9E+4
|
4E−5
|
1E−7
|
3E−4
|
3E−3
|
74
|
Tungsten−178
|
D, all compounds
|
5E+3
|
2E+4
|
8E−6
|
3E−8
|
7E−5
|
7E−4
|
74
|
Tungsten−179
b/
|
D, all compounds
|
5E+5
|
2E+6
|
7E−4
|
2E−6
|
7E−3
|
7E−2
|
74
|
Tungsten−181
|
D, all compounds
|
2E+4
|
3E+4
|
1E−5
|
5E−8
|
2E−4
|
2E−3
|
74
|
Tungsten−185
|
D, all compounds
|
2E+3
|
7E+3
|
3E−6
|
9E−9
|
−
|
−
|
74
|
Tungsten−187
|
D, all compounds
|
2E+3
|
9E+3
|
4E−6
|
1E−8
|
3E−5
|
3E−4
|
74
|
Tungsten−188
|
D, all compounds
|
4E+2
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
75
|
Rhenium−177
b/
|
D, all compounds except those given for W
|
9E+4
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
|
|
|
W, oxides, hydroxides, and nitrates
|
−
|
4E+5
|
1E−4
|
5E−7
|
−
|
−
|
75
|
Rhenium−178
b/
|
D, see
177
Re
|
7E+4
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
|
|
|
W, see
177
Re
|
−
|
3E+5
|
1E−4
|
4E−7
|
−
|
−
|
75
|
Rhenium−181
|
D, see
177
Re
|
5E+3
|
9E+3
|
4E−6
|
1E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
177
Re
|
−
|
9E+3
|
4E−6
|
1E−8
|
−
|
−
|
75
|
Rhenium−182
|
D, see
177
Re
|
7E+3
|
1E+4
|
5E−6
|
2E−8
|
9E−5
|
9E−4
|
|
|
(12.7 h)
|
W, see
177
Re
|
−
|
2E+4
|
6E−6
|
2E−8
|
−
|
−
|
75
|
Rhenium−182
|
D, see
177
Re
|
1E+3
|
2E+3
|
1E−6
|
3E−9
|
2E−5
|
2E−4
|
|
|
(64.0 h)
|
W, see
177
Re
|
−
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
75
|
Rhenium−184m
|
D, see
177
Re
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
177
Re
|
−
|
4E+2
|
2E−7
|
6E−10
|
−
|
−
|
75
|
Rhenium−184
|
D, see
177
Re
|
2E+3
|
4E+3
|
1E−6
|
5E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
177
Re
|
−
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
75
|
Rhenium−186m
|
D, see
177
Re
|
1E+3
|
2E+3
|
7E−7
|
−
|
−
|
−
|
|
|
|
|
(2E+3)
|
(2E+3)
|
−
|
3E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
177
Re
|
−
|
2E+2
|
6E−8
|
2E−10
|
−
|
−
|
75
|
Rhenium−186
|
D, see
177
Re
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
177
Re
|
−
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
75
|
Rhenium−187
|
D, see
177
Re
|
6E+5
|
8E+5
|
4E−4
|
−
|
8E−3
|
8E−2
|
|
|
|
W, see
177
Re
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
75
|
Rhenium−188m
b/
|
D, see
177
Re
|
8E+4
|
1E+5
|
6E−5
|
2E−7
|
1E−3
|
1E−2
|
|
|
|
W, see
177
Re
|
−
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
75
|
Rhenium−188
|
D, see
177
Re
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
177
Re
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
75
|
Rhenium−189
|
D, see
177
Re
|
3E+3
|
5E+3
|
2E−6
|
7E−9
|
4E−5
|
4E−4
|
|
|
|
W, see
177
Re
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
76
|
Osmium−180
b/
|
D, all compounds except those given for W and Y
|
1E+5
|
4E+5
|
2E−4
|
5E−7
|
1E−3
|
1E−2
|
|
|
|
W, halides and nitrates
|
−
|
5E+5
|
2E−4
|
7E−7
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
5E+5
|
2E−4
|
6E−7
|
−
|
−
|
76
|
Osmium−181
b/
|
D, see
180
Os
|
1E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
180
Os
|
−
|
5E+4
|
2E−5
|
6E−8
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
76
|
Osmium−182
|
D, see
180
Os
|
2E+3
|
6E+3
|
2E−6
|
8E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
180
Os
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
76
|
Osmium−185
|
D, see
180
Os
|
2E+3
|
5E+2
|
2E−7
|
7E−10
|
3E−5
|
3E−4
|
|
|
|
W, see
180
Os
|
−
|
8E+2
|
3E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
8E+2
|
3E−7
|
1E−9
|
−
|
−
|
76
|
Osmium−189m
|
D, see
180
Os
|
8E+4
|
2E+5
|
1E−4
|
3E−7
|
1E−3
|
1E−2
|
|
|
|
W, see
180
Os
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
76
|
Osmium−191m
|
D, see
180
Os
|
1E+4
|
3E+4
|
1E−5
|
4E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
180
Os
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
76
|
Osmium−191
|
D, see
180
Os
|
2E+3
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
|
|
|
W, see
180
Os
|
−
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
76
|
Osmium−193
|
D, see
180
Os
|
2E+3
|
5E+3
|
2E−6
|
6E−9
|
−
|
−
|
|
|
|
W, see
180
Os
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
76
|
Osmium−194
|
D, see
180
Os
|
4E+2
|
4E+1
|
2E−8
|
6E−11
|
−
|
−
|
|
|
|
W, see
180
Os
|
−
|
6E+1
|
2E−8
|
8E−11
|
−
|
−
|
|
|
|
Y, see
180
Os
|
−
|
8E+0
|
3E−9
|
1E−11
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
77
|
Iridium−182
b/
|
D, all compounds except those given for W and Y
|
4E+4
|
1E+5
|
6E−5
|
2E−7
|
−
|
−
|
|
|
|
W, halides, nitrates, and metallic iridium
|
−
|
2E+5
|
6E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
1E+5
|
5E−5
|
2E−7
|
−
|
−
|
77
|
Iridium−184
|
D, see
182
Ir
|
8E+3
|
2E+4
|
1E−5
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
182
Ir
|
−
|
3E+4
|
1E−5
|
5E−8
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
77
|
Iridium−185
|
D, see
182
Ir
|
5E+3
|
1E+4
|
5E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
182
Ir
|
−
|
1E+4
|
5E−6
|
2E−8
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
1E+4
|
4E−5
|
1E−8
|
−
|
−
|
77
|
Iridium−186
|
D, see
182
Ir
|
2E+3
|
8E+3
|
3E−6
|
1E−8
|
3E−5
|
3E−4
|
|
|
|
W, see
182
Ir
|
−
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
6E+3
|
2E−6
|
8E−9
|
−
|
−
|
77
|
Iridium−187
|
D, see
182
Ir
|
1E+4
|
3E+4
|
1E−5
|
5E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
182
Ir
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
77
|
Iridium−188
|
D, see
182
Ir
|
2E+3
|
5E+3
|
2E−6
|
6E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
182
Ir
|
−
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
3E+3
|
1E−6
|
5E−9
|
−
|
−
|
77
|
Iridium−189
|
D, see
182
Ir
|
5E+3
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
|
|
|
W, see
182
Ir
|
−
|
4E+3
|
2E−6
|
5E−9
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
4E+3
|
1E−6
|
5E−9
|
−
|
−
|
77
|
Iridium−190m
b/
|
D, see
182
Ir
|
2E+5
|
2E+5
|
8E−5
|
3E−7
|
2E−3
|
2E−2
|
|
|
|
W, see
182
Ir
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
77
|
Iridium−190
|
D, see
182
Ir
|
1E+3
|
9E+2
|
4E−7
|
1E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
182
Ir
|
−
|
1E+3
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
77
|
Iridium−192m
|
D, see
182
Ir
|
3E+3
|
9E+1
|
4E−8
|
1E−10
|
4E−5
|
4E−4
|
|
|
|
W, see
182
Ir
|
−
|
2E+2
|
9E−8
|
3E−10
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
2E+1
|
6E−9
|
2E−11
|
−
|
−
|
77
|
Iridium−192
|
D, see
182
Ir
|
9E+2
|
3E+2
|
1E−7
|
4E−10
|
1E−5
|
1E−4
|
|
|
|
W, see
182
Ir
|
−
|
4E+2
|
2E−7
|
6E−10
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
2E+2
|
9E−8
|
3E−10
|
−
|
−
|
77
|
Iridium−194m
|
D, see
182
Ir
|
6E+2
|
9E+1
|
4E−8
|
1E−10
|
9E−6
|
9E−5
|
|
|
|
W, see
182
Ir
|
−
|
2E+2
|
7E−8
|
2E−10
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
1E+2
|
4E−8
|
1E−10
|
−
|
−
|
77
|
Iridium−194
|
D, see
182
Ir
|
1E+3
|
3E+3
|
1E−6
|
4E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
182
Ir
|
−
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
77
|
Iridium−195m
|
D, see
182
Ir
|
8E+3
|
2E+4
|
1E−5
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
182
Ir
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
77
|
Iridium−
195
|
D, see
182
Ir
|
1E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
182
Ir
|
−
|
5E+4
|
2E−5
|
7E−8
|
−
|
−
|
|
|
|
Y, see
182
Ir
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
78
|
Platinum−186
|
D, all compounds
|
1E+4
|
4E+4
|
2E−5
|
5E−8
|
2E−4
|
2E−3
|
78
|
Platinum−188
|
D, all compounds
|
2E+3
|
2E+3
|
7E−7
|
2E−9
|
2E−5
|
2E−4
|
78
|
Platinum−189
|
D, all compounds
|
1E+4
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
78
|
Platinum−191
|
D, all compounds
|
4E+3
|
8E+3
|
4E−6
|
1E−8
|
5E−5
|
5E−4
|
78
|
Platinum−193m
|
D, all compounds
|
3E+3
|
6E+3
|
3E−6
|
8E−9
|
−
|
−
|
78
|
Platinum−193
|
D, all compounds
|
4E+4
|
2E+4
|
1E−5
|
3E−8
|
−
|
−
|
78
|
Platinum−195m
|
D, all compounds
|
2E+3
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
78
|
Platinum−197m
b/
|
D, all compounds
|
2E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
78
|
Platinum−197
|
D, all compounds
|
3E+3
|
1E+4
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
78
|
Platinum−199
b/
|
D, all compounds
|
5E+4
|
1E+5
|
6E−5
|
2E−7
|
7E−4
|
7E−3
|
78
|
Platinum−200
|
D, all compounds
|
1E+3
|
3E+3
|
1E−6
|
5E−9
|
2E−5
|
2E−4
|
79
|
Gold−193
|
D, all compounds except those given for W and Y
|
9E+3
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
|
|
|
W, halides and nitrates
|
−
|
2E+4
|
9E−6
|
3E−8
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
2E+4
|
8E−6
|
3E−8
|
−
|
−
|
79
|
Gold−194
|
D, see
193
Au
|
3E+3
|
8E+3
|
3E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
W, see
193
Au
|
−
|
5E+3
|
2E−6
|
8E−9
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
79
|
Gold−195
|
D, see
193
Au
|
5E+3
|
1E+4
|
5E−6
|
2E−8
|
7E−5
|
7E−4
|
|
|
|
W, see
193
Au
|
−
|
1E+3
|
6E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
4E+2
|
2E−7
|
6E−10
|
−
|
−
|
79
|
Gold−198m
|
D, see
193
Au
|
1E+3
|
3E+3
|
1E−6
|
4E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
193
Au
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
79
|
Gold−198
|
D, see
193
Au
|
1E+3
|
4E+3
|
2E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
193
Au
|
−
|
2E+3
|
8E−7
|
3E−9
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
79
|
Gold−199
|
D, see
193
Au
|
3E+3
|
9E+3
|
4E−6
|
1E−8
|
−
|
−
|
|
|
|
W, see
193
Au
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
4E+3
|
2E−6
|
5E−9
|
−
|
−
|
79
|
Gold−200m
|
D, see
193
Au
|
1E+3
|
4E+3
|
1E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
193
Au
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
2E+4
|
1E−6
|
3E−9
|
−
|
−
|
79
|
Gold−200
b/
|
D, see
193
Au
|
3E+4
|
6E+4
|
3E−5
|
9E−8
|
4E−4
|
4E−3
|
|
|
|
W, see
193
Au
|
−
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
79
|
Gold−201
b/
|
D, see
193
Au
|
7E+4
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
|
|
|
W, see
193
Au
|
−
|
2E+5
|
1E−4
|
3E−7
|
−
|
−
|
|
|
|
Y, see
193
Au
|
−
|
2E+5
|
9E−5
|
3E−7
|
−
|
−
|
80
|
Mercury−193m
|
Vapor
|
−
|
8E+3
|
4E−6
|
1E−8
|
−
|
−
|
|
|
|
Organic D
|
4E+3
|
1E+4
|
5E−6
|
2E−8
|
6E−5
|
6E−4
|
|
|
|
D, sulfates
|
3E+3
|
9E+3
|
4E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
W, oxides, hydroxides, halides, nitrates, and sulfides
|
−
|
8E+3
|
3E−6
|
1E−8
|
−
|
−
|
80
|
Mercury−193
|
Vapor
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
|
|
|
Organic D
|
2E+4
|
6E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
|
|
|
D, see
193m
Hg
|
2E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
193m
Hg
|
−
|
4E+4
|
2E−5
|
6E−8
|
−
|
−
|
80
|
Mercury−194
|
Vapor
|
−
|
3E+1
|
1E−8
|
4E−11
|
−
|
−
|
|
|
|
Organic D
|
2E+1
|
3E+1
|
1E−8
|
4E−11
|
2E−7
|
2E−6
|
|
|
|
D, see
193m
Hg
|
8E+2
|
4E+1
|
2E−8
|
6E−11
|
1E−5
|
1E−4
|
|
|
|
W, see
193m
Hg
|
−
|
1E+2
|
5E−8
|
2E−10
|
−
|
−
|
80
|
Mercury−195m
|
Vapor
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
|
|
|
Organic D
|
3E+3
|
6E+3
|
3E−6
|
8E−9
|
4E−5
|
4E−4
|
|
|
|
D, see
193m
Hg
|
2E+3
|
5E+3
|
2E−6
|
7E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
193m
Hg
|
−
|
4E+3
|
2E−6
|
5E−9
|
−
|
−
|
80
|
Mercury−195
|
Vapor
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
|
|
|
Organic D
|
2E+4
|
5E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
D, see
193m
Hg
|
1E+4
|
4E+4
|
1E−5
|
5E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
193m
Hg
|
−
|
3E+4
|
1E−5
|
5E−8
|
−
|
−
|
80
|
Mercury−197m
|
Vapor
|
−
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
|
|
|
Organic D
|
4E+3
|
9E+3
|
4E−6
|
1E−8
|
5E−5
|
5E−4
|
|
|
|
D, see
193m
Hg
|
3E+3
|
7E+3
|
3E−6
|
1E−8
|
4E−5
|
4E−4
|
|
|
|
W, see
193m
Hg
|
−
|
5E+3
|
2E−6
|
7E−9
|
−
|
−
|
80
|
Mercury−197
|
Vapor
|
−
|
8E+3
|
4E−6
|
1E−8
|
−
|
−
|
|
|
|
Organic D
|
7E+3
|
1E+4
|
6E−6
|
2E−8
|
9E−5
|
9E−4
|
|
|
|
D, see
193m
Hg
|
6E+3
|
1E+4
|
5E−6
|
2E−8
|
8E−5
|
8E−4
|
|
|
|
W, see
193m
Hg
|
−
|
9E+3
|
4E−6
|
1E−8
|
−
|
−
|
80
|
Mercury−199m
b/
|
Vapor
|
−
|
8E+4
|
3E−5
|
1E−7
|
−
|
−
|
|
|
|
Organic D
|
6E+4
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
|
|
|
D, see
193m
Hg
|
6E+4
|
1E+5
|
6E−5
|
2E−7
|
8E−4
|
8E−3
|
|
|
|
W, see
193m
Hg
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
80
|
Mercury−203
|
Vapor
|
−
|
8E+2
|
4E−7
|
1E−9
|
−
|
−
|
|
|
|
Organic D
|
5E+2
|
8E+2
|
3E−7
|
1E−9
|
7E−6
|
7E−5
|
|
|
|
D, see
193m
Hg
|
2E+3
|
1E+3
|
5E−7
|
2E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
193m
Hg
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
81
|
Thallium−194m
b/
|
D, all compounds
|
5E+4
|
2E+5
|
6E−5
|
2E−7
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
81
|
Thallium−194
b/
|
D, all compounds
|
3E+5
|
6E+5
|
2E−4
|
8E−7
|
−
|
−
|
81
|
Thallium−195
b/
|
D, all compounds
|
6E+4
|
1E+5
|
5E−5
|
2E−7
|
9E−4
|
9E−3
|
81
|
Thallium−197
|
D, all compounds
|
7E+4
|
1E+5
|
5E−5
|
2E−7
|
1E−3
|
1E−2
|
81
|
Thallium−198m
b/
|
D, all compounds
|
3E+4
|
5E+4
|
2E−5
|
8E−8
|
4E−4
|
4E−3
|
81
|
Thallium−198
|
D, all compounds
|
2E+4
|
3E+4
|
1E−5
|
5E−8
|
3E−4
|
3E−3
|
81
|
Thallium−199
|
D, all compounds
|
6E+4
|
8E+4
|
4E−5
|
1E−7
|
9E−4
|
9E−3
|
81
|
Thallium−200
|
D, all compounds
|
8E+3
|
1E+4
|
5E−6
|
2E−8
|
1E−4
|
1E−3
|
81
|
Thallium−201
|
D, all compounds
|
2E+4
|
2E+4
|
9E−6
|
3E−8
|
2E−4
|
2E−3
|
81
|
Thallium−202
|
D, all compounds
|
4E+3
|
5E+3
|
2E−6
|
7E−9
|
5E−5
|
5E−4
|
81
|
Thallium−204
|
D, all compounds
|
2E+3
|
2E+3
|
9E−7
|
3E−9
|
2E−5
|
2E−4
|
82
|
Lead−195m
b/
|
D, all compounds
|
6E+4
|
2E+5
|
8E−5
|
3E−7
|
8E−4
|
8E−3
|
82
|
Lead−198
|
D, all compounds
|
3E+4
|
6E+4
|
3E−5
|
9E−8
|
4E−4
|
4E−3
|
82
|
Lead−199
b/
|
D, all compounds
|
2E+4
|
7E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
82
|
Lead−200
|
D, all compounds
|
3E+3
|
6E+3
|
3E−6
|
9E−9
|
4E−5
|
4E−4
|
82
|
Lead−201
|
D, all compounds
|
7E+3
|
2E+4
|
8E−6
|
3E−8
|
1E−4
|
1E−3
|
82
|
Lead−202m
|
D, all compounds
|
9E+3
|
3E+4
|
1E−5
|
4E−8
|
1E−4
|
1E−3
|
82
|
Lead−202
|
D, all compounds
|
1E+2
|
5E+1
|
2E−8
|
7E−11
|
2E−6
|
2E−5
|
82
|
Lead−203
|
D, all compounds
|
5E+3
|
9E+3
|
4E−6
|
1E−8
|
7E−5
|
7E−4
|
82
|
Lead−205
|
D, all compounds
|
4E+3
|
1E+3
|
6E−7
|
2E−9
|
5E−5
|
5E−4
|
82
|
Lead−209
|
D, all compounds
|
2E+4
|
6E+4
|
2E−5
|
8E−8
|
3E−4
|
3E−3
|
82
|
Lead−210
|
D, all compounds
|
6E−1
|
2E−1
|
1E−10
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(4E−1)
|
−
|
6E−13
|
1E−8
|
1E−7
|
82
|
Lead−211
b/
|
D, all compounds
|
1E+4
|
6E+2
|
3E−7
|
9E−10
|
2E−4
|
2E−3
|
82
|
Lead−212
|
D, all compounds
|
8E+1
|
3E+1
|
1E−8
|
5E−11
|
−
|
−
|
82
|
Lead−214
b/
|
D, all compounds
|
9E+3
|
8E+2
|
3E−7
|
1E−9
|
1E−4
|
1E−3
|
83
|
Bismuth−200
b/
|
D, nitrates
|
3E+4
|
8E+4
|
4E−5
|
1E−7
|
4E−4
|
4E−3
|
|
|
|
W, all other compounds
|
−
|
1E+5
|
4E−5
|
1E−7
|
−
|
−
|
83
|
Bismuth−201
b/
|
D, see
200
Bi
|
1E+4
|
3E+4
|
1E−5
|
4E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
200
Bi
|
−
|
4E+4
|
2E−5
|
5E−8
|
−
|
−
|
83
|
Bismuth−202
b/
|
D, see
200
Bi
|
1E+4
|
4E+4
|
2E−5
|
6E−8
|
2E−4
|
2E−3
|
|
|
|
W, see
200
Bi
|
−
|
6E+4
|
3E−5
|
1E−7
|
−
|
−
|
83
|
Bismuth−203
|
D, see
200
Bi
|
2E+3
|
7E+3
|
3E−6
|
9E−9
|
3E−5
|
3E−4
|
|
|
|
W, see
200
Bi
|
−
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
83
|
Bismuth−205
|
D, see
200
Bi
|
1E+3
|
3E+3
|
1E−6
|
3E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
200
Bi
|
−
|
1E+3
|
5E−7
|
2E−9
|
−
|
−
|
83
|
Bismuth−206
|
D, see
200
Bi
|
6E+2
|
1E+3
|
6E−7
|
2E−9
|
9E−6
|
9E−5
|
|
|
|
W, see
200
Bi
|
−
|
9E+2
|
4E−7
|
1E−9
|
−
|
−
|
83
|
Bismuth−207
|
D, see
200
Bi
|
1E+3
|
2E+3
|
7E−7
|
2E−9
|
1E−5
|
1E−4
|
|
|
|
W, see
200
Bi
|
−
|
4E+2
|
1E−7
|
5E−10
|
−
|
−
|
83
|
Bismuth−210m
|
D, see
200
Bi
|
4E+1
|
5E+0
|
2E−9
|
−
|
−
|
−
|
|
|
|
|
(6E+1)
|
(6E+0)
|
−
|
9E−12
|
8E−7
|
8E−6
|
|
|
|
W, see
200
Bi
|
−
|
7E−1
|
3E−10
|
9E−13
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
83
|
Bismuth−210
|
D, see
200
Bi
|
8E+2
|
2E+2
|
1E−7
|
−
|
1E−5
|
1E−4
|
|
|
|
W, see
200
Bi
|
−
|
3E+1
|
1E−8
|
4E−11
|
−
|
−
|
83
|
Bismuth−212
b/
|
D, see
200
Bi
|
5E+3
|
2E+2
|
1E−7
|
3E−10
|
7E−5
|
7E−4
|
|
|
|
W, see
200
Bi
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
83
|
Bismuth−213
b/
|
D, see
200
Bi
|
7E+3
|
3E+2
|
1E−7
|
4E−10
|
1E−4
|
1E−3
|
|
|
|
W, see
200
Bi
|
−
|
4E+2
|
1E−7
|
5E−10
|
−
|
−
|
83
|
Bismuth−214
b/
|
D, see
200
Bi
|
2E+4
|
8E+2
|
3E−7
|
1E−9
|
−
|
−
|
|
|
|
W, see
200
Bi
|
−
|
9E−2
|
4E−7
|
1E−9
|
−
|
−
|
84
|
Polonium−203
b/
|
D, all compounds except those given for W
|
3E+4
|
6E+4
|
3E−5
|
9E−8
|
3E−4
|
3E−3
|
|
|
|
W, oxides, hydroxides, and nitrates
|
−
|
9E+4
|
4E−5
|
1E−7
|
−
|
−
|
84
|
Polonium−205
b/
|
D, see
203
Po
|
2E+4
|
4E+4
|
2E−5
|
5E−8
|
3E−4
|
3E−3
|
|
|
|
W, see
203
Po
|
−
|
7E+4
|
3E−5
|
1E−7
|
−
|
−
|
84
|
Polonium−207
|
D, see
203
Po
|
8E+3
|
3E+4
|
1E−5
|
3E−8
|
1E−4
|
1E−3
|
|
|
|
W, see
203
Po
|
−
|
3E+4
|
1E−5
|
4E−8
|
−
|
−
|
84
|
Polonium−210
|
D, see
203
Po
|
3E+0
|
6E−1
|
3E−10
|
9E−13
|
4E−8
|
4E−7
|
|
|
|
W, see
203
Po
|
−
|
6E−1
|
3E−10
|
9E−13
|
−
|
−
|
85
|
Astatine−207
b/
|
D, halides
|
6E+3
|
3E+3
|
1E−6
|
4E−9
|
8E−5
|
8E−4
|
85
|
Astatine−211
|
D, halides
|
1E+2
|
8E+1
|
3E−8
|
1E−10
|
2E−6
|
2E−5
|
86
|
Radon−220
|
With daughters removed
|
−
|
2E+4
|
7E−6
|
2E−8
|
−
|
−
|
|
|
|
With daughters present
|
−
|
2E+1
|
9E−9
|
3E−11
|
−
|
−
|
86
|
Radon−222
|
With daughters removed
|
−
|
1E+4
|
4E−6
|
1E−8
|
−
|
−
|
|
|
|
With daughters present
|
−
|
1E+2
|
3E−8
|
1E−10
|
−
|
−
|
87
|
Francium−222
b/
|
D, all compounds
|
2E+3
|
5E+2
|
2E−7
|
6E−10
|
3E−5
|
3E−4
|
87
|
Francium−223
b/
|
D, all compounds
|
6E+2
|
8E+2
|
3E−7
|
1E−9
|
8E−6
|
8E−5
|
88
|
Radium−223
|
W, all compounds
|
5E+0
|
7E−1
|
3E−10
|
9E−13
|
−
|
−
|
88
|
Radium−224
|
W, all compounds
|
8E+0
|
2E+0
|
7E−10
|
2E−12
|
−
|
−
|
88
|
Radium−225
|
W, all compounds
|
8E+0
|
7E−1
|
3E−10
|
9E−13
|
−
|
−
|
88
|
Radium−226
|
W, all compounds
|
2E+0
|
6E−1
|
3E−10
|
9E−13
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
88
|
Radium−227
b/
|
W, all compounds
|
2E+4
|
1E+4
|
6E−6
|
−
|
−
|
−
|
|
|
|
|
(2E+4)
|
(2E+4)
|
−
|
3E−8
|
3E−4
|
3E−3
|
88
|
Radium−228
|
W, all compounds
|
2E+0
|
1E+0
|
5E−10
|
2E−12
|
−
|
−
|
89
|
Actinium−224
|
D, all compounds except those given for W and Y
|
2E+3
|
3E+1
|
1E−8
|
−
|
−
|
−
|
|
|
|
|
(2E+3)
|
(4E+1)
|
−
|
5E−11
|
3E−5
|
3E−4
|
|
|
|
W, halides and nitrates
|
−
|
5E+1
|
2E−8
|
7E−11
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
5E+1
|
2E−8
|
6E−11
|
−
|
−
|
89
|
Actinium−225
|
D, see
224
Ac
|
5E+1
|
3E−1
|
1E−10
|
−
|
−
|
−
|
|
|
|
|
(5E+1)
|
(5E−1)
|
−
|
7E−13
|
7E−7
|
7E−6
|
|
|
|
W, see
224
Ac
|
−
|
6E−1
|
3E−10
|
9E−13
|
−
|
−
|
|
|
|
Y, see
224
Ac
|
−
|
6E−1
|
3E−10
|
9E−13
|
−
|
−
|
89
|
Actinium−226
|
D, see
224
Ac
|
1E+2
|
3E+0
|
1E−9
|
−
|
−
|
−
|
|
|
|
|
(1E+2)
|
(4E+0)
|
−
|
5E−12
|
2E−6
|
2E−5
|
|
|
|
W, see
224
Ac
|
−
|
5E+0
|
2E−9
|
7E−12
|
−
|
−
|
|
|
|
Y, see
224
Ac
|
−
|
5E+0
|
2E−9
|
6E−12
|
−
|
−
|
89
|
Actinium−227
|
D, see
224
Ac
|
2E−1
|
4E−4
|
2E−13
|
−
|
−
|
−
|
|
|
|
|
(4E−1)
|
(8E−4)
|
−
|
1E−15
|
5E−9
|
5E−8
|
|
|
|
W, see
224
Ac
|
−
|
2E−3
|
7E−13
|
−
|
−
|
−
|
|
|
|
Y, see
224
Ac
|
−
|
4E−3
|
2E−12
|
6E−15
|
−
|
−
|
89
|
Actinium−228
|
D, see
224
Ac
|
2E+3
|
9E+0
|
4E−9
|
−
|
3E−5
|
3E−4
|
|
|
|
W, see
224
Ac
|
−
|
4E+1
|
2E−8
|
−
|
−
|
−
|
|
|
|
Y, see
224
Ac
|
−
|
4E+1
|
2E−8
|
6E−11
|
−
|
−
|
90
|
Thorium−226
b/
|
W, all compounds except those given for Y
|
5E+3
|
2E+2
|
6E−8
|
2E−10
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
1E+2
|
6E−8
|
2E−10
|
−
|
−
|
90
|
Thorium−227
|
W, see
226
Th
|
1E+2
|
3E−1
|
1E−10
|
5E−13
|
2E−6
|
2E−5
|
|
|
|
Y, see
226
Th
|
−
|
3E−1
|
1E−10
|
5E−13
|
−
|
−
|
90
|
Thorium−228
|
W, see
226
Th
|
6E+0
|
1E−2
|
4E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+1)
|
(2E−2)
|
−
|
3E−14
|
2E−7
|
2E−6
|
|
|
|
Y, see
226
Th
|
−
|
2E−2
|
7E−12
|
2E−14
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
90
|
Thorium−229
|
W, see
226
Th
|
6E−1
|
9E−4
|
4E−13
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(2E−3)
|
−
|
3E−15
|
2E−8
|
2E−7
|
|
|
|
Y, see
226
Th
|
−
|
2E−3
|
1E−12
|
−
|
−
|
−
|
90
|
Thorium−230
|
W, see
226
Th
|
4E+0
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(9E+0)
|
(2E−2)
|
−
|
2E−14
|
1E−7
|
1E−6
|
|
|
|
Y, see
226
Th
|
−
|
2E−2
|
6E−12
|
−
|
−
|
−
|
90
|
Thorium−231
|
W, see
226
Th
|
4E+3
|
6E+3
|
3E−6
|
9E−9
|
5E−5
|
5E−4
|
|
|
|
Y, see
226
Th
|
−
|
6E+3
|
3E−6
|
9E−9
|
−
|
−
|
90
|
Thorium−232
|
W, see
226
Th
|
7E−1
|
1E−3
|
5E−13
|
−
|
−
|
−
|
|
|
|
|
(2E+0)
|
(3E−3)
|
−
|
4E−15
|
3E−8
|
3E−7
|
|
|
|
Y, see
226
Th
|
−
|
3E−3
|
1E−12
|
−
|
−
|
−
|
90
|
Thorium−234
|
W, see
226
Th
|
3E+2
|
2E+2
|
8E−8
|
3E−10
|
−
|
−
|
|
|
|
Y, see
226
Th
|
−
|
2E+2
|
6E−8
|
2E−10
|
−
|
−
|
91
|
Protactinium−227
b/
|
W, all compounds except those given for Y
|
4E+3
|
1E+2
|
5E−8
|
2E−10
|
5E−5
|
5E−4
|
|
|
|
Y, oxides and hydroxides
|
−
|
1E+2
|
4E−8
|
1E−10
|
−
|
−
|
91
|
Protactinium−228
|
W, see
227
Pa
|
1E+3
|
1E+1
|
5E−9
|
−
|
2E−5
|
2E−4
|
|
|
|
Y, see
227
Pa
|
−
|
1E+1
|
5E−9
|
2E−11
|
−
|
−
|
91
|
Protactinium−230
|
W, see
227
Pa
|
6E+2
|
5E+0
|
2E−9
|
7E−12
|
−
|
−
|
|
|
|
Y, see
227
Pa
|
−
|
4E+0
|
1E−9
|
5E−12
|
−
|
−
|
91
|
Protactinium−231
|
W, see
227
Pa
|
2E−1
|
2E−3
|
6E−13
|
−
|
−
|
−
|
|
|
|
|
(5E−1)
|
(4E−3)
|
−
|
6E−15
|
6E−9
|
6E−8
|
|
|
|
Y, see
227
Pa
|
−
|
4E−3
|
2E−12
|
−
|
−
|
−
|
91
|
Protactinium−232
|
W, see
227
Pa
|
1E+3
|
2E+1
|
9E−9
|
−
|
2E−5
|
2E−4
|
|
|
|
Y, see
227
Pa
|
−
|
6E+1
|
2E−8
|
−
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
91
|
Protactinium−233
|
W, see
227
Pa
|
1E+3
|
7E+2
|
3E−7
|
1E−9
|
−
|
−
|
|
|
|
Y, see
227
Pa
|
−
|
6E+2
|
2E−7
|
8E−10
|
−
|
−
|
91
|
Protactinium−234
|
W, see
227
Pa
|
2E+3
|
8E+3
|
3E−6
|
1E−8
|
3E−5
|
3E−4
|
|
|
|
Y, see
227
Pa
|
−
|
7E+3
|
3E−6
|
9E−9
|
−
|
−
|
92
|
Uranium−230
|
D, UF
6
, UO
2
F
2
,
UO
2
,(NO
3
)
2
|
4E+0
|
4E−1
|
2E−10
|
−
|
−
|
−
|
|
|
|
|
(6E+0)
|
(6E−1)
|
−
|
8E−13
|
8E−8
|
8E−7
|
|
|
|
W, UO
3
, UF
4
, UCl
4
|
−
|
4E−1
|
1E−10
|
5E−13
|
−
|
−
|
|
|
|
Y, UO
2
, U
3
O
8
|
−
|
3E−1
|
1E−10
|
4E−13
|
−
|
−
|
92
|
Uranium−231
|
D, see
230
U
|
5E+3
|
8E+3
|
3E−6
|
1E−8
|
−
|
−
|
|
|
|
W, see
230
U
|
−
|
6E+3
|
2E−6
|
8E−9
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
5E+3
|
2E−6
|
6E−9
|
−
|
−
|
92
|
Uranium−232
|
D, see
230
U
|
2E+0
|
2E−1
|
9E−11
|
−
|
−
|
−
|
|
|
|
|
(4E+0)
|
(4E−1)
|
−
|
6E−13
|
6E−8
|
6E−7
|
|
|
|
W, see
230
U
|
−
|
4E−1
|
2E−10
|
5E−13
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
8E−3
|
3E−12
|
1E−14
|
−
|
−
|
92
|
Uranium−233
|
D, see
230
U
|
1E+1
|
1E+0
|
5E−10
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(2E+0)
|
−
|
3E−12
|
3E−7
|
3E−6
|
|
|
|
W, see
230
U
|
−
|
7E−1
|
3E−10
|
1E−12
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
4E−2
|
2E−11
|
5E−14
|
−
|
−
|
92
|
Uranium−234
c/
|
D, see
230
U
|
1E+1
|
1E+0
|
5E−10
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(2E+0)
|
−
|
3E−12
|
3E−7
|
3E−6
|
|
|
|
W, see
230
U
|
−
|
7E−1
|
3E−10
|
1E−12
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
4E−2
|
2E−11
|
5E−14
|
−
|
−
|
92
|
Uranium−235
c/
|
D, see
230
U
|
1E+1
|
1E+0
|
6E−10
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(2E+0)
|
−
|
3E−12
|
3E−7
|
3E−6
|
|
|
|
W, see
230
U
|
−
|
8E−1
|
3E−10
|
1E−12
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
4E−2
|
2E−11
|
6E−14
|
−
|
−
|
92
|
Uranium−236
|
D, see
230
U
|
1E+1
|
1E+0
|
5E−10
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(2E+0)
|
−
|
3E−12
|
3E−7
|
3E−6
|
|
|
|
W, see
230
U
|
−
|
8E−1
|
3E−10
|
1E−12
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
4E−2
|
2E−11
|
6E−14
|
−
|
−
|
92
|
Uranium−237
|
D, see
230
U
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
W, see
230
U
|
−
|
2E+3
|
7E−7
|
2E−9
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
2E+3
|
6E−7
|
2E−9
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
92
|
Uranium−238
c/
|
D, see
230
U
|
1E+1
|
1E+0
|
6E−10
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(2E+0)
|
−
|
3E−12
|
3E−7
|
3E−6
|
|
|
|
W, see
230
U
|
−
|
8E−1
|
3E−10
|
1E−12
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
4E−2
|
2E−11
|
6E−14
|
−
|
−
|
92
|
Uranium−239
b/
|
D, see
230
U
|
7E+4
|
2E+5
|
8E−5
|
3E−7
|
9E−4
|
9E−3
|
|
|
|
W, see
230
U
|
−
|
2E+5
|
7E−5
|
2E−7
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
2E+5
|
6E−5
|
2E−7
|
−
|
−
|
92
|
Uranium−240
|
D, see
230
U
|
1E+3
|
4E+3
|
2E−6
|
5E−9
|
2E−5
|
2E−4
|
|
|
|
W, see
230
U
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
2E+3
|
1E−5
|
3E−9
|
−
|
−
|
92
|
Uranium−
natural
c
/
|
D, see
230
U
|
1E+1
|
1E+0
|
5E−10
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(2E+0)
|
−
|
3E−12
|
3E−7
|
3E−6
|
|
|
|
W, see
230
U
|
−
|
8E−1
|
3E−10
|
9E−13
|
−
|
−
|
|
|
|
Y, see
230
U
|
−
|
5E−2
|
2E−11
|
9E−14
|
−
|
−
|
93
|
Neptunium−232
b/
|
W, all compounds
|
1E+5
|
2E+3
|
7E−7
|
−
|
2E−3
|
2E−2
|
93
|
Neptunium−233
b/
|
W, all compounds
|
8E+5
|
3E+6
|
1E−3
|
4E−6
|
1E−2
|
1E−1
|
93
|
Neptunium−234
|
W, all compounds
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
3E−5
|
3E−4
|
93
|
Neptunium−235
|
W, all compounds
|
2E+4
|
8E+2
|
3E−7
|
−
|
−
|
−
|
|
|
|
|
(2E+4)
|
(1E+3)
|
−
|
2E−9
|
3E−4
|
3E−3
|
93
|
Neptunium−236
|
W, all compounds
|
3E+0
|
2E−2
|
9E−12
|
−
|
−
|
−
|
|
|
(1.15E+5 y)
|
|
Bone surf
|
Bone surf
|
|
|
|
|
|
|
|
|
(6E+0)
|
(5E−2)
|
−
|
8E−14
|
9E−8
|
9E−7
|
93
|
Neptunium−236
|
W, all compounds
|
3E+3
|
3E+1
|
1E−8
|
−
|
−
|
−
|
|
|
(22.5 h)
|
|
Bone surf
|
Bone surf
|
|
|
|
|
|
|
|
|
(4E+3)
|
(7E+1)
|
−
|
1E−10
|
5E−5
|
5E−4
|
93
|
Neptunium−237
|
W, all compounds
|
5E−1
|
4E−3
|
2E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
1E−14
|
2E−8
|
2E−7
|
93
|
Neptunium−238
|
W, all compounds
|
1E+3
|
6E+1
|
3E−8
|
−
|
2E−5
|
2E−4
|
93
|
Neptunium−239
|
W, all compounds
|
2E+3
|
2E+3
|
9E−7
|
3E−9
|
−
|
−
|
93
|
Neptunium−240
b/
|
W, all compounds
|
2E+4
|
8E+4
|
3E−5
|
1E−7
|
3E−4
|
3E−3
|
94
|
Plutonium−234
|
W, all compounds except PuO
2
|
8E+3
|
2E+2
|
9E−8
|
3E−10
|
1E−4
|
1E−3
|
|
|
|
Y, PuO
2
|
−
|
2E+2
|
8E−8
|
3E−10
|
−
|
−
|
94
|
Plutonium−235
b/
|
W, see
234
Pu
|
9E+5
|
3E+6
|
1E−3
|
4E−6
|
1E−2
|
1E−1
|
|
|
|
Y, see
234
Pu
|
−
|
3E+6
|
1E−3
|
3E−6
|
−
|
−
|
94
|
Plutonium−236
|
W, see
234
Pu
|
2E+0
|
2E−2
|
8E−12
|
−
|
−
|
−
|
|
|
|
|
(4E+0)
|
(4E−2)
|
−
|
5E−14
|
6E−8
|
6E−7
|
|
|
|
Y, see
234
Pu
|
−
|
4E−2
|
2E−11
|
6E−14
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
94
|
Plutonium−237
|
W, see
234
Pu
|
1E+4
|
3E+3
|
1E−6
|
5E−9
|
2E−4
|
2E−3
|
|
|
|
Y, see
234
Pu
|
−
|
3E+3
|
1E−6
|
4E−9
|
−
|
−
|
94
|
Plutonium−238
|
W, see
234
Pu
|
9E−1
|
7E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(2E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
|
|
|
Y, see
234
Pu
|
−
|
2E−2
|
8E−12
|
2E−14
|
−
|
−
|
94
|
Plutonium−239
|
W, see
234
Pu
|
8E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
|
|
|
Y, see
234
Pu
|
−
|
2E−2
|
7E−12
|
−
|
−
|
−
|
94
|
Plutonium−240
|
W, see
234
Pu
|
8E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
|
|
|
Y, see
234
Pu
|
−
|
2E−2
|
7E−12
|
−
|
−
|
−
|
94
|
Plutonium−241
|
W, see
234
Pu
|
4E+1
|
3E−1
|
1E−10
|
−
|
−
|
−
|
|
|
|
|
(7E+1)
|
(6E−1)
|
−
|
8E−13
|
1E−6
|
1E−5
|
|
|
|
Y, see
234
Pu
|
−
|
8E−1
|
3E−10
|
−
|
−
|
−
|
94
|
Plutonium−242
|
W, see
234
Pu
|
8E−1
|
7E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
|
|
|
Y, see
234
Pu
|
−
|
2E−2
|
7E−12
|
−
|
−
|
−
|
94
|
Plutonium−243
|
W, see
234
Pu
|
2E+4
|
4E+4
|
2E−5
|
5E−8
|
2E−4
|
2E−3
|
|
|
|
Y, see
234
Pu
|
−
|
4E+4
|
2E−5
|
5E−8
|
−
|
−
|
94
|
Plutonium−244
|
W, see
234
Pu
|
8E−1
|
7E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(2E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
|
|
|
Y, see
234
Pu
|
−
|
2E−2
|
7E−12
|
−
|
−
|
−
|
94
|
Plutonium−245
|
W, see
234
Pu
|
2E+3
|
5E+3
|
2E−6
|
6E−9
|
3E−5
|
3E−4
|
|
|
|
Y, see
234
Pu
|
−
|
4E+3
|
2E−6
|
6E−9
|
−
|
−
|
94
|
Plutonium−246
|
W, see
234
Pu
|
4E+2
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
|
|
|
Y, see
234
Pu
|
−
|
3E+2
|
1E−7
|
4E−10
|
−
|
−
|
95
|
Americium−237
b/
|
W, all compounds
|
8E+4
|
3E+5
|
1E−4
|
4E−7
|
1E−3
|
1E−2
|
95
|
Americium−238b/
|
W, all compounds
|
4E+4
|
3E+3
|
1E−6
|
−
|
5E−4
|
5E−3
|
95
|
Americium−239
|
W, all compounds
|
5E+3
|
1E+4
|
5E−6
|
2E−8
|
7E−5
|
7E−4
|
95
|
Americium−240
|
W, all compounds
|
2E+3
|
3E+3
|
1E−6
|
4E−9
|
3E−5
|
3E−4
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
95
|
Americium−241
|
W, all compounds
|
8E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
95
|
Americium−242m
|
W, all compounds
|
8E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
95
|
Americium−242
|
W, all compounds
|
4E+3
|
8E+1
|
4E−8
|
−
|
5E−5
|
5E−4
|
95
|
Americium−243
|
W, all compounds
|
8E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
95
|
Americium−244m
b/
|
W, all compounds
|
6E+4
|
4E+3
|
2E−6
|
|
|
|
|
|
|
|
(8E+4)
|
(7E+3)
|
−
|
1E−8
|
1E−3
|
1E−2
|
95
|
Americium−244
|
W, all compounds
|
3E+3
|
2E+2
|
8E−8
|
−
|
4E−5
|
4E−4
|
95
|
Americium−245
|
W, all compounds
|
3E+4
|
8E+4
|
3E−5
|
1E−7
|
4E−4
|
4E−3
|
95
|
Americium−246m
b/
|
W, all compounds
|
5E+4
|
2E+5
|
8E−5
|
3E−7
|
−
|
−
|
95
|
Americium−246
b/
|
W, all compounds
|
3E+4
|
1E+5
|
4E−5
|
1E−7
|
4E−4
|
4E−3
|
96
|
Curium−238
|
W, all compounds
|
2E+4
|
1E+3
|
5E−7
|
2E−9
|
2E−4
|
2E−3
|
96
|
Curium−240
|
W, all compounds
|
6E+1
|
6E−1
|
2E−10
|
−
|
−
|
−
|
|
|
|
|
(8E+1)
|
(6E−1)
|
−
|
9E−13
|
1E−6
|
1E−5
|
96
|
Curium−241
|
W, all compounds
|
1E+3
|
3E+1
|
1E−8
|
−
|
2E−5
|
2E−4
|
96
|
Curium−242
|
W, all compounds
|
3E+1
|
3E−1
|
1E−10
|
−
|
−
|
−
|
|
|
|
|
(5E+1)
|
(3E−1)
|
−
|
4E−13
|
7E−7
|
7E−6
|
96
|
Curium−243
|
W, all compounds
|
1E+0
|
9E−3
|
4E−12
|
−
|
−
|
−
|
|
|
|
|
(2E+0)
|
(2E−2)
|
−
|
2E−14
|
2E−8
|
3E−7
|
96
|
Curium−244
|
W, all compounds
|
1E+0
|
1E−2
|
5E−12
|
−
|
−
|
−
|
|
|
|
|
(3E+0)
|
(2E−2)
|
−
|
3E−14
|
3E−8
|
3E−7
|
96
|
Curium−245
|
W, all compounds
|
7E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
96
|
Curium−246
|
W, all compounds
|
7E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
96
|
Curium−247
|
W, all compounds
|
8E−1
|
6E−3
|
3E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(1E−2)
|
−
|
2E−14
|
2E−8
|
2E−7
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
96
|
Curium−248
|
W, all compounds
|
2E−1
|
2E−3
|
7E−13
|
−
|
−
|
−
|
|
|
|
|
(4E−1)
|
(3E−3)
|
−
|
4E−15
|
5E−9
|
5E−8
|
96
|
Curium−249
b/
|
W, all compounds
|
5E+4
|
2E+4
|
7E−6
|
−
|
7E−4
|
7E−3
|
96
|
Curium−250
|
W, all compounds
|
4E−2
|
3E−4
|
1E−13
|
−
|
−
|
−
|
|
|
|
|
(6E−2)
|
(5E−4)
|
−
|
8E−16
|
9E−10
|
9E−9
|
97
|
Berkelium−245
|
W, all compounds
|
2E+3
|
1E+3
|
5E−7
|
2E−9
|
3E−5
|
3E−4
|
97
|
Berkelium−246
|
W, all compounds
|
3E+3
|
3E+3
|
1E−6
|
4E−9
|
4E−5
|
4E−4
|
97
|
Berkelium−247
|
W, all compounds
|
5E−1
|
4E−3
|
2E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(9E−3)
|
−
|
1E−14
|
2E−8
|
2E−7
|
97
|
Berkelium−249
|
W, all compounds
|
2E+2
|
2E+0
|
7E−10
|
−
|
−
|
−
|
|
|
|
|
(5E+2)
|
(4E+0)
|
−
|
5E−12
|
6E−6
|
6E−5
|
97
|
Berkelium−250
|
W, all compounds
|
9E+3
|
3E+2
|
1E−7
|
−
|
1E−4
|
1E−3
|
98
|
Californium−244
b/
|
W, all compounds except those given for Y
|
3E+4
|
6E+2
|
2E−7
|
8E−10
|
−
|
−
|
|
|
|
Y, oxides and hydroxides
|
−
|
6E+2
|
2E−7
|
8E−10
|
−
|
−
|
98
|
Californium−246
|
W, see
244
Cf
|
4E+2
|
9E+0
|
4E−9
|
1E−11
|
5E−6
|
5E−5
|
|
|
|
Y, see
244
Cf
|
−
|
9E+0
|
4E−9
|
1E−11
|
−
|
−
|
98
|
Californium−248
|
W, see
244
Cf
|
8E+0
|
6E−2
|
3E−11
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(1E−1)
|
−
|
2E−13
|
2E−7
|
2E−6
|
|
|
|
Y, see
244
Cf
|
−
|
1E−1
|
4E−11
|
1E−13
|
−
|
−
|
98
|
Californium−249
|
W, see
244
Cf
|
5E−1
|
4E−3
|
2E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(9E−3)
|
−
|
1E−14
|
2E−8
|
2E−7
|
|
|
|
Y, see
244
Cf
|
−
|
1E−2
|
4E−12
|
−
|
−
|
−
|
98
|
Californium−250
|
W, see
244
Cf
|
1E+0
|
9E−3
|
4E−12
|
−
|
−
|
−
|
|
|
|
|
(2E+0)
|
(2E−2)
|
−
|
3E−14
|
3E−8
|
3E−7
|
|
|
|
Y, see
244
Cf
|
−
|
3E−2
|
1E−11
|
4E−14
|
−
|
−
|
98
|
Californium−251
|
W, see
244
Cf
|
5E−1
|
4E−3
|
2E−12
|
−
|
−
|
−
|
|
|
|
|
(1E+0)
|
(9E−3)
|
−
|
1E−14
|
2E−8
|
2E−7
|
|
|
|
Y, see
244
Cf
|
−
|
1E−2
|
4E−12
|
−
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
98
|
Californium−252
|
W, see
244
Cf
|
2E+0
|
2E−2
|
8E−12
|
−
|
−
|
−
|
|
|
|
|
(5E+0)
|
(4E−2)
|
−
|
5E−14
|
7E−8
|
7E−7
|
|
|
|
Y, see
244
Cf
|
−
|
3E−2
|
1E−11
|
5E−14
|
−
|
−
|
98
|
Californium−253
|
W, see
244
Cf
|
2E+2
|
2E+0
|
8E−10
|
3E−12
|
−
|
−
|
|
|
|
Y, see
244
Cf
|
−
|
2E+0
|
7E−10
|
2E−12
|
−
|
−
|
98
|
Californium−254
|
W, see
244
Cf
|
2E+0
|
2E−2
|
9E−12
|
3E−14
|
3E−8
|
3E−7
|
|
|
|
Y, see
244
Cf
|
−
|
2E−2
|
7E−12
|
2E−14
|
−
|
−
|
99
|
Einsteinium−250
|
W, all compounds
|
4E+4
|
5E+2
|
2E−7
|
−
|
6E−4
|
6E−3
|
99
|
Einsteinium−251
|
W, all compounds
|
7E+3
|
9E+2
|
4E−7
|
−
|
1E−4
|
1E−3
|
99
|
Einsteinium−253
|
W, all compounds
|
2E+2
|
1E+0
|
6E−10
|
2E−12
|
2E−6
|
2E−5
|
99
|
Einsteinium−254m
|
W, all compounds
|
3E+2
|
1E+1
|
4E−9
|
1E−11
|
−
|
−
|
99
|
Einsteinium−254
|
W, all compounds
|
8E+0
|
7E−2
|
3E−11
|
−
|
−
|
−
|
|
|
|
|
(2E+1)
|
(1E−1)
|
−
|
2E−13
|
2E−7
|
2E−6
|
100
|
Fermium−252
|
W, all compounds
|
5E+2
|
1E+1
|
5E−9
|
2E−11
|
6E−6
|
6E−5
|
100
|
Fermium−253
|
W, all compounds
|
1E+3
|
1E+1
|
4E−9
|
1E−11
|
1E−5
|
1E−4
|
100
|
Fermium−254
|
W, all compounds
|
3E+3
|
9E+1
|
4E−8
|
1E−10
|
4E−5
|
4E−4
|
100
|
Fermium−255
|
W, all compounds
|
5E+2
|
2E+1
|
9E−9
|
3E−11
|
7E−6
|
7E−5
|
100
|
Fermium−257
|
W, all compounds
|
2E+1
|
2E−1
|
7E−11
|
−
|
−
|
−
|
|
|
|
|
(4E+1)
|
(2E−1)
|
−
|
3E−13
|
5E−7
|
5E−6
|
101
|
Mendelevium−257
|
W, all compounds
|
7E+3
|
8E+1
|
4E−8
|
−
|
1E−4
|
1E−3
|
101
|
Mendelevium−258
|
W, all compounds
|
3E+1
|
2E−1
|
1E−10
|
−
|
−
|
−
|
|
|
|
|
(5E+1)
|
(3E−1)
|
−
|
5E−13
|
6E−7
|
6E−6
|
−Any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half− life less than 2 hours
|
Submersion
a
/
|
−
|
2E+2
|
1E−7
|
1E−9
|
−
|
−
|
−Any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half− life greater than 2 hours
|
. . . .
|
−
|
2E−1
|
1E−10
|
1E−12
|
1E−8
|
1E−7
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
−Any single radionuclide not listed above that decays by alpha emission or spontaneous fission, or any mixture for which either the identity or the concentration of any radionuclide in the mixture is not known
|
. . . .
|
−
|
4E−4
|
2E−13
|
1E−15
|
2E−9
|
2E−8
|
Footnotes:
a
/ “Submersion” means that values given are for submersion in a hemispherical semi−infinite cloud of airborne material.
b
/ These radionuclides have radiological half−lives of less than 2 hours. The total effective dose equivalent received during operations with these radionuclides might include a significant contribution from external exposure. The DAC values for all radionuclides, other than those designated Class “Submersion,” are based upon the committed effective dose equivalent due to the intake of the radionuclide into the body and do NOT include potentially significant contributions to dose equivalent from external exposures. The licensee may substitute 1E−7
Ci/ml for the listed DAC to account for the submersion dose prospectively, but should use individual monitoring devices or other radiation measuring instruments that measure external exposure to demonstrate compliance with the limits. (See s.
DHS 157.22 (3)
)
c
/ For soluble mixtures of U−238, U−234, and U−235 in air, chemical toxicity may be the limiting factor (see D.201e.). If the percent by weight enrichment of U−235 is not greater than 5, the concentration value for a 40−hour workweek is 0.2 milligrams uranium per cubic meter of air average. For any enrichment, the product of the average concentration and time of exposure during a 40−hour workweek may not exceed 8E−3 (SA)
Ci−
hr
/ml, where SA is the specific activity of the uranium inhaled. The specific activity for natural uranium is 6.77E−7 curies per gram U. The specific activity for other mixtures of U−238, U−235, and U−234, if not known, shall be:
SA = 3.6E−7 curies/gram U U−depleted
SA = [0.4 + 0.38 enrichment + 0.0034 enrichment
2
] E−6, enrichment > 0.72
where
enrichment is the percentage by weight of U−235, expressed as percent.
Note:
1. If the identity of each radionuclide in a mixture is known but the concentration of one or more of the radionuclides in the mixture
is
not known, the DAC for the mixture shall be the most restrictive DAC of any radionuclide in the mixture.
2. If the identity of each radionuclide in the mixture is not known, but it is known that certain radionuclides specified in this appendix are not present in the mixture, the inhalation ALI, DAC, and effluent and sewage concentrations for the mixture are the lowest values specified in this appendix for any radionuclide that is not known to be absent from the mixture; or
If it is known that Ac−227−D and Cm−250−W are not present
|
−
|
7E−4
|
3E−13
|
−
|
−
|
−
|
|
If, in addition, it is known that Ac−227−W,Y, Th−229−W,Y, Th−230−W, Th−232−W,Y, Pa−231−W,Y, Np−237−W, Pu−239−W, Pu−240−W, Pu−242−W, Am−241−W, Am−242m−W, Am−243−W, Cm−245−W, Cm−246−W, Cm−247−W, Cm−248−W, Bk−247−W, Cf−249−W, and Cf−251−W are not present
|
−
|
7E−3
|
3E−12
|
−
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
If, in addition, it is known that Sm−146−W, Sm−147−W, Gd−148−D
,W
, Gd−152−D,W, Th−228−W,Y, Th−230−Y, U−232−Y, U−233−Y, U−234−Y, U−235−Y, U−236−Y, U−238−Y, Np−236−W, Pu−236−W,Y, Pu−238−W,Y, Pu−239−Y, Pu−240−Y, Pu−242−Y, Pu−244−W,Y, Cm−243−W, Cm−244−W, Cf−248−W, Cf−249−Y, Cf−250−W,Y, Cf−251−Y, Cf−252−W,Y, and Cf−254−W,Y are not present. . . .
|
7E−2
|
3E−11
|
−
|
−
|
−
|
|
If, in addition, it is known that Pb−210−D, Bi−210m−W, Po−210−D,W, Ra−223−W, Ra−225−W, Ra−226−W, Ac−225−D,W,Y, Th−227−W,Y, U−230−D,W,Y, U−232−D,W, Pu−241−W, Cm−240−W, Cm−242−W, Cf−248−Y, Es−254−W, Fm−257−W, and Md−258−W are not present
|
−
|
7E−1
|
3E−10
|
−
|
−
|
−
|
If, in addition, it is known that Si−32−Y,
Ti−44−Y, Fe−60−D, Sr−90−Y, Zr−93−D,
Cd−113m−D, Cd−113−D, In−115−D,W, La−138−D,
Lu−176−W, Hf−178m−D,W, Hf−182−D,W, Bi−210m−D,
Ra−224−W, Ra−228−W, Ac−226−D,W,Y, Pa−230−W,Y,
U−233−D,W, U−234−D,W, U−235−D,W, U−236−D,W,
U−238−D,W, Pu−241−Y, Bk−249−W, Cf−253−W,Y,
and Es−253−W are not present
|
−
|
7E+0
|
3E−9
|
−
|
−
|
−
|
If it is known that Ac−227−D,W,Y, Th−229−W,Y, Th−232−W,Y, Pa−231−W,Y, Cm−248−W, and Cm−250−W are not present
|
−
|
−
|
−
|
1E−14
|
−
|
−
|
If, in addition, it is known that Sm−146−W, Gd−148−D,W, Gd−152−D, Th−228−W,Y, Th−230−W,Y, U−232−Y, U−233−Y, U−234−Y, U−235−Y, U−236−Y, U−238−Y, U−Nat−Y, Np−236−W, Np−237−W, Pu−236−W,Y, Pu−238−W,Y, Pu−239−W,Y, Pu−240−W,Y, Pu−242−W,Y, Pu−244−W,Y, Am−241−W, Am−242m−W, Am−243−W, Cm−243−W, Cm−244−W, Cm−245−W, Cm−246−W, Cm−247−W, Bk−247−W, Cf−249−W,Y, Cf−250−W,Y, Cf−251−W,Y, Cf−252−W,Y, and Cf−254−W,Y are not present
|
−
|
−
|
−
|
1E−13
|
−
|
|
If, in addition, it is known that Sm−147−W, Gd−152−W, Pb−210−D, Bi−210m−W, Po−210−D,W, Ra−223−W, Ra−225−W, Ra−226−W, Ac−225−D,W,Y, Th−227−W,Y, U−230−D,W,Y, U−232−D,W, U−Nat−W, Pu−241−W, Cm−240−W, Cm−242−W, Cf−248−W,Y, Es−254−W, Fm−257−W, and Md−258−W are not present
|
−
|
−
|
−
|
1E−12
|
−
|
−
|
Annual Limits on Intake (ALI) & Derived Air Concentrations (DAC) of
Radionuclides for Occupational Exposure Effluent Concentrations
Concentrations for Release to Sanitary Sewerage (Continued)
|
|
|
|
|
Table I
|
Table II
|
Table III
|
|
|
|
|
Occupational Values
|
Effluent Concentrations
|
Releases to Sewers
|
|
|
|
|
Col. 1
|
Col. 2
|
Col. 3
|
Col. 1
|
Col. 2
|
|
|
|
|
|
Oral Ingestion
|
Inhalation
|
|
|
Monthly Average
|
Atomic
|
|
|
ALI
|
ALI
|
DAC
|
Air
|
Water
|
Concentration
|
No.
|
Radionuclide
|
Class
|
(
µ
Ci)
|
(
µ
Ci)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
(
µ
Ci/ml)
|
If, in addition it is known that Fe−60,
Sr−90, Cd−113m, Cd−113, In−115, I−129,
Cs−134, Sm−145, Sm−147, Gd−148, Gd−152,
Hg−194 (organic), Bi−210m, Ra−223, Ra−224,
Ra−225, Ac−225, Th−228, Th−230, U−233, U−234,
U−235, U−236, U−238, U−Nat, Cm−242, Cf−248,
Es−254, Fm−257, and Md−258 are not present
|
−
|
−
|
−
|
−
|
1E−6
|
1E−5
|
3. If a mixture of radionuclides consists of uranium and its daughters in ore dust (10
m AMAD particle distribution assumed) prior to chemical separation of the uranium from the ore, the following values may be used for the DAC of the mixture: 6E−11
Ci of gross alpha activity from uranium−238, uranium−234, thorium−230, and radium−226 per milliliter of air; 3E−11
Ci of natural uranium per milliliter of air; or 45 micrograms of natural uranium per cubic meter of air.
4. If the identity and concentration of each radionuclide in a mixture are known, the limiting values should be derived as follows: determine, for each radionuclide in the mixture, the ratio between the concentration present in the mixture and the concentration otherwise established in Appendix E for the specific radionuclide when not in a mixture. The sum of such ratios for all of the radionuclides in the mixture may not exceed “1,” which is “unity”.
Example: If radionuclides “A,” “B,” and “C” are present in concentrations C
A
, C
B
, and C
C
, and if the applicable DACs are DAC
A
, DAC
B
, and DAC
C
, respectively, then the concentrations shall be limited so that the following relationship exists:
Á
_________________________
SECTION
100
.
DHS 157 Appendix H Table V is
repealed and recreated
to read:
T
ABLE
V
(See PDF for image)
Radionuclide
|
Concentration
Curie/Cubic Meter
a/
|
|
Column 1
|
Column 2
|
Column 3
|
T
otal of all radionuclides with less than
5−yea
r
half−life
|
700
|
*
|
*
|
Ni−6
3
i
n
activate
d
metal
|
35
|
700
|
7000
|
a
/
Note:
T
o
convert
the
Ci/m3
value
to
gigabecque
r
el
(
GBq
)
per
cubic
mete
r
,
multiply
the
Ci/m3
value
by
37.
The
r
e
a
r
e
no
limits established
fo
r
thes
e
radionuclide
s
i
n
Clas
s
B
o
r
C
wastes
.
Practica
l
consideration
s
suc
h
a
s
th
e
effect
s
o
f
externa
l
radiatio
n
and
internal
hea
t
generatio
n
o
n
transportation
,
handling
,
an
d
disposa
l
wil
l
limi
t
th
e
concentration
s
fo
r
thes
e
wastes
.
Thes
e
waste
s
shall
be
Class
B
unless
the
concentrations
of
other
radionuclides
in
T
able
V
determine
the
waste
to
be
Class
C
independent
of
these radionuclides
SECTION
10
1
.
DHS 157 Appendix I
is
repealed and recreated
to read:
APPENDIX I
(See PDF for image)
Quantities for Use with Decommissioning under Section
DHS 157.15
NOTE:
To convert
Ci to
kBq
, multiply the
Ci value by 37.
Material
Microcurie
Americium−
241
0.01
Antimony−122
100
Antimony−124
10
Antimony−
125
10
Arsenic−
73
100
Arsenic−
74
10
Arsenic−
76
10
Arsenic−
77
100
Barium−
131
10
Barium−
133
10
Barium−
140
10
Bismuth−
210
1
Bromine−
82
10
Cadmium−
109
10
Cadmium−
115m
10
Cadmium−
115
100
Calcium−
45
10
Calcium−
47
10
Carbon−
14
100
Cerium−
141
100
Cerium−
143
100
Cerium−
144
1
Cesium−
131
1,000
Cesium−
134m
100
Cesium−
134
1
Cesium−
135
10
Cesium−
136
10
Cesium−137
10
Chlorine−
36
10
Chlorine−
38
10
Chromium−
51
1,000
Cobalt−57
100
Cobalt−
58m
10
Cobalt−
58
10
Cobalt−
60
1
Copper−
64
100
Material
Microcurie
Dysprosium−165
10
Dysprosium−166
100
Erbium−169
100
Erbium−171
100
Europium−152 (9.2 h)
100
Europium−152 (13
yr
)
1
Europium−154
1
Europium−155
10
Fluorine−
18
1,000
Gadolinium−
153
10
Gadolinium−
159
100
Gallium−
72
10
Germanium−68
10
Germanium−71
100
Gold−195
10
Gold−
198
100
Gold−
199
100
Hafnium−
181
10
Holmium−
166
100
Hydrogen−
3
1,000
Indium−
113m
100
Indium−
114m
10
Indium−
115m
100
Indium−
115
10
Iodine−
125
1
Iodine−
126
1
Iodine−
129
0.1
Iodine−
131
1
Iodine−
132
10
Iodine−
133
1
Iodine−
134
10
Iodine−
135
10
Iridium−
192
10
Iridium−
194
100
Iron−
55
100
Iron−
59
10
Krypton−85
100
Krypton−
87
10
Lanthanum−
140
10
Lutetium−
177
100
Manganese−
52
10
Manganese−
54
10
Manganese−
56
10
Material
Microcurie
Mercury−
197m
100
Mercury−
197
100
Mercury−203
10
Molybdenum−
99
100
Neodymium−
147
100
Neodymium−
149
100
Nickel−
59
100
Nickel−
63
10
Nickel−
65
100
Niobium−
93m
10
Niobium−
95
10
Niobium−
97
10
Osmium−
185
10
Osmium−
191m
100
Osmium−
191
100
Osmium−
193
100
Palladium−
103
100
Palladium−
109
100
Phosphorus−
32
10
Platinum−
191
100
Platinum−
193m
100
Platinum−
193
100
Platinum−
197m
100
Platinum−
197
100
Plutonium−
239
0.01
Polonium−
210
0.1
Potassium−
42
10
Praseodymium−142
100
Praseodymium−
143
100
Promethium−
147
10
Promethium−
149
10
Radium−
226
0.01
Rhenium−
186
100
Rhenium−
188
100
Rhodium−
103m
100
Rhodium−
105
100
Rubidium−
86
10
Rubidium−
87
10
Ruthenium−
97
100
Ruthenium−
103
10
Ruthenium−
105
10
Material
Microcurie
Ruthenium−
106
1
Samarium−
151
10
Samarium−
153
100
Scandium−
46
10
Scandium−
47
100
Scandium−
48
10
Selenium−
75
10
Silicon−
31
100
Silver−
105
10
Silver−
110m
1
Silver−
111
100
Sodium−
22
10
Sodium−
24
10
Strontium−
85
10
Strontium−
89
1
Strontium−
90
0.1
Strontium−
91
10
Strontium−
92
10
Sulfur −
35
100
Tantalum−
182
10
Technetium−
96
10
Technetium−
97m
100
Technetium−
97
100
Technetium−
99m
100
Technetium−
99
10
Tellurium−
125m
10
Tellurium−127m
10
Tellurium−
127
100
Tellurium−
129m
10
Tellurium−
129
100
Tellurium−
131m
10
Tellurium−
132
10
Terbium−
160
10
Thallium−
200
100
Thallium−
201
100
Thallium−
202
100
Thallium−
204
10
Thorium (natural
)
c
/
100
Thulium−170
.
10
Thulium−
171
10
Tin−
113
10
Material
Microcurie
Tin−
125
10
Tungsten−
181
10
Tungsten−
185
10
Tungsten−
187
100
Uranium (natural
)
d
/
100
Uranium−
233
0.01
Uranium−
234
0.01
Uranium−
235
0.01
Vanadium−
48
10
Xenon−
131m
1,000
Xenon−
133
100
Xenon−
135
100
Ytterbium−
175
100
Yttrium−
90
10
Yttrium−
91
10
Yttrium−
92
100
Yttrium−
93
100
Zinc−
65
10
Zinc−
69m
100
Zinc−
69
1,000
Zirconium−
93
10
Zirconium−
95
10
Zirconium−
97
10
Any alpha emitting radionuclide not listed above or
mixtures
of alpha emitters of unknown composition
0.01
Any radionuclide other than alpha emitting radionuclides,
not
listed above or mixtures of beta emitters of unknown
composition
0.1
c
/
Based on alpha disintegration rate of Th−232, Th−230 and their daughter products.
d
/
Based on alpha disintegration rate of U−238, U−234, and U−235
Note:
Where there is involved a combination of isotopes in known amounts, the limit for the combination should be derived as follows: Determine, for each isotope in the combination, the ratio between the quantity present in the combination and the limit otherwise established for the specific isotope when not in combination. The sum of the ratios for all the isotopes in the combination may not exceed “1” — that is, unity.
Section
10
2
.
DHS 157 Appendix M is
repealed and recreated
to read:
APPENDIX M
Information to be
Submitted
by Persons
Proposing to Conduct Healing Arts Screening
Persons requesting that the department approve a healing arts screening program shall submit the following information and evaluation. Mammography screening
,
bone density screening and National Cancer Institute approved low dose CT lung screening are exempt from this requirem
ent unless persons under age 18 are involved:
a.
Name and address of the applicant and, where applicable, the names and addresses of agents within this state.
b.
Diseases or conditions for which the x
-
ray examinations are to be used in diagnoses.
c.
A detailed description of the x
-
ray examinations proposed in the screening program.
d.
A description of the population to be examined in the screening program, which is age, sex, physical condition, and other appropriate information. If the study involves women of reproductive age and the exam involves the trunk of the body, what precautions are being taken to ensure the subjects are not
pregnant.
e.
An evaluation of any known alternate methods not involving ionizing radiation which could achieve the goals of the screening program and why these methods are not used instead of the x
-
ray examinations.
f.
An evaluation by a medical physicist of the x
-
ray system to be used in the screening program. The evaluation by the medical physicist shall show that the system satisfies all requirements of this chapter. The evaluation shall include a measurement of patient exposures from the x
-
ray examinations to be performed. This exposure information must be included in the informed consent papers signed by the subject. An explanation of the risk from the radiation exposure shall be included in the informed consent if the head, neck or trunk is involved in the procedure.
g.
The name and address of the individual who will interpret the radiograph or images if any are produced. The interpreting physicians must be licensed in Wisconsin.
h.
A description of the procedures to be used in advising the individuals screened and their private practitioners of the healing arts of the results of the screening procedure and any further medical needs indicated.
i.
A description of the procedures for the retention or disposition of the radiographs, images, graphs and other records pertaining to the x
-
ray examinations.
j.
An indication of the frequency of screening and the duration of the entire screening program.
k.
Human
-
use committee approval of the screening program if one is required by local policy.
l.
A copy of the informed consent information being provided to the subjects.
m.
If minors are involved, parental consent is required.
SECTION
10
3
.
DHS 157 Appendix O is
repealed and recreated
to read:
APPENDIX O
(See PDF for image)
Determination of A
1
and A
2
I.
Values of A
1
and A
2
for individual radionuclides, which are the bases for many activity limits elsewhere in these regulations, are given in TABLE VI. The curie (Ci) values specified are obtained by converting from the
Terabecquerel
(
TBq
) figure. The curie values are expressed to 3 significant figures to assure that the difference in the
TBq
and Ci quantities is one tenth of one percent or less. Where values of A
1
or A
2
are unlimited, it is for radiation control purposes only. For nuclear criticality safety, some materials are subject to controls placed on fissile material.
II.
(a)
For individual radionuclides whose identities are known, but which are not listed in TABLE VI, the determination of the values of A
1
and A
2
requires department approval, except that the values of A
1
and A
2
in TABLE VIII may be used without obtaining department approval.
(
b
)
For individual radionuclides whose identities are known, but which are not listed in Table VII, the exempt material activity concentration and exempt consignment activity values contained in Table VIII may be used. Otherwise, the licensee shall obtain prior department approval of the exempt material activity concentration and exempt consignment activity values for radionuclides not listed in Table VII, before shipping the material.
(c)
The licensee shall submit requests for prior approval, described under paragraphs
II(
a) and II(b) of this Appendix, in writing to the department.
III.
In the calculations of A
1
and A
2
for a radionuclide not in TABLE VI, a single radioactive decay chain, in which radionuclides are present in their naturally occurring proportions, and in which no daughter nuclide has a half−life either longer than 10 days, or longer than that of the parent nuclide, shall be considered as a single radionuclide, and the activity to be taken into account, and the A
1
or A
2
value to be applied shall be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any daughter nuclide has a half−life either longer than 10 days, or greater than that of the parent nuclide, the parent and those daughter nuclides shall be considered as mixtures of different nuclides.
IV.
For mixtures of radionuclides whose identities and respective activities are known, the following conditions apply:
(a)
For special form radioactive material, the maximum quantity transported in a Type A package is as follows:
where
B(
i
) is the activity of radionuclide
i
in special form,
and A
1
(
i
) is the A
1
value for radionuclide
i
.
(b)
For normal form radioactive material, the maximum quantity transported in a Type A package is as follows:
where
B(
i
) is the activity of radionuclide
i
in normal form,
and A
2
(
i
) is the value for radionuclide
i
.
(c)
If the package contains both special and normal form radioactive material, the activity that may be transported in a Type A package is as follows:
w
here
B(
i
) is the activity of radionuclide
i
as special form radioactive material,
A
1
(
i
) is the A
1
value for radionuclide
i,
C(
j
) is the activity of radionuclide
j
as normal form radioactive material,
A
2
(
j
) is the A
2
value for radionuclide
j
.
(d)
Alternatively, the A
1
value for mixtures of special form material may be determined as follows:
where
f(i) is the fraction of activity of nuclide (i) in the mixture and A
1
(i) is the appropriate A
1
value for nuclide i.
(e)
Alternatively the A
2
value for mixtures of normal form material may be determined as follows:
where
f(i) is the fraction of activity for radionuclide (i) in the mixture, and A
2
(i) is the appropriate A
2
value for radionuclide (i).
(f
)
The exempt activity concentration for mixtures of nuclides may be determined as follows:
where
f(i) is the fraction of activity concentration of radionuclide (i) in the mixture, and [A] is the activity concentration for exempt material containing radionuclide (i).
(g
)
The activity limit for an exempt consignment for mixtures of radionuclides may be determined as follows:
where
f(i) is the fraction of activity of radionuclide (i) in the mixture, and A is the activity limit for exempt consignments for radionuclide (i).
V.
(a)
When the identity of each radionuclide is known, but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest A
1
or A
2
value, as appropriate, for the radionuclides in each group may be used in applying the formulas in paragraph IV. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest A
1
or A
2
values for the alpha emitters and beta/gamma emitters.
(b)
When the identity of each radionuclide is known but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest [A] (activity concentration for exempt material) or A (activity limit for exempt consignment) value, as appropriate, for the radionuclides in each group may be used in applying the formulas
in paragraph IV
. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest [A] or
A
values for the alpha emitters and beta/gamma emitters, respectively.
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Ac−225 (a)
|
Actinium (89)
|
8.0X10
−1
|
2.2X10
1
|
6.0X10
−3
|
1.6X10
−1
|
2.1X10
3
|
5.8X10
4
|
Ac−227 (a)
|
|
9.0X10
−1
|
2.4X10
1
|
9.0X10
−5
|
2.4X10
−3
|
2.7
|
7.2X10
1
|
Ac−228
|
|
6.0X10
−1
|
1.6X10
1
|
5.0X10
−1
|
1.4X10
1
|
8.4X10
4
|
2.2X10
6
|
Ag−105
|
Silver (47)
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
1.1X10
3
|
3.0X10
4
|
Ag−108m (a)
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
9.7X10
−1
|
2.6X10
1
|
Ag−110m (a)
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.8X10
2
|
4.7X10
3
|
Ag−111
|
|
2.0
|
5.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
5.8X10
3
|
1.6X10
5
|
Al−26
|
Aluminum (13)
|
1.0X10
−1
|
2.7
|
1.0X10
−1
|
2.7
|
7.0X10
−4
|
1.9X10
−2
|
Am−241
|
Americium (95)
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
1.3X10
−1
|
3.4
|
Am−242m (a)
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
3.6X10
−1
|
1.0X10
1
|
Am−243 (a)
|
|
5.0
|
1.4X10
2
|
1.0X10
−3
|
2.7X10
−2
|
7.4X10
−3
|
2.0X10
−1
|
Ar−37
|
Argon (18)
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
3.7X10
3
|
9.9X10
4
|
Ar−39
|
|
4.0X10
1
|
1.1X10
3
|
2.0X10
1
|
5.4X10
2
|
1.3
|
3.4X10
1
|
Ar−41
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
1.5X10
6
|
4.2X10
7
|
As−72
|
Arsenic (33)
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
6.2X10
4
|
1.7X10
6
|
As−73
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
8.2X10
2
|
2.2X10
4
|
As−74
|
|
1.0
|
2.7X10
1
|
9.0X10
−1
|
2.4X10
1
|
3.7X10
3
|
9.9X10
4
|
As−76
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
5.8X10
4
|
1.6X10
6
|
As−77
|
|
2.0X10
1
|
5.4X10
2
|
7.0X10
−1
|
1.9X10
1
|
3.9X10
4
|
1.0X10
6
|
At−211 (a)
|
Astatine (85)
|
2.0X10
1
|
5.4X10
2
|
5.0X10
−1
|
1.4X10
1
|
7.6X10
4
|
2.1X10
6
|
Au−193
|
Gold (79)
|
7.0
|
1.9X10
2
|
2.0
|
5.4X10
1
|
3.4X10
4
|
9.2X10
5
|
Au−194
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
1.5X10
4
|
4.1X10
5
|
Au−195
|
|
1.0X10
1
|
2.7X10
2
|
6.0
|
1.6X10
2
|
1.4X10
2
|
3.7X10
3
|
Au−198
|
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
9.0X10
3
|
2.4X10
5
|
Au−199
|
|
1.0X10
1
|
2.7X10
2
|
6.0X10
−1
|
1.6X10
1
|
7.7X10
3
|
2.1X10
5
|
Ba−131 (a)
|
Barium (56)
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
3.1X10
3
|
8.4X10
4
|
Ba−133
|
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
9.4
|
2.6X10
2
|
Ba−133m
|
|
2.0X10
1
|
5.4X10
2
|
6.0X10
−1
|
1.6X10
1
|
2.2X10
4
|
6.1X10
5
|
Ba−140 (a)
|
|
5.0X10
−1
|
1.4X10
1
|
3.0X10
−1
|
8.1
|
2.7X10
3
|
7.3X10
4
|
Be−7
|
Beryllium (4)
|
2.0X10
1
|
5.4X10
2
|
2.0X10
1
|
5.4X10
2
|
1.3X10
4
|
3.5X10
5
|
Be−10
|
|
4.0X10
1
|
1.1X10
3
|
6.0X10
−1
|
1.6X10
1
|
8.3X10
−4
|
2.2X10
−2
|
Bi−205
|
Bismuth (83)
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
1.5X10
3
|
4.2X10
4
|
Bi−206
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
3.8X10
3
|
1.0X10
5
|
Bi−207
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
1.9
|
5.2X10
1
|
Bi−210
|
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
4.6X10
3
|
1.2X10
5
|
Bi−210m (a)
|
|
6.0X10
−1
|
1.6X10
1
|
2.0X10
−2
|
5.4X10
−1
|
2.1X10
−5
|
5.7X10
−4
|
Bi−212 (a)
|
|
7.0X10
−1
|
1.9X10
1
|
6.0X10
−1
|
1.6X10
1
|
5.4X10
5
|
1.5X10
7
|
Bk−247
|
Berkelium (97)
|
8.0
|
2.2X10
2
|
8.0X10
−4
|
2.2X10
−2
|
3.8X10
−2
|
1.0
|
Bk−249 (a)
|
|
4.0X10
1
|
1.1X10
3
|
3.0X10
−1
|
8.1
|
6.1X10
1
|
1.6X10
3
|
Br−76
|
Bromine (35)
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
9.4X10
4
|
2.5X10
6
|
Br−77
|
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
2.6X10
4
|
7.1X10
5
|
Br−82
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
4
|
1.1X10
6
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
C−11
|
Carbon (6)
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
3.1X10
7
|
8.4X10
8
|
C−14
|
|
4.0X10
1
|
1.1X10
3
|
3.0
|
8.1X10
1
|
1.6X10
−1
|
4.5
|
Ca−41
|
Calcium (20)
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
3.1X10
−3
|
8.5X10
−2
|
Ca−45
|
|
4.0X10
1
|
1.1X10
3
|
1.0
|
2.7X10
1
|
6.6X10
2
|
1.8X10
4
|
Ca−47 (a)
|
|
3.0
|
8.1X10
1
|
3.0X10
−1
|
8.1
|
2.3X10
4
|
6.1X10
5
|
Cd−109
|
Cadmium (48)
|
3.0X10
1
|
8.1X10
2
|
2.0
|
5.4X10
1
|
9.6X10
1
|
2.6X10
3
|
Cd−113m
|
|
4.0X10
1
|
1.1X10
3
|
5.0X10
−1
|
1.4X10
1
|
8.3
|
2.2X10
2
|
Cd−115 (a)
|
|
3.0
|
8.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.9X10
4
|
5.1X10
5
|
Cd−115m
|
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
9.4X10
2
|
2.5X10
4
|
Ce−139
|
Cerium (58)
|
7.0
|
1.9X10
2
|
2.0
|
5.4X10
1
|
2.5X10
2
|
6.8X10
3
|
Ce−141
|
|
2.0X10
1
|
5.4X10
2
|
6.0X10
−1
|
1.6X10
1
|
1.1X10
3
|
2.8X10
4
|
Ce−143
|
|
9.0X10
−1
|
2.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.5X10
4
|
6.6X10
5
|
Ce−144 (a)
|
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
1.2X10
2
|
3.2X10
3
|
Cf−248
|
Californium (98)
|
4.0X10
1
|
1.1X10
3
|
6.0X10
−3
|
1.6X10
−1
|
5.8X10
1
|
1.6X10
3
|
Cf−249
|
|
3.0
|
8.1X10
1
|
8.0X10
−4
|
2.2X10
−2
|
1.5X10
−1
|
4.1
|
Cf−250
|
|
2.0X10
1
|
5.4X10
2
|
2.0X10
−3
|
5.4X10
−2
|
4.0
|
1.1X10
2
|
Cf−251
|
|
7.0
|
1.9X10
2
|
7.0X10
−4
|
1.9X10
−2
|
5.9X10
−2
|
1.6
|
Cf−252
|
|
1
.0X10
−
1
|
2.7
|
3.0X10
−3
|
8.1X10
−2
|
2.0X10
1
|
5.4X10
2
|
Cf−253 (a)
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
−2
|
1.1
|
1.1X10
3
|
2.9X10
4
|
Cf−254
|
|
1.0X10
−3
|
2.7X10
−2
|
1.0X10
−3
|
2.7X10
−2
|
3.1X10
2
|
8.5X10
3
|
Cl−36
|
Chlorine (17)
|
1.0X10
1
|
2.7X10
2
|
6.0X10
−1
|
1.6X10
1
|
1.2X10
−3
|
3.3X10
−2
|
Cl−38
|
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
4.9X10
6
|
1.3X10
8
|
Cm−240
|
Curium (96)
|
4.0X10
1
|
1.1X10
3
|
2.0X10
−2
|
5.4X10
−1
|
7.5X10
2
|
2.0X10
4
|
Cm−241
|
|
2.0
|
5.4X10
1
|
1.0
|
2.7X10
1
|
6.1X10
2
|
1.7X10
4
|
Cm−242
|
|
4.0X10
1
|
1.1X10
3
|
1.0X10
−2
|
2.7X10
−1
|
1.2X10
2
|
3.3X10
3
|
Cm−243
|
|
9.0
|
2.4X10
2
|
1.0X10
−3
|
2.7X10
−2
|
1.9X10
−3
|
5.2X10
1
|
Cm−244
|
|
2.0X10
1
|
5.4X10
2
|
2.0X10
−3
|
5.4X10
−2
|
3.0
|
8.1X10
1
|
Cm−245
|
|
9.0
|
2.4X10
2
|
9.0X10
−4
|
2.4X10
−2
|
6.4X10
−3
|
1.7X10
−1
|
Cm−246
|
|
9.0
|
2.4X10
2
|
9.0X10
−4
|
2.4X10
−2
|
1.1X10
−2
|
3.1X10
−1
|
Cm−247 (a)
|
|
3.0
|
8.1X10
1
|
1.0X10
−3
|
2.7X10
−2
|
3.4X10
−6
|
9.3X10
−5
|
Cm−248
|
|
2.0X10
−2
|
5.4X10
−1
|
3.0X10
−4
|
8.1X10
−3
|
1.6X10
−4
|
4.2X10
−3
|
Co−55
|
Cobalt (27)
|
5.0X10
−1
|
1.4 X10
1
|
5.0X10
−1
|
1.4 X10
1
|
1.1X10
5
|
3.1X10
6
|
Co−56
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
1.1X10
3
|
3.0X10
4
|
Co−57
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
1
|
2.7X10
2
|
3.1X10
2
|
8.4X10
3
|
Co−58
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
1.2X10
3
|
3.2X10
4
|
Co−58m
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
2.2X10
5
|
5.9X10
6
|
Co−60
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
4.2X10
1
|
1.1X10
3
|
Cr−51
|
Chromium (24)
|
3.0x10
1
|
8.1X10
2
|
3.0x10
1
|
8.1X10
2
|
3.4X10
3
|
9.2X10
4
|
Cs−129
|
Cesium (55)
|
4.0
|
1.1X10
2
|
4.0
|
1.1X10
2
|
2.8X10
4
|
7.6X10
5
|
Cs−131
|
|
3.0X10
1
|
8.1X10
2
|
3.0X10
1
|
8.1X10
2
|
3.8X10
3
|
1.0X10
5
|
Cs−132
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
5.7X10
3
|
1.5X10
5
|
Cs−134
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
4.8X10
1
|
1.3X10
3
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Cs−134m
|
|
4.0X10
1
|
1.1X10
3
|
6.0X10
−1
|
1.6X10
1
|
3.0X10
5
|
8.0X10
6
|
Cs−135
|
|
4.0X10
1
|
1.1X10
3
|
1.0
|
2.7X10
1
|
4.3X10
−5
|
1.2X10
−3
|
Cs−136
|
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
2.7X10
3
|
7.3X10
4
|
Cs−137 (a)
|
|
2.0
|
5.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
3.2
|
8.7X10
1
|
Cu−64
|
Copper (29)
|
6.0
|
1.6X10
2
|
1.0
|
2.7X10
1
|
1.4X10
5
|
3.9X10
6
|
Cu−67
|
|
1.0X10
1
|
2.7X10
2
|
7.0X10
−1
|
1.9X10
1
|
2.8X10
4
|
7.6X10
5
|
Dy−159
|
Dysprosium (66)
|
2.0X10
1
|
5.4X10
2
|
2.0X10
1
|
5.4X10
2
|
2.1X10
2
|
5.7X10
3
|
Dy−165
|
|
9.0X10
−1
|
2.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
3.0X10
5
|
8.2X10
6
|
Dy−166 (a)
|
|
9.0X10
−1
|
2.4X10
1
|
3.0X10
−1
|
8.1
|
8.6X10
3
|
2.3X10
5
|
Er−169
|
Erbium (68)
|
4.0X10
1
|
1.1X10
3
|
1.0
|
2.7X10
1
|
3.1X10
3
|
8.3X10
4
|
Er−171
|
|
8.0X10
−1
|
2.2X10
1
|
5.0X10
−1
|
1.4X10
1
|
9.0X10
4
|
2.4X10
6
|
Eu−147
|
Europium (63)
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
1.4X10
3
|
3.7X10
4
|
Eu−148
|
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
6.0X10
2
|
1.6X10
4
|
Eu−149
|
|
2.0X10
1
|
5.4X10
2
|
2.0X10
1
|
5.4X10
2
|
3.5X10
2
|
9.4X10
3
|
Eu−150
(short lived)
|
|
2.0
|
5.4X10
1
|
7.0X10
−1
|
1.9X10
1
|
6.1X10
4
|
1.6X10
6
|
Eu−150
(long lived)
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
6.1X10
4
|
1.6X10
6
|
Eu−152
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
6.5
|
1.8X10
2
|
Eu−152m
|
|
8.0X10
−1
|
2.2X10
1
|
8.0X10
−1
|
2.2X10
1
|
8.2X10
4
|
2.2X10
6
|
Eu−154
|
|
9.0X10
−1
|
2.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
9.8
|
2.6X10
2
|
Eu−155
|
|
2.0X10
1
|
5.4X10
2
|
3.0
|
8.1X10
1
|
1.8X10
1
|
4.9X10
2
|
Eu−156
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
2.0X10
3
|
5.5X10
4
|
F−18
|
Fluorine (9)
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
3.5X10
6
|
9.5X10
7
|
Fe−52 (a)
|
Iron (26)
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
2.7X10
5
|
7.3X10
6
|
Fe−55
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
8.8X10
1
|
2.4X10
3
|
Fe−59
|
|
9.0X10
−1
|
2.4X10
1
|
9.0X10
−1
|
2.4X10
1
|
1.8X10
3
|
5.0X10
4
|
Fe−60 (a)
|
|
4.0X10
1
|
1.1X10
3
|
2.0X10
−1
|
5.4
|
7.4X10
−4
|
2.0X10
−2
|
Ga−67
|
Gallium (31)
|
7.0
|
1.9X10
2
|
3.0
|
8.1X10
1
|
2.2X10
4
|
6.0X10
5
|
Ga−68
|
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
1.5X10
6
|
4.1X10
7
|
Ga−72
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.1X10
5
|
3.1X10
6
|
Gd−146 (a)
|
Gadolinium (64)
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
6.9X10
2
|
1.9X10
4
|
Gd−148
|
|
2.0X10
1
|
5.4X10
2
|
2.0X10
−3
|
5.4X10
−2
|
1.2
|
3.2X10
1
|
Gd−153
|
|
1.0X10
1
|
2.7X10
2
|
9.0
|
2.4X10
2
|
1.3X10
2
|
3.5X10
3
|
Gd−159
|
|
3.0
|
8.1X10
1
|
6.0X10
−1
|
1.6X10
1
|
3.9X10
4
|
1.1X10
6
|
Ge−68 (a)
|
Germanium (32)
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
2.6X10
2
|
7.1X10
3
|
Ge−71
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
5.8X10
3
|
1.6X10
5
|
Ge−77
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
1.3X10
5
|
3.6X10
6
|
Hf−172 (a)
|
Hafnium (72)
|
6.0X10
−1
|
1.6X10
1
|
6.0X10
−1
|
1.6X10
1
|
4.1X10
1
|
1.1X10
3
|
Hf−175
|
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
3.9X10
2
|
1.1X10
4
|
Hf−181
|
|
2.0
|
5.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
6.3X10
2
|
1.7X10
4
|
Hf−182
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
8.1X10
−6
|
2.2X10
−4
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Hg−194 (a)
|
Mercury (80)
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
1.3X10
−1
|
3.5
|
Hg−195m (a)
|
|
3.0
|
8.1X10
1
|
7.0X10
−1
|
1.9X10
1
|
1.5X10
4
|
4.0X10
5
|
Hg−197
|
|
2.0X10
1
|
5.4X10
2
|
1.0X10
1
|
2.7X10
2
|
9.2X10
3
|
2.5X10
5
|
Hg−197m
|
|
1.0X10
1
|
2.7X10
2
|
4.0X10
−1
|
1.1X10
1
|
2.5X10
4
|
6.7X10
5
|
Hg−203
|
|
5.0
|
1.4X10
2
|
1.0
|
2.7X10
1
|
5.1X10
2
|
1.4X10
4
|
Ho−166
|
Holmium (67)
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
2.6X10
4
|
7.0X10
5
|
Ho−166m
|
|
6.0X10
−1
|
1.6X10
1
|
5.0X10
−1
|
1.4X10
1
|
6.6X10
−2
|
1.8
|
I−123
|
Iodine (53)
|
6.0
|
1.6X10
2
|
3.0
|
8.1X10
1
|
7.1X10
4
|
1.9X10
6
|
I−124
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
9.3X10
3
|
2.5X10
5
|
I−125
|
|
2.0X10
1
|
5.4X10
2
|
3.0
|
8.1X10
1
|
6.4X10
2
|
1.7X10
4
|
I−126
|
|
2.0
|
5.4X10
1
|
1.0
|
2.7X10
1
|
2.9X10
3
|
8.0X10
4
|
I−129
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
6.5X10
−6
|
1.8X10
−4
|
I−131
|
|
3.0
|
8.1X10
1
|
7.0X10
−1
|
1.9X10
1
|
4.6X10
3
|
1.2X10
5
|
I−132
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
3.8X10
5
|
1.0X10
7
|
I−133
|
|
7.0X10
−1
|
1.9X10
1
|
6.0X10
−1
|
1.6X10
1
|
4.2X10
4
|
1.1X10
6
|
I−134
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
9.9X10
5
|
2.7X10
7
|
I−135 (a)
|
|
6.0X10
−1
|
1.6X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.3X10
5
|
3.5X10
6
|
In−111
|
Indium (49)
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
1.5X10
4
|
4.2X10
5
|
In−113m
|
|
4.0
|
1.1X10
2
|
2.0
|
5.4X10
1
|
6.2X10
5
|
1.7X10
7
|
In−114m (a)
|
|
1.0X10
1
|
2.7X10
2
|
5.0X10
−1
|
1.4X10
1
|
8.6X10
2
|
2.3X10
4
|
In−115m
|
|
7.0
|
1.9X10
2
|
1.0
|
2.7X10
1
|
2.2X10
5
|
6.1X10
6
|
Ir−189 (a)
|
Iridium (77)
|
1.0X10
1
|
2.7X10
2
|
1.0X10
1
|
2.7X10
2
|
1.9X10
3
|
5.2X10
4
|
Ir−190
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
2.3X10
3
|
6.2X10
4
|
Ir−192
|
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
3.4X10
2
|
9.2X10
3
|
Ir−194
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
3.1X10
4
|
8.4X10
5
|
K−40
|
Potassium (19)
|
9.0X10
−1
|
2.4X10
1
|
9.0X10
−1
|
2.4X10
1
|
2.4X10
−7
|
6.4X10
−6
|
K−42
|
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
2.2X10
5
|
6.0X10
6
|
K−43
|
|
7.0X10
−1
|
1.9X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.2X10
5
|
3.3X10
6
|
Kr−81
|
Krypton (36)
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
7.8X10
−4
|
2.1X10
−2
|
Kr−85
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
1
|
2.7X10
2
|
1.5X10
1
|
3.9X10
2
|
Kr−85m
|
|
8.0
|
2.2X10
2
|
3.0
|
8.1X10
1
|
3.0X10
5
|
8.2X10
6
|
Kr−87
|
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
1.0X10
6
|
2.8X10
7
|
La−137
|
Lanthanum (57)
|
3.0X10
1
|
8.1X10
2
|
6.0
|
1.6X10
2
|
1.6X10
−3
|
4.4X10
−2
|
La−140
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
2.1X10
4
|
5.6X10
5
|
Lu−172
|
Lutetium (71)
|
6.0X10
−1
|
1.6X10
1
|
6.0X10
−1
|
1.6X10
1
|
4.2X10
3
|
1.1X10
5
|
Lu−173
|
|
8.0
|
2.2X10
2
|
8.0
|
2.2X10
2
|
5.6X10
1
|
1.5X10
3
|
Lu−174
|
|
9.0
|
2.4X10
2
|
9.0
|
2.4X10
2
|
2.3X10
1
|
6.2X10
2
|
Lu−174m
|
|
2.0X10
1
|
5.4X10
2
|
1.0X10
1
|
2.7X10
2
|
2.0X10
2
|
5.3X10
3
|
Lu−177
|
|
3.0X10
1
|
8.1X10
2
|
7.0X10
−1
|
1.9X10
1
|
4.1X10
3
|
1.1X10
5
|
Mg−28 (a)
|
Magnesium (12)
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
2.0X10
5
|
5.4X10
6
|
Mn−52
|
Manganese (25)
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
1.6X10
4
|
4.4X10
5
|
Mn−53
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
6.8X10
−5
|
1.8X10
−3
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Mn−54
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
2.9X10
2
|
7.7X10
3
|
Mn−56
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
8.0X10
5
|
2.2X10
7
|
Mo−93
|
Molybdenum (42)
|
4.0X10
1
|
1.1X10
3
|
2.0X10
1
|
5.4X10
2
|
4.1X10
−2
|
1.1
|
Mo−99 (a) (h
)
|
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.8X10
4
|
4.8X10
5
|
N−13
|
Nitrogen (7)
|
9.0X10
−1
|
2.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
5.4X10
7
|
1.5X10
9
|
Na−22
|
Sodium (11)
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
2.3X10
2
|
6.3X10
3
|
Na−24
|
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
3.2X10
5
|
8.7X10
6
|
Nb−93m
|
Niobium (41)
|
4.0X10
1
|
1.1X10
3
|
3.0X10
1
|
8.1X10
2
|
8.8
|
2.4X10
2
|
Nb−94
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
6.9X10
−3
|
1.9X10
−1
|
Nb−95
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
1.5X10
3
|
3.9X10
4
|
Nb−97
|
|
9.0X10
−1
|
2.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
9.9X10
5
|
2.7X10
7
|
Nd−147
|
Neodymium (60)
|
6.0
|
1.6X10
2
|
6.0X10
−1
|
1.6X10
1
|
3.0X10
3
|
8.1X10
4
|
Nd−149
|
|
6.0X10
−1
|
1.6X10
1
|
5.0X10
−1
|
1.4X10
1
|
4.5X10
5
|
1.2X10
7
|
Ni−59
|
Nickel (28)
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
3.0X10
−3
|
8.0X10
−2
|
Ni−63
|
|
4.0X10
1
|
1.1X10
3
|
3.0X10
1
|
8.1X10
2
|
2.1
|
5.7X10
1
|
Ni−65
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
7.1X10
5
|
1.9X10
7
|
Np−235
|
Neptunium (93)
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
5.2X10
1
|
1.4X10
3
|
Np−236
(short−lived)
|
|
2.0X10
1
|
5.4X10
2
|
2.0
|
5.4X10
1
|
4.7X10
−4
|
1.3X10
−2
|
Np−236
(long−lived)
|
|
9.0
|
2.4X10
2
|
2.0X10
−2
|
5.4X10
−1
|
4.7X10
−4
|
1.3X10
−2
|
Np−237
|
|
2.0X10
1
|
5.4X10
2
|
2.0X10
−3
|
5.4X10
−2
|
2.6X10
−5
|
7.1X10
−4
|
Np−239
|
|
7.0
|
1.9X10
2
|
4.0X10
−1
|
1.1X10
1
|
8.6X10
3
|
2.3X10
5
|
Os−185
|
Osmium (76)
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
2.8X10
2
|
7.5X10
3
|
Os−191
|
|
1.0X10
1
|
2.7X10
2
|
2.0
|
5.4X10
1
|
1.6X10
3
|
4.4X10
4
|
Os−191m
|
|
4.0X10
1
|
1.1X10
3
|
3.0X10
1
|
8.1X10
2
|
4.6X10
4
|
1.3X10
6
|
Os−193
|
|
2.0
|
5.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.0X10
4
|
5.3X10
5
|
Os−194 (a)
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
1.1X10
1
|
3.1X10
2
|
P−32
|
Phosphorus (15)
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
1.1X10
4
|
2.9X10
5
|
P−33
|
|
4.0X10
1
|
1.1X10
3
|
1.0
|
2.7X10
1
|
5.8X10
3
|
1.6X10
5
|
Pa−230 (a)
|
Protactinium (91)
|
2.0
|
5.4X10
1
|
7.0X10
−2
|
1.9
|
1.2X10
3
|
3.3X10
4
|
Pa−231
|
|
4.0
|
1.1X10
2
|
4.0X10
−4
|
1.1X10
−2
|
1.7X10
−3
|
4.7X10
−2
|
Pa−233
|
|
5.0
|
1.4X10
2
|
7.0X10
−1
|
1.9X10
1
|
7.7X10
2
|
2.1X10
4
|
Pb−201
|
Lead (82)
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
6.2X10
4
|
1.7X10
6
|
Pb−202
|
|
4.0X10
1
|
1.1X10
3
|
2.0X10
1
|
5.4X10
2
|
1.2X10
−4
|
3.4X10
−3
|
Pb−203
|
|
4.0
|
1.1X10
2
|
3.0
|
8.1X10
1
|
1.1X10
4
|
3.0X10
5
|
Pb−205
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
4.5X10
−6
|
1.2X10
−4
|
Pb−210 (a)
|
|
1.0
|
2.7X10
1
|
5.0X10
−2
|
1.4
|
2.8
|
7.6X10
1
|
Pb−212 (a)
|
|
7.0X10
−1
|
1.9X10
1
|
2.0X10
−1
|
5.4
|
5.1X10
4
|
1.4X10
6
|
Pd−103 (a)
|
Palladium (46)
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
2.8X10
3
|
7.5X10
4
|
Pd−107
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
1.9X10
−5
|
5.1X10
−4
|
Pd−109
|
|
2.0
|
5.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
7.9X10
4
|
2.1X10
6
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Pm−143
|
Promethium (61)
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
1.3X10
2
|
3.4X10
3
|
Pm−144
|
|
7.0X10
−1
|
1.9X10
1
|
7.0X10
−1
|
1.9X10
1
|
9.2X10
1
|
2.5X10
3
|
Pm−145
|
|
3.0X10
1
|
8.1X10
2
|
1.0X10
1
|
2.7X10
2
|
5.2
|
1.4X10
2
|
Pm−147
|
|
4.0X10
1
|
1.1X10
3
|
2.0
|
5.4X10
1
|
3.4X10
1
|
9.3X10
2
|
Pm−148m (a)
|
|
8.0X10
−1
|
2.2X10
1
|
7.0X10
−1
|
1.9X10
1
|
7.9X10
2
|
2.1X10
4
|
Pm−149
|
|
2.0
|
5.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.5X10
4
|
4.0X10
5
|
Pm−151
|
|
2.0
|
5.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.7X10
4
|
7.3X10
5
|
Po−210
|
Polonium (84)
|
4.0X10
1
|
1.1X10
3
|
2.0X10
−2
|
5.4X10
−1
|
1.7X10
2
|
4.5X10
3
|
Pr−142
|
Praseodymium
(59)
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
4.3X10
4
|
1.2X10
6
|
Pr−143
|
|
3.0
|
8.1X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.5X10
3
|
6.7X10
4
|
Pt−188 (a)
|
Platinum (78)
|
1.0
|
2.7X10
1
|
8.0X10
−1
|
2.2X10
1
|
2.5X10
3
|
6.8X10
4
|
Pt−191
|
|
4.0
|
1.1X10
2
|
3.0
|
8.1X10
1
|
8.7X10
3
|
2.4X10
5
|
Pt−193
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
1.4
|
3.7X10
1
|
Pt−193m
|
|
4.0X10
1
|
1.1X10
3
|
5.0X10
−1
|
1.4X10
1
|
5.8X10
3
|
1.6X10
5
|
Pt−195m
|
|
1.0X10
1
|
2.7X10
2
|
5.0X10
−1
|
1.4X10
1
|
6.2X10
3
|
1.7X10
5
|
Pt−197
|
|
2.0X10
1
|
5.4X10
2
|
6.0X10
−1
|
1.6X10
1
|
3.2X10
4
|
8.7X10
5
|
Pt−197m
|
|
1.0X10
1
|
2.7X10
2
|
6.0X10
−1
|
1.6X10
1
|
3.7X10
5
|
1.0X10
7
|
Pu−236
|
Plutonium (94)
|
3.0X10
1
|
8.1X10
2
|
3.0X10
−3
|
8.1X10
−2
|
2.0X10
1
|
5.3X10
2
|
Pu−237
|
|
2.0X10
1
|
5.4X10
2
|
2.0X10
1
|
5.4X10
2
|
4.5X10
2
|
1.2X10
4
|
Pu−238
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
6.3X10
−1
|
1.7X10
1
|
Pu−239
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
2.3X10
−3
|
6.2X10
−2
|
Pu−240
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
8.4X10
−3
|
2.3X10
−1
|
Pu−241 (a)
|
|
4.0X10
1
|
1.1X10
3
|
6.0X10
−2
|
1.6
|
3.8
|
1.0X10
2
|
Pu−242
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
1.5X10
−4
|
3.9X10
−3
|
Pu−244 (a)
|
|
4.0X10
−1
|
1.1X10
1
|
1.0X10
−3
|
2.7X10
−2
|
6.7X10
−7
|
1.8X10
−5
|
Ra−223 (a)
|
Radium (88)
|
4.0X10
−1
|
1.1X10
1
|
7.0X10
−3
|
1.9X10
−1
|
1.9X10
3
|
5.1X10
4
|
Ra−224 (a)
|
|
4.0X10
−1
|
1.1X10
1
|
2.0X10
−2
|
5.4X10
−1
|
5.9X10
3
|
1.6X10
5
|
Ra−225 (a)
|
|
2.0X10
−1
|
5.4
|
4.0X10
−3
|
1.1X10
−1
|
1.5X10
3
|
3.9X10
4
|
Ra−226 (a)
|
|
2.0X10
−1
|
5.4
|
3.0X10
−3
|
8.1X10
−2
|
3.7X10
−2
|
1.0
|
Ra−228 (a)
|
|
6.0X10
−1
|
1.6X10
1
|
2.0X10
−2
|
5.4X10
−1
|
1.0X10
1
|
2.7X10
2
|
Rb−81
|
Rubidium (37)
|
2.0
|
5.4X10
1
|
8.0X10
−1
|
2.2X10
1
|
3.1X10
5
|
8.4X10
6
|
Rb−83 (a)
|
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
6.8X10
2
|
1.8X10
4
|
Rb−84
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
1.8X10
3
|
4.7X10
4
|
Rb−86
|
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
3.0X10
3
|
8.1X10
4
|
Rb−87
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
3.2X10
−9
|
8.6X10
−8
|
Rb
(
nat
)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
6.7X10
6
|
1.8X10
8
|
Re−184
|
Rhenium (75)
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
6.9X10
2
|
1.9X10
4
|
Re−184m
|
|
3.0
|
8.1X10
1
|
1.0
|
2.7X10
1
|
1.6X10
2
|
4.3X10
3
|
Re−186
|
|
2.0
|
5.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
6.9X10
3
|
1.9X10
5
|
Re−187
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
1.4X10
−9
|
3.8X10
−8
|
Re−188
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
3.6X10
4
|
9.8X10
5
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Re−189 (a)
|
|
3.0
|
8.1X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.5X10
4
|
6.8X10
5
|
Re(
nat
)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
0.0
|
2.4X10
−8
|
Rh−99
|
Rhodium (45)
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
3.0X10
3
|
8.2X10
4
|
Rh−101
|
|
4.0
|
1.1X10
2
|
3.0
|
8.1X10
1
|
4.1X10
1
|
1.1X10
3
|
Rh−102
|
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
4.5X10
1
|
1.2X10
3
|
Rh−102m
|
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
2.3X10
2
|
6.2X10
3
|
Rh−103m
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
1.2X10
6
|
3.3X10
7
|
Rh−105
|
|
1.0X10
1
|
2.7X10
2
|
8.0X10
−1
|
2.2X10
1
|
3.1X10
4
|
8.4X10
5
|
Rn−222 (a)
|
Radon (86)
|
3.0X10
−1
|
8.1
|
4.0X10
−3
|
1.1X10
−1
|
5.7X10
3
|
1.5X10
5
|
Ru−97
|
Ruthenium (44)
|
5.0
|
1.4X10
2
|
5.0
|
1.4X10
2
|
1.7X10
4
|
4.6X10
5
|
Ru−103 (a)
|
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
1.2X10
3
|
3.2X10
4
|
Ru−105
|
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.5X10
5
|
6.7X10
6
|
Ru−106 (a)
|
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
1.2X10
2
|
3.3X10
3
|
S−35
|
Sulphur
(16)
|
4.0X10
1
|
1.1X10
3
|
3.0
|
8.1X10
1
|
1.6X10
3
|
4.3X10
4
|
Sb−122
|
Antimony (51)
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.5X10
4
|
4.0X10
5
|
Sb−124
|
|
6.0X10
−1
|
1.6X10
1
|
6.0X10
−1
|
1.6X10
1
|
6.5X10
2
|
1.7X10
4
|
Sb−125
|
|
2.0
|
5.4X10
1
|
1.0
|
2.7X10
1
|
3.9X10
1
|
1.0X10
3
|
Sb−126
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
3.1X10
3
|
8.4X10
4
|
Sc−44
|
Scandium (21)
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
6.7X10
5
|
1.8X10
7
|
Sc−46
|
|
5.0X10
−1
|
1.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
1.3X10
3
|
3.4X10
4
|
Sc−47
|
|
1.0X10
1
|
2.7X10
2
|
7.0X10
−1
|
1.9X10
1
|
3.1X10
4
|
8.3X10
5
|
Sc−48
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
5.5X10
4
|
1.5X10
6
|
Se−75
|
Selenium (34)
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
5.4X10
2
|
1.5X10
4
|
Se−79
|
|
4.0X10
1
|
1.1X10
3
|
2.0
|
5.4X10
1
|
2.6X10
−3
|
7.0X10
−2
|
Si−31
|
Silicon (14)
|
6.0X10
−1
|
1.6X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.4X10
6
|
3.9X10
7
|
Si−32
|
|
4.0X10
1
|
1.1X10
3
|
5.0X10
−1
|
1.4X10
1
|
3.9
|
1.1X10
2
|
Sm−145
|
Samarium (62)
|
1.0X10
1
|
2.7X10
2
|
1.0X10
1
|
2.7X10
2
|
9.8X10
1
|
2.6X10
3
|
Sm−147
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
8.5X10
−1
|
2.3X10
−8
|
Sm−151
|
|
4.0X10
1
|
1.1X10
3
|
1.0X10
1
|
2.7X10
2
|
9.7X10
−1
|
2.6X10
1
|
Sm−153
|
|
9.0
|
2.4X10
2
|
6.0X10
−1
|
1.6X10
1
|
1.6X10
4
|
4.4X10
5
|
Sn−113 (a)
|
Tin (50)
|
4.0
|
1.1X10
2
|
2.0
|
5.4X10
1
|
3.7X10
2
|
1.0X10
4
|
Sn−117m
|
|
7.0
|
1.9X10
2
|
4.0X10
−1
|
1.1X10
1
|
3.0X10
3
|
8.2X10
4
|
Sn−119m
|
|
4.0X10
1
|
1.1X10
3
|
3.0X10
1
|
8.1X10
2
|
1.4X10
2
|
3.7X10
3
|
Sn−121m (a)
|
|
4.0X10
1
|
1.1X10
3
|
9.0X10
−1
|
2.4X10
1
|
2.0
|
5.4X10
1
|
Sn−123
|
|
8.0X10
−1
|
2.2X10
1
|
6.0X10
−1
|
1.6X10
1
|
3.0X10
2
|
8.2X10
3
|
Sn−125
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
3
|
1.1X10
5
|
Sn−126 (a)
|
|
6.0X10
−1
|
1.6X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.0X10
−3
|
2.8X10
−2
|
Sr−82 (a)
|
Strontium (38)
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
2.3X10
3
|
6.2X10
4
|
Sr−85
|
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
8.8X10
2
|
2.4X10
4
|
Sr−85m
|
|
5.0
|
1.4X10
2
|
5.0
|
1.4X10
2
|
1.2X10
6
|
3.3X10
7
|
Sr−87m
|
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
4.8X10
5
|
1.3X10
7
|
Sr−89
|
|
6.0X10
−1
|
1.6X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.1X10
3
|
2.9X10
4
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Sr−90 (a)
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
5.1
|
1.4X10
2
|
Sr−91 (a)
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
1.3X10
5
|
3.6X10
6
|
Sr−92 (a)
|
|
1.0
|
2.7X10
1
|
3.0X10
−1
|
8.1
|
4.7X10
5
|
1.3X10
7
|
T(H−3)
|
Tritium (1)
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
3.6X10
2
|
9.7X10
3
|
Ta−178
(long−lived)
|
Tantalum (73)
|
1.0
|
2.7X10
1
|
8.0X10
−1
|
2.2X10
1
|
4.2X10
6
|
1.1X10
8
|
Ta−179
|
|
3.0X10
1
|
8.1X10
2
|
3.0X10
1
|
8.1X10
2
|
4.1X10
1
|
1.1X10
3
|
Ta−182
|
|
9.0X10
−1
|
2.4X10
1
|
5.0X10
−1
|
1.4X10
1
|
2.3X10
2
|
6.2X10
3
|
Tb−157
|
Terbium (65)
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
5.6X10
−1
|
1.5X10
1
|
Tb−158
|
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
5.6X10
−1
|
1.5X10
1
|
Tb−160
|
|
1.0
|
2.7X10
1
|
6.0X10
−1
|
1.6X10
1
|
4.2X10
2
|
1.1X10
4
|
Tc−95m (a)
|
Technetium (43)
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
8.3X10
2
|
2.2X10
4
|
Tc−96
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.2X10
4
|
3.2X10
5
|
Tc−96m (a)
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.4X10
6
|
3.8X10
7
|
Tc−97
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
5.2X10
−5
|
1.4X10
−3
|
Tc−97m
|
|
4.0X10
1
|
1.1X10
3
|
1.0
|
2.7X10
1
|
5.6X10
2
|
1.5X10
4
|
Tc−98
|
|
8.0X10
−1
|
2.2X10
1
|
7.0X10
−1
|
1.9X10
1
|
3.2X10
−5
|
8.7X10
−4
|
Tc−99
|
|
4.0X10
1
|
1.1X10
3
|
9.0X10
−1
|
2.4X10
1
|
6.3X10
−4
|
1.7X10
−2
|
Tc−99m
|
|
1.0X10
1
|
2.7X10
2
|
4.0
|
1.1X10
2
|
1.9X10
5
|
5.3X10
6
|
Te−121
|
Tellurium (52)
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
2.4X10
3
|
6.4X10
4
|
Te−121m
|
|
5.0
|
1.4X10
2
|
3.0
|
8.1X10
1
|
2.6X10
2
|
7.0X10
3
|
Te−123m
|
|
8.0
|
2.2X10
2
|
1.0
|
2.7X10
1
|
3.3X10
2
|
8.9X10
3
|
Te−125m
|
|
2.0X10
1
|
5.4X10
2
|
9.0X10
−1
|
2.4X10
1
|
6.7X10
2
|
1.8X10
4
|
Te−127
|
|
2.0X10
1
|
5.4X10
2
|
7.0X10
−1
|
1.9X10
1
|
9.8X10
4
|
2.6X10
6
|
Te−127m (a)
|
|
2.0X10
1
|
5.4X10
2
|
5.0X10
−1
|
1.4X10
1
|
3.5X10
2
|
9.4X10
3
|
Te−129
|
|
7.0X10
−1
|
1.9X10
1
|
6.0X10
−1
|
1.6X10
1
|
7.7X10
5
|
2.1X10
7
|
Te−129m (a)
|
|
8.0X10
−1
|
2.2X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.1X10
3
|
3.0X10
4
|
Te−131m (a)
|
|
7.0X10
−1
|
1.9X10
1
|
5.0X10
−1
|
1.4X10
1
|
3.0X10
4
|
8.0X10
5
|
Te−132 (a)
|
|
5.0X10
−1
|
1.4X10
1
|
4.0X10
−1
|
1.1X10
1
|
1.1X10
4
|
3.0X10
5
|
Th−227
|
Thorium (90)
|
1.0X10
1
|
2.7X10
2
|
5.0X10
−3
|
1.4X10
−1
|
1.1X10
3
|
3.1X10
4
|
Th−228 (a)
|
|
5.0X10
−1
|
1.4X10
1
|
1.0X10
−3
|
2.7X10
−2
|
3.0X10
1
|
8.2X10
2
|
Th−229
|
|
5.0
|
1.4X10
2
|
5.0X10
−4
|
1.4X10
−2
|
7.9X10
−3
|
2.1X10
−1
|
Th−230
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
7.6X10
−4
|
2.1X10
−2
|
Th−231
|
|
4.0X10
1
|
1.1X10
3
|
2.0X10
−2
|
5.4X10
−1
|
2.0X10
4
|
5.3X10
5
|
Th−232
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
4.0X10
−9
|
1.1X10
−7
|
Th−234 (a)
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
8.6X10
2
|
2.3X10
4
|
Th
(
nat
)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
8.1X10
−9
|
2.2X10
−7
|
Ti−44 (a)
|
Titanium (22)
|
5.0X10
−1
|
1.4X10
1
|
4.0X10
−1
|
1.1X10
1
|
6.4
|
1.7X10
2
|
Tl−200
|
Thallium (81)
|
9.0X10
−1
|
2.4X10
1
|
9.0X10
−1
|
2.4X10
1
|
2.2X10
4
|
6.0X10
5
|
Tl−201
|
|
1.0X10
1
|
2.7X10
2
|
4.0
|
1.1X10
2
|
7.9X10
3
|
2.1X10
5
|
Tl−202
|
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
2.0X10
3
|
5.3X10
4
|
Tl−204
|
|
1.0X10
1
|
2.7X10
2
|
7.0X10
−1
|
1.9X10
1
|
1.7X10
1
|
4.6X10
2
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
Tm−167
|
Thulium (69)
|
7.0
|
1.9X10
2
|
8.0X10
−1
|
2.2X10
1
|
3.1X10
3
|
8.5X10
4
|
Tm−170
|
|
3.0
|
8.1X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.2X10
2
|
6.0X10
3
|
Tm−171
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
U−230 (fast lung absorption) (a)(d)
|
Uranium (92)
|
4.0X10
1
|
1.1X10
3
|
1.0X10
−1
|
2.7
|
1.0X10
3
|
2.7X10
4
|
U−230 (medium lung absorption) (a)(e)
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
−3
|
1.1X10
−1
|
1.0X10
3
|
2.7X10
4
|
U−230 (slow lung absorption) (a)(f)
|
|
3.0X10
1
|
8.1X10
2
|
3.0X10
−3
|
8.1X10
−2
|
1.0X10
3
|
2.7X10
4
|
U−232 (fast lung absorption) (d)
|
|
4.0X10
1
|
1.1X10
3
|
1.0X10
−2
|
2.7X10
−1
|
8.3X10
−1
|
2.2X10
1
|
U−232 (medium lung absorption) (e)
|
|
4.0X10
1
|
1.1X10
3
|
7.0X10
−3
|
1.9X10
−1
|
8.3X10
−1
|
2.2X10
1
|
U−232 (slow lung absorption) (f)
|
|
1.0X10
1
|
2.7X10
2
|
1.0X10
−3
|
2.7X10
−2
|
8.3X10
−1
|
2.2X10
1
|
U−233 (fast lung absorption) (d)
|
|
4.0X10
1
|
1.1X10
3
|
9.0X10
−2
|
2.4
|
3.6X10
−4
|
9.7X10
−3
|
U−233 (medium lung absorption) (e)
|
|
4.0X10
1
|
1.1X10
3
|
2.0X10
−2
|
5.4X10
−1
|
3.6X10
−4
|
9.7X10
−3
|
U−233 (slow lung absorption) (f)
|
|
4.0X10
1
|
1.1X10
3
|
6.0X10
−3
|
1.6X10
−1
|
3.6X10
−4
|
9.7X10
−3
|
U−234 (fast lung absorption) (d)
|
|
4.0X10
1
|
1.1X10
3
|
9.0X10
−2
|
2.4
|
2.3X10
−4
|
6.2X10
−3
|
U−234 (medium lung absorption) (e)
|
|
4.0X10
1
|
1.1X10
3
|
2.0X10
−2
|
5.4X10
−1
|
2.3X10
−4
|
6.2X10
−3
|
U−234 (slow lung absorption) (f)
|
|
4.0X10
1
|
1.1X10
3
|
6.0X10
−3
|
1.6X10
−1
|
2.3X10
−4
|
6.2X10
−3
|
U−235 (all lung absorption types) (a),(d),(e),(f)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
8.0X10
−8
|
2.2X10
−6
|
U−236 (fast lung absorption) (d)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
2.4X10
−6
|
6.5X10
−5
|
U−236 (medium lung absorption) (e)
|
|
4.0X10
1
|
1.1X10
3
|
2.0X10
−2
|
5.4X10
−1
|
2.4X10
−6
|
6.5X10
−5
|
TABLE VI
A
1
AND A
2
VALUES FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
A1
(
TBq
)
|
A1
(Ci)
|
A2
(
TBq
)
|
A2
(Ci)
|
Specific Activity
(
TBq
/g)
(Ci/g)
|
U−236 (slow lung absorption) (f)
|
|
4.0X10
1
|
1.1X10
3
|
6.0X10
−3
|
1.6X10
−1
|
2.4X10
−6
|
6.5X10
−5
|
U−238 (all lung absorption types) (d),(e),(f)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
1.2X10
−8
|
3.4X10
−7
|
U (
nat
)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
2.6X10
−8
|
7.1X10
−7
|
U (enriched to 20% or less)(g)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
N/A
|
N/A
|
U (
dep
)
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
0.0
|
(See Table IX)
|
V−48
|
Vanadium (23)
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
6.3X10
3
|
1.7X10
5
|
V−49
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
3.0X10
2
|
8.1X10
3
|
W−178 (a)
|
Tungsten (74)
|
9.0
|
2.4X10
2
|
5.0
|
1.4X10
2
|
1.3X10
3
|
3.4X10
4
|
W−181
|
|
3.0X10
1
|
8.1X10
2
|
3.0X10
1
|
8.1X10
2
|
2.2X10
2
|
6.0X10
3
|
W−185
|
|
4.0X10
1
|
1.1X10
3
|
8.0X10
−1
|
2.2X10
1
|
3.5X10
2
|
9.4X10
3
|
W−187
|
|
2.0
|
5.4X10
1
|
6.0X10
−1
|
1.6X10
1
|
2.6X10
4
|
7.0X10
5
|
W−188 (a)
|
|
4.0X10
−1
|
1.1X10
1
|
3.0X10
−1
|
8.1
|
3.7X10
2
|
1.0X10
4
|
Xe−122 (a)
|
Xenon (54)
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
4.8X10
4
|
1.3X10
6
|
Xe−123
|
|
2.0
|
5.4X10
1
|
7.0X10
−1
|
1.9X10
1
|
4.4X10
5
|
1.2X10
7
|
Xe−127
|
|
4.0
|
1.1X10
2
|
2.0
|
5.4X10
1
|
1.0X10
3
|
2.8X10
4
|
Xe−131m
|
|
4.0X10
1
|
1.1X10
3
|
4.0X10
1
|
1.1X10
3
|
3.1X10
3
|
8.4X10
4
|
Xe−133
|
|
2.0X10
1
|
5.4X10
2
|
1.0X10
1
|
2.7X10
2
|
6.9X10
3
|
1.9X10
5
|
Xe−135
|
|
3.0
|
8.1X10
1
|
2.0
|
5.4X10
1
|
9.5X10
4
|
2.6X10
6
|
Y−87 (a)
|
Yttrium (39)
|
1.0
|
2.7X10
1
|
1.0
|
2.7X10
1
|
1.7X10
4
|
4.5X10
5
|
Y−88
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
5.2X10
2
|
1.4X10
4
|
Y−90
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
2.0X10
4
|
5.4X10
5
|
Y−91
|
|
6.0X10
−1
|
1.6X10
1
|
6.0X10
−1
|
1.6X10
1
|
9.1X10
2
|
2.5X10
4
|
Y−91m
|
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
1.5X10
6
|
4.2X10
7
|
Y−92
|
|
2.0X10
−1
|
5.4
|
2.0X10
−1
|
5.4
|
3.6X10
5
|
9.6X10
6
|
Y−93
|
|
3.0X10
−1
|
8.1
|
3.0X10
−1
|
8.1
|
1.2X10
5
|
3.3X10
6
|
Yb−169
|
Ytterbium (79)
|
4.0
|
1.1X10
2
|
1.0
|
2.7X10
1
|
8.9X10
2
|
2.4X10
4
|
Yb−175
|
|
3.0X10
1
|
8.1X10
2
|
9.0X10
−1
|
2.4X10
1
|
6.6X10
3
|
1.8X10
5
|
Zn−65
|
Zinc (30)
|
2.0
|
5.4X10
1
|
2.0
|
5.4X10
1
|
3.0X10
2
|
8.2X10
3
|
Zn−69
|
|
3.0
|
8.1X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.8X10
6
|
4.9X10
7
|
Zn−69m (a)
|
|
3.0
|
8.1X10
1
|
6.0X10
−1
|
1.6X10
1
|
1.2X10
5
|
3.3X10
6
|
Zr−88
|
Zirconium (40)
|
3.0
|
8.1X10
1
|
3.0
|
8.1X10
1
|
6.6X10
2
|
1.8X10
4
|
Zr−93
|
|
Unlimited
|
Unlimited
|
Unlimited
|
Unlimited
|
9.3X10
−5
|
2.5X10
−3
|
Zr−95 (a)
|
|
2.0
|
5.4X10
1
|
8.0X10
−1
|
2.2X10
1
|
7.9X10
2
|
2.1X10
4
|
Zr−97 (a)
|
|
4.0X10
−1
|
1.1X10
1
|
4.0X10
−1
|
1.1X10
1
|
7.1X10
4
|
1.9X10
6
|
NOTES
(a) A
1
and/or A
2
values include contributions from daughter nuclides with half−lives less than 10 days
, as listed in the following:
Pb-212
|
Bi-212, Tl-208, Po-212
|
Rn-222
|
Po-218, Pb-214, At-218, Bi-214, Po-214
|
Ra-223
|
Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207
|
Ra-224
|
Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212
|
Ra-225
|
Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209
|
Ra-226
|
Rn-222, Po-218, Pb-214, At-218, Bi-214, Po-214
|
Ac-225
|
Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209
|
Th-228
|
Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212
|
Pa-230
|
Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214
|
U-230
|
Th-226, Ra-222, Rn-218, Po-214
|
(b) The values of A
1
and A
2
in curies (Ci) are approximate and for information only; the regulatory standard units are
Terabecquerels
(
TBq
).
(c)
The activity of Ir-192 in special form may
be determined from a measurement of the rate of decay or a measurement of the radiation level at a prescribed distance from the source.
(d) These values apply only to compounds of uranium that take the chemical form of UF
6
, UO
2
F
2
and
UO
2
(
NO
3
)
2
in both normal and accident conditions of transport.
(e) These values apply only to compounds of uranium that take the chemical form of UO
3
, UF
4
, UCl
4
, and hexavalent compounds in both normal and accident conditions of transport.
(f) These values apply to all compounds of uranium other than those specified in (d) and (e), above.
(g) These values apply to unirradiated uranium only.
(h
) A
2
= 0.74
TBq
(20 Ci) for Mo−99 for domestic use.
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Ac−225
|
Actinium (89)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Ac−227
|
|
1.0X10
−1
|
2.7X10
−12
|
1.0X10
3
|
2.7X10
−8
|
Ac−228
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Ag−105
|
Silver (47)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Ag−108m (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Ag−110m
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Ag−111
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Al−26
|
Aluminum (13)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Am−241
|
Americium (95)
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Am−242m (a)
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Am−243 (a)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Ar−37
|
Argon (18)
|
1.0X10
6
|
2.7X10
−5
|
1.0X10
8
|
2.7X10
−3
|
Ar−39
|
|
1.0X10
7
|
2.7X10
−4
|
1.0X10
4
|
2.7X10
−7
|
Ar−41
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
9
|
2.7X10
−2
|
As−72
|
Arsenic (33)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
As−73
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
As−74
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
As−76
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
As−77
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
At−211
|
Astatine (85)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Au−193
|
Gold (79)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Au−194
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Au−195
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Au−198
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Au−199
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Be−7
|
Beryllium (4)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Be−10
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
6
|
2.7X10
−5
|
Bi−205
|
Bismuth (83)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Bi−206
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Bi−207
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Bi−210
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Bi−210m
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Bi−212 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Ba−131
|
Barium (56)
|
1.0X10
2
|
2.7X10
−9
|
1.0X106
|
2.7X10
−5
|
Ba−133
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X106
|
2.7X10
−5
|
Ba−133m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X106
|
2.7X10
−5
|
Ba−140 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Bk−247
|
Berkelium (97)
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Bk−249
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Br−76
|
Bromine (35)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Br−77
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Br−82
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
C−11
|
Carbon (6)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
C−14
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Ca−41
|
Calcium (20)
|
1.0X10
5
|
2.7X10
−6
|
1.0X10
7
|
2.7X10
−4
|
Ca−45
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Ca−47
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Cd−109
|
Cadmium (48)
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
6
|
2.7X10
−5
|
Cd−113m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Cd−115
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Cd−115m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Ce−139
|
Cerium (58)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Ce−141
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Ce−143
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Ce−144 (a)
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Cf−248
|
Californium (98)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Cf−249
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Cf−250
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Cf−251
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Cf−252
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Cf−253
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Cf−254
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Cl−36
|
Chlorine (17)
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
6
|
2.7X10
−5
|
Cl−38
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Cm−240
|
Curium (96)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Cm−241
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Cm−242
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Cm−243
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Cm−244
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Cm−245
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Cm−246
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Cm−247
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Cm−248
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Co−55
|
Cobalt (27)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Co−56
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Co−57
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Co−58
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Co−58m
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Co−60
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Cr−51
|
Chromium (24)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Cs−129
|
Cesium (55)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Cs−131
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Cs−132
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Cs−134
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Cs−134m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
5
|
2.7X10
−6
|
Cs−135
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Cs−136
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Cs−137 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Cu−64
|
Copper (29)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Cu−67
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Dy−159
|
Dysprosium (66)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Dy−165
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Dy−166
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Er−169
|
Erbium (68)
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Er−171
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Eu−147
|
Europium (63)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Eu−148
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Eu−149
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Eu−150
(short lived)
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Eu−150
(long lived)
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Eu−152
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Eu−152 m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Eu−154
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Eu−155
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Eu−156
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
F−18
|
Fluorine (9)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Fe−52
|
Iron (26)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Fe−55
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
6
|
2.7X10
−5
|
Fe−59
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Fe−60
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Ga−67
|
Gallium (31)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Ga−68
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Ga−72
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Gd−146
|
Gadolinium (64)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Gd−148
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Gd−153
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Gd−159
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Ge−68
|
Germanium (32)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Ge−71
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
8
|
2.7X10
−3
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Ge−77
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Hf−172
|
Hafnium (72)
|
1.0X10
2
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Hf−175
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Hf−181
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Hf−182
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Hg−194
|
Mercury (80)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Hg−195m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Hg−197
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Hg−197m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Hg−203
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Ho−166
|
Holmium (67)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
5
|
2.7X10
−6
|
Ho−166m
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
I−123
|
Iodine (53)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
I−124
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
I−125
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
I−126
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
I−129
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
I−131
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
I−132
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
I−133
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
I−134
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
I−135
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
In−111
|
Indium (49)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
In−113m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
In−114m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
In−115m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Ir−189
|
Iridium (77)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Ir−190
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Ir−192
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Ir−194
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
K−40
|
Potassium (19)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
K−42
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
K−43
|
|
1.0X10
2
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Kr−79
|
Krypton (36)
|
1.0X10
3
|
2.7X10
−
8
|
1.0X10
5
|
2.7X10
−
6
|
Kr−81
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Kr−85
|
|
1.0X10
5
|
2.7X10
−6
|
1.0X10
4
|
2.7X10
−7
|
Kr−85m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
10
|
2.7X10
−1
|
Kr−87
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
9
|
2.7X10
−2
|
La−137
|
Lanthanum (57)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
La−140
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Lu−172
|
Lutetium (71)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Lu−173
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Lu−174
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Lu−174m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Lu−177
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Mg−28
|
Magnesium (12)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Mn−52
|
Manganese (25)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Mn−53
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
9
|
2.7X10
−2
|
Mn−54
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Mn−56
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Mo−93
|
Molybdenum (42)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
8
|
2.7X10
−3
|
Mo−99
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
N−13
|
Nitrogen (7)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
9
|
2.7X10
−2
|
Na−22
|
Sodium (11)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Na−24
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Nb−93m
|
Niobium (41)
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Nb−94
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Nb−95
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Nb−97
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Nd−147
|
Neodymium (60)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Nd−149
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Ni−59
|
Nickel (28)
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
8
|
2.7X10
−3
|
Ni−63
|
|
1.0X10
5
|
2.7X10
−6
|
1.0X10
8
|
2.7X10
−3
|
Ni−65
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Np−235
|
Neptunium (93)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Np−236 (short−lived)
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Np−236
(long−lived)
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Np−237
(a)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Np−239
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Os−185
|
Osmium (76)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Os−191
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Os−191m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Os−193
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Os−194
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
P−32
|
Phosphorus (15)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
5
|
2.7X10
−6
|
P−33
|
|
1.0X10
5
|
2.7X10
−6
|
1.0X10
8
|
2.7X10
−3
|
Pa−230
|
Protactinium (91)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Pa−231
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Pa−233
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Pb−201
|
Lead (82)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Pb−202
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Pb−203
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Pb−205
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Pb−210 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Pb−212 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Pd−103
|
Palladium (46)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
8
|
2.7X10
−3
|
Pd−107
|
|
1.0X10
5
|
2.7X10
−6
|
1.0X10
8
|
2.7X10
−3
|
Pd−109
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Pm−143
|
Promethium (61)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Pm−144
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Pm−145
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Pm−147
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Pm−148m
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Pm−149
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Pm−151
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Po−210
|
Polonium (84)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Pr−142
|
Praseodymium (59)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Pr−143
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
6
|
2.7X10
−5
|
Pt−188
|
Platinum (78)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Pt−191
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Pt−193
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Pt−193m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Pt−195m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Pt−197
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Pt−197m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Pu−236
|
Plutonium (94)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Pu−237
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Pu−238
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Pu−239
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Pu−240
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Pu−241
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Pu−242
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Pu−244
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Ra−223 (a)
|
Radium (88)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Ra−224 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Ra−225
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Ra−226 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Ra−228 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Rb−81
|
Rubidium (37)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Rb−83
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Rb−84
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Rb−86
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Rb−87
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Rb
(
nat
)
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Re−184
|
Rhenium (75)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Re−184m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Re−186
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Re−187
|
|
1.0X10
6
|
2.7X10
−5
|
1.0X10
9
|
2.7X10
−2
|
Re−188
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Re−189
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Re(
nat
)
|
|
1.0X10
6
|
2.7X10
−5
|
1.0X10
9
|
2.7X10
−2
|
Rh−99
|
Rhodium (45)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Rh−101
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Rh−102
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Rh−102m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Rh−103m
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
8
|
2.7X10
−3
|
Rh−105
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Rn−222 (a)
|
Radon (86)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
8
|
2.7X10
−3
|
Ru−97
|
Ruthenium (44)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Ru−103
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Ru−105
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Ru−106 (a)
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
S−35
|
Sulphur
(16)
|
1.0X10
5
|
2.7X10
−6
|
1.0X10
8
|
2.7X10
−3
|
Sb−122
|
Antimony (51)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
4
|
2.7X10
−7
|
Sb−124
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Sb−125
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Sb−126
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Sc−44
|
Scandium (21)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Sc−46
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Sc−47
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Sc−48
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Se−75
|
Selenium (34)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Se−79
|
|
1.0X10
4
|
2.7X10
−10
|
1.0X10
7
|
2.7X10
−4
|
Si−31
|
Silicon (14)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Si−32
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Sm−145
|
Samarium (62)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Sm−147
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Sm−151
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
8
|
2.7X10
−3
|
Sm−153
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Sn−113
|
Tin (50)
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Sn−117m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Sn−119m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Sn−121m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Sn−123
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Sn−125
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Sn−126
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Sr−82
|
Strontium (38)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Sr−85
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Sr−85m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Sr−87m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Sr−89
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Sr−90 (a)
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
4
|
2.7X10
−7
|
Sr−91
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Sr−92
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
T(H−3)
|
Tritium (1)
|
1.0X10
6
|
2.7X10
−5
|
1.0X10
9
|
2.7X10
−2
|
Ta−178
(long−lived)
|
Tantalum (73)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Ta−179
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Ta−182
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Tb−157
|
Terbium (65)
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Tb−158
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Tb−160
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Tc−9
5m
|
Technetium (43)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Tc−96
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Tc−96m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Tc−97
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
8
|
2.7X10
−3
|
Tc−97m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Tc−98
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Tc−99
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
Tc−99m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Te−121
|
Tellurium (52)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Te−121m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−
5
|
Te−123m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Te−125m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Te−127
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Te−127m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Te−129
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Te−129m
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Te−131m
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Te−132
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Th−227
|
Thorium (90)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Th−228 (a)
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Th−229
(a)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Th−230
|
|
1.0
|
2.7X10
−11
|
1.0X10
4
|
2.7X10
−7
|
Th−231
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Th−232
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
Th−234 (a)
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
5
|
2.7X10
−6
|
Th
(
nat
)
(a)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
Ti−44
|
Titanium (22)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
Tl−200
|
Thallium (81)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Tl−201
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Tl−202
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Tl−204
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
4
|
2.7X10
−7
|
Tm−167
|
Thulium (69)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Tm−170
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Tm−171
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
8
|
2.7X10
−3
|
U−
230 (fast lung absorption) (a), (b
)
|
Uranium (92)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
U−230 (medium lung absorptio
n) (c
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
U−
230 (slow lung absorption) (d
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
U−232 (fast lung absorption) (a), (b
)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
U−232 (medium lung absorption)
(c
)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
U−232 (slow lung absorption)
(d
)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
U−233 (fast lung absorption) (b
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−
233 (medium lung absorption) (c
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−233 (slow lung absorption) (d
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
U−234 (fast lung absorption) (b
)
|
Uranium (92)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−
234 (medium lung absorption) (c
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−234 (slow lung absorption) (d
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−235 (a
ll lung absorption types) (a),(b),(c),(d
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−236 (fast lung absorption) (b
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−2
36 (medium lung absorption) (c
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−236 (slow lung absorption) (d
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U−23
8 (all lung absorption types) (a), (b),(c),(d
)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
4
|
2.7X10
−7
|
U (
nat
)
(a)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
U (enriched to 20% or less)(e
)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
U (
dep
)
|
|
1.0
|
2.7X10
−11
|
1.0X10
3
|
2.7X10
−8
|
V−48
|
Vanadium (23)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
V−49
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
W−178
|
Tungsten (74)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
W−181
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
W−185
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
7
|
2.7X10
−4
|
W−187
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
W−188
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Xe−122
|
Xenon (54)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
9
|
2.7X10
−2
|
Xe−123
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
9
|
2.7X10
−2
|
Xe−127
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
5
|
2.7X10
−6
|
Xe−131m
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
4
|
2.7X10
−7
|
Xe−133
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
4
|
2.7X10
−7
|
Xe−135
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
10
|
2.7X10
−1
|
Y−87
|
Yttrium (39)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Y−88
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Y−90
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
5
|
2.7X10
−6
|
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
|
Element and Atomic No.
|
Activity concentration for exempt material (
Bq
/g)
|
Activity concentration for exempt material (Ci/g)
|
Activity limit for exempt consignment (
Bq
)
|
Activity limit for exempt consignment (Ci)
|
Y−91
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
6
|
2.7X10
−5
|
Y−91m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Y−92
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Y−93
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
5
|
2.7X10
−6
|
Yb−169
|
Ytterbium (79)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
7
|
2.7X10
−4
|
Yb−175
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Zn−65
|
Zinc (30)
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Zn−69
|
|
1.0X10
4
|
2.7X10
−7
|
1.0X10
6
|
2.7X10
−5
|
Zn−69m
|
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Zr−88
|
Zirconium (40)
|
1.0X10
2
|
2.7X10
−9
|
1.0X10
6
|
2.7X10
−5
|
Zr−93
(a)
|
|
1.0X10
3
|
2.7X10
−8
|
1.0X10
7
|
2.7X10
−4
|
Zr−95
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
6
|
2.7X10
−5
|
Zr−97 (a)
|
|
1.0X10
1
|
2.7X10
−10
|
1.0X10
5
|
2.7X10
−6
|
NOTES
(a
) Parent nuclides and their progeny included in secular equilibrium are listed in the following:
Bi-212
|
Tl-208 (0.36), Po-212 (0.64)
|
Pb-212
|
Bi-212, Tl-208 (0.36), Po-212 (0.64)
|
Rn-222
|
Po-218, Pb-214, Bi-214, Po-214
|
Ra-223
|
Rn-219, Po-215, Pb-211, Bi-211, Tl-207
|
Ra-224
|
Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
|
Ra-226
|
Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210
|
Th-228
|
Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
|
Th-229
|
Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209
|
Th-nat
|
Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
|
U-230
|
Th-226, Ra-222, Rn-218, Po-214
|
U-232
|
Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
|
U-
nat
|
Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210
|
(b
) These values apply only to compounds of uranium that take the chemical form of UF
6
, UO
2
F
2
, and
UO
2
(
NO
3
)
2
in both normal and accident conditions of transport.
(c
) These values apply only to compounds of uranium that take the chemical form of UO3, UF4, UCl4, and hexavalent compounds in both normal and accident conditions of transport.
(d
) These values apply to all compounds of uranium other than those specified in (d) and (e), above.
(e
) These values apply to unirradiated uranium only.
TABLE VIII
GENERAL VALUES FOR A
1
AND A
2
Contents
|
Only beta or gamma emitting radionuclides are known to be present
|
Alpha emitting nuclides, but no neutron emitters, are known to be present. (a)
|
Neutron emitting nuclides are known to be present or no relevant data are available
|
A
1
|
(
TBq
)
|
1 x 10
−1
|
2 x 10
−1
|
1 x 10
−3
|
|
|
(Ci)
|
2.7 x 10
0
|
5.4 x 10
0
|
2.7 x 10
−
|
A
2
|
(
TBq
)
|
2 x 10
−2
|
9 x 10
−5
|
9 x 10
−5
|
|
|
(Ci)
|
5.4 x 10
−1
|
2.4 x 10
−3
|
2.4 x 10
−3
|
Activity concentration for exempt material
(
Bq
/g)
|
1 x 10
1
|
1 x 10
−1
|
1 x 10
−1
|
Activity concentration for exempt material
(Ci/g)
|
2.7 x10
−10
|
2.7 x10
−12
|
2.7 x10
−12
|
Activity limits for exempt consignments
(
Bq
)
|
1 x 10
4
|
1 x 10
3
|
1 x 10
3
|
Activity limits for exempt consignments
(Ci)
|
2.7 x10
−7
|
2.7 x10
−
|
2.7 x10
−8
|
(a)
If beta or gamma emitting nuclides are known to be present, the A1 value of 0.1
TBq
(2.7 Ci) should be used.
TABLE IX
ACTIVITY−MASS RELATIONSHIPS FOR URANIUM
Uranium Enrichment*
wt
% U−235 present
|
Specific Activity
|
0.45
|
1.9 x 10
−8
|
5.0 x 10
−7
|
0.72
|
2.6 x 10
−8
|
7.1 x 10
−7
|
1 2.
|
8 x 10
−8
|
7.6 x 10
−7
|
1.5
|
3.7 x 10
−8
|
1.0 x 10
−6
|
5
|
1.0 x 10
−7
|
2.7 x 10
−6
|
10
|
1.8 x 10
−7
|
4.8 x 10
−6
|
20
|
3.7 x 10
−7
|
1.0 x 10
−5
|
35
|
7.4 x 10
−7
|
2.0 x 10
−5
|
50
|
9.3 x 10
−7
|
2.5 x 10
−5
|
90
|
2.1 x 10
−6
|
5.8 x 10
−5
|
93
|
2.6 x 10
−6
|
7.0 x 10
−5
|
95
|
3.4 x 10
−6
|
9.1 x 10
−5
|
Natural thorium
|
8.1 x 10
−9
|
2.2 x 10
−7
|
Note:
The figures for uranium include representative values for the activity of the uranium−234 that is concentrated
during
the enrichment process.
SECTION
104
.
DHS 157 Appendix
U
is
created
to read:
APPENDIX U
Category 1 and Category 2 Quantity of Radioactive Material Thresholds
The sum of fractions’ methodology for evaluating combinations of multiple sources
, aggregated sources,
or multiple radionuclides is to be used in determining whether a location meets or exceeds the threshold and is thus subject to the requirements of
subch
. XV.
Category 1
and category
2 quantities of radioactive material do not include the radioactive material contained in any fuel assembly, subassembly, fuel rod, or fuel pellet.
The
terabecquerel
(
TBq
) values are the regulatory standard. The curie (Ci) values specified are obtained by converting from the
TBq
value. The curie values are provided for practical usefulness only.
Radioactive material
|
Category 1
(
TBq
)
|
Category 1
(Ci)
|
Category 2
(
TBq
)
|
Category 2
(Ci)
|
Americium-241......................................................................................
Americium-241/Be.................................................................................
Californium-252.....................................................................................
Cobalt-60...............................................................................................
Curium-244............................................................................................
Cesium-137...........................................................................................
Gadolinium-153.....................................................................................
Iridium-192............................................................................................
Plutonium-238.......................................................................................
Plutonium-239/Be..................................................................................
Promethium-147....................................................................................
Radium-226...........................................................................................
Selenium-75..........................................................................................
Strontium-90..........................................................................................
Thulium-170..........................................................................................
Ytterbium-169........................................................................................
|
60
60
20
30
50
100
1,000
80
60
60
40,000
40
200
1,000
20,000
300
|
1,620
1,620
540
810
1,350
2,700
27,000
2,160
1,620
1,620
1,080,000
1,080
5,400
27,000
540,000
8,100
|
0.6
0.6
0.2
0.3
0.5
1
10
0.8
0.6
0.6
400
0.4
2
10
200
3
|
16.2
16.2
5.40
8.10
13.5
27.0
270
21.6
16.2
16.2
10,800
10.8
54.0
270
5,400
81.0
|
Note:
Calculations Concerning Multiple Sources or Multiple Radionuclides
I. If multiple sources of the same radionuclide
or
multiple radionuclides are aggregated at a location, the sum of the ratios of the total activity of each of the radionuclides shall be determined to verify whether the activity at the location is less than the category 1 or category 2 thresholds
of
Appendix U, as appropriate. If the calculated sum of the ratios, using the equation below, is greater than or equal to 1.0, then the applicable requirements of
subch
. XV apply.
II. First determine the total activity for each radionuclide from Appendix U. This is done by adding the activity of each individual source, material in any device, and any loose or bulk material that contains the radionuclide. Then use the equation below to calculate the sum of the ratios by inserting the total activity of the applicable radionuclides from
Appendix U
in the numerator of the equation and the corresponding threshold activity from Table 1 in the denominator of the equation. Calculations shall be performed in metric values (i.e.,
TBq
) and the numerator and denominator values shall be in the same units.
R
1
= total activity for radionuclide 1
R
2
= total activity for radionuclide 2
R
N
= total activity for radionuclide n
AR
1
= activity threshold for radionuclide 1
AR
2
= activity threshold for radionuclide 2
AR
N
= activity threshold for radionuclide n
SECTION
106.
EFFECTIVE DATE: This rule shall take effect on the first day of the month following publication in the Wisconsin administrative register, as provided in s.
227.22 (2)
, Stats
.
.
