TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.101 AUTHORITY
Section 1000.101 Authority
The Board adopts the rules
contained in this title under the authority of Title VI-A of the Environmental
Protection Act. [415 ILCS 5/25b]
(Source:
Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
 | TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.102 PURPOSE
Section 1000.102 Purpose
a) This Part establishes standards for protection against
radiological air pollutants associated with materials and activities under
licenses issued by the United States Nuclear Regulatory Commission (NRC) under
the Atomic Energy Act of 1954 (42 U.S.C. 5801 et seq.), and the Energy
Reorganization Act of 1974 (42 U.S.C. 5801 et seq.)
b) In addition to complying with the other applicable
requirements of this Part, persons subject to this Part must make every
reasonable effort to maintain radiation exposures in, and releases of radioactive
materials to, unrestricted areas as low as is reasonably achievable. The term
"as low as is reasonably achievable" means as low as is reasonably
achievable considering the state of technology, the economics of improvements
in relation to benefits to the public health and safety, and other societal and
socioeconomic considerations, in relation to the utilization of atomic energy
in the public interest.
c) Persons licensed by the NRC to operate light-water-cooled
nuclear power reactors will satisfy subsection (b) if they achieve the design
objectives and limiting conditions for operation specified in 10 CFR 50,
Appendix I, incorporated by reference in Section 1000.202.
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.103 SCOPE
Section 1000.103 Scope
This Part applies to all persons
who receive, possess, use, or transfer material licensed under 10 CFR 30
through 35, 40, or 70, incorporated by reference in Section 1000.202, or who
are licensed to operate a production or utilization facility under 10 CFR 50,
incorporated by reference in Section 1000.202.
(Source:
Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
SUBPART B: DEFINITIONS
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.201 DEFINITIONS
Section 1000.201 Definitions
Except as stated in this
Section, or unless a different meaning of a word or term is clear from the
context, the definition of words or terms in this Part are the same as that
applied to the same words or terms in the Environmental Protection Act [415
ILCS 5]:
"Act"
means the Environmental Protection Act [415 ILCS 5].
"Board"
means the Illinois Pollution Control Board.
"Dose"
means the quantity of radiation absorbed, per unit of mass, by the body or by
any portion of the body. Under this Part, a dose during a period of time means
the total quantity of radiation absorbed, per unit of mass, by the body or by
any portion of the body during such period of time. The units of dose used in this
Part are "Rad" and "Rem", as defined in this Section.
"IEMA"
means the Illinois Emergency Management Agency, Division of Nuclear Safety.
"Individual"
means any human being.
"Licensed
activity" means any activity engaged in under a general or specific
license issued by the NRC.
"Licensed
facility" means any facility constructed or operated under a permit or a
general or specific license issued by the NRC.
"Licensed
material" means any material received, possessed, used, or transferred
under a general or specific license issued by the NRC.
"Licensee"
means any person to whom a permit or a general or specific license has been
issued by the NRC.
"NRC"
means the United States Nuclear Regulatory Commission.
"Rad"
means a measure of the dose of any radiation to body tissues in terms of the
energy absorbed per unit mass of the tissue. One rad is the dose corresponding
to the absorption of 100 ergs per gram of tissue. (One millirad (mrad) = 0.001
rad).
"Radiation"
means any or all of the following: alpha rays, beta rays, gamma rays, X-rays,
neutrons, high-speed electrons, high-speed protons, and other atomic particles;
but not sound or radio waves, or visible, infrared, or ultraviolet light.
"Radioactive
material" and "radioactive emissions" mean any dusts,
particulates, fumes, mists, vapors, or gases which spontaneously emit ionizing
radiation.
"Rem"
means a measure of the dose of any ionizing radiation to body tissue in terms
of its estimated biological effect relative to a dose received from an exposure
to one roentgen of X-rays. (One millirem (mrem) = 0.001 rem). The relation of
rem to other dose units depends on the biological effect under consideration
and the condition of irradiation. For this Part, any of the following is
considered to be equivalent to a dose of one rem:
An exposure to one roentgen of X- or gamma radiation;
A dose of one rad due to X-, gamma, or beta radiation;
A dose of 0.1 rad due to neutrons or high energy protons;
A dose of 0.05
rad due to particles heavier than protons and with sufficient energy to reach
the lens of the eye. If it is more convenient to measure the neutron flux, or
equivalent, than to determine the neutron dose in rads, one rem of neutron
radiation may be assumed to be equivalent to 14 million neutrons per square
centimeter incident upon the body; or, if information is available to estimate
with reasonable accuracy the approximate distribution in the energy of
neutrons, the incident number of neutrons per square centimeter equivalent to
one rem may be estimated from the following table.
|
Neutron
Flux Dose Equivalents
|
|
Neutron
Energy (Mev)
|
No.
of Neutron per square centimeter equivalent to a dose of 1 rem (neutrons/cm2)
|
Average
flux to deliver 100 millirem in 40 hours (neutron/cm2 per second)
|
|
Thermal..........................
|
970 x 106
|
670
|
|
|
0.0001.............................
|
720 x 106
|
500
|
|
|
0.005...............................
|
820 x 106
|
570
|
|
|
0.02.................................
|
400 x 106
|
280
|
|
|
0.1...................................
|
120 x 106
|
80
|
|
|
0.5...................................
|
43 x 106
|
30
|
|
|
1.0...................................
|
26 x 106
|
18
|
|
|
2.5...................................
|
29 x 106
|
20
|
|
|
5.0...................................
|
26 x 106
|
18
|
|
|
7.5...................................
|
24 x 106
|
17
|
|
|
10.0.................................
|
24 x 106
|
17
|
|
|
10 to 30...........................
|
14 x 106
|
10
|
|
|
|
|
|
|
|
"Restricted
area" means any area to which access is controlled by the licensee to
protect individuals from exposure to radiation and radioactive materials.
"Restricted area" must not include any areas used as residential
quarters, although a separate room or rooms in a residential building may be
set apart as a restricted area.
"Unrestricted
area" means any area to which access is not controlled by the licensee to
protect individuals from exposure to radiation and radioactive materials, and
any area used for residential quarters.
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.202 INCORPORATIONS BY REFERENCE
Section 1000.202 Incorporations by Reference
The following materials are incorporated by reference. These
incorporations by reference do not include any later amendments or editions:
a) Numerical
Guides for Design Objectives and Limiting Conditions for Operations to Meet the
Criterion "As Low as is Reasonably Achievable" for Radioactive
Material in Light-Water-Cooled Nuclear Power Reactor Effluents, 10 CFR 50,
Appendix I (1984).
b) Rules
of General Applicability to Domestic Licensing of Byproduct Material, 10 CFR 30
(1984).
c) General
Domestic Licenses for Byproduct Material, 10 CFR 31 (1984).
d) Specific
Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct
Material, 10 CFR 32 (1984).
e) Specific
Domestic Licenses of Broad Scope for Byproduct Material, 10 CFR 33 (1984).
f) Licenses
for Industrial Radiography and Radiation Safety Requirements for Industrial
Radiographic Operations, 10 CFR 34 (1984).
g) Medical
Use of Byproduct Material, 10 CFR 35 (1984).
h) Domestic
Licensing of Source Material, 10 CFR 40 (1984).
i) Domestic
Licensing of Production and Utilization Facilities, 10 CFR 50 (1984).
j) Environmental
Protection Regulations for Domestic Licensing and Related Regulatory Functions,
10 CFR 51 (1984).
k) Domestic
Licensing of Special Nuclear Material, 10 CFR 70 (1984).
(Source: Added
at 47 Ill. Reg. 6679, effective May 4, 2023)
SUBPART C: STANDARDS AND LIMITATIONS
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.301 PERMISSIBLE LEVELS OF RADIATION IN UNRESTRICTED AREAS
Section 1000.301 Permissible
Levels of Radiation in Unrestricted Areas
A person must not possess, use,
receive, or transfer licensed material or engage in licensed activities in a
way that creates radiation levels in the air in any unrestricted area:
a) That could result in a dose to the whole body greater than 0.5
rem in any single year, when all radioactive emissions by the licensee are considered;
b) That could result in an individual continuously present in the
area receiving a dose greater than 2 millirems in any single hour, when all
radioactive emissions by the licensee are considered; or
c) That could result in an individual continuously present in the
area receiving a dose greater than 100 millirems in any 7 consecutive days,
when all radioactive emissions by the licensee are considered.
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.302 RADIOACTIVE EMISSIONS TO UNRESTRICTED AREAS
Section 1000.302 Radioactive
Emissions to Unrestricted Areas
a) A person must not possess, use, receive, or transfer licensed
material or engage in licensed activities in a way that releases to the air in
an unrestricted area radioactive material exceeding the concentration limits
specified in Appendix A. For this Section, concentrations of radioactive
material may be averaged over a period not greater than one year.
b) For this Section, the concentration limits in Appendix A apply
at the boundary of the restricted area. The concentration of radioactive
material discharged through a stack, pipe or similar conduit may be determined for
the point where the material leaves the conduit. If the conduit discharges
within the restricted area, the concentration at the boundary may be determined
by applying established factors for dilution, dispersion, or decay between the
point of discharge and the boundary.
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
SUBPART D: ADDITIONAL REQUIREMENTS
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.401 APPLICABILITY
Section 1000.401
Applicability
This Subpart applies to
radiation doses received by members of the public in the general environment
and to radioactive materials introduced into the general environment due to
operations that are part of a nuclear fuel cycle.
(Source:
Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.402 DEFINITIONS
Section 1000.402 Definitions
As used in this Subpart:
"Curie"
(Ci) means the quantity of radioactive material that produces 37 billion
nuclear transformations per second. (One millicurie (mCi) = 0.001 Ci.)
"Dose
equivalent" means the product of absorbed dose and appropriate factors to
account for differences in biological effectiveness due to the quality of
radiation and its spatial distribution in the body. The unit of dose
equivalent is the "rem." (One millirem (mrem) = 0.001 rem.)
"General
environment" means the total terrestrial, atmospheric, and aquatic
environments outside sites upon which any operation that is part of a nuclear
fuel cycle is conducted.
"Gigawatt-year"
refers to the quantity of electrical energy produced at the busbar of a
generating station. A gigawatt is equal to one billion watts. A gigawatt-year
is equivalent to the amount of energy output represented by an average electric
power level of one gigawatt sustained for one year.
"Member
of the public" means any individual who can receive a radiation dose in
the general environment, whether or not the individual is also exposed to
radiation in an occupation associated with a nuclear fuel cycle. However, an
individual is not considered a member of the public during any period in which that
individual is engaged in carrying out any operation that is part of a nuclear
fuel cycle.
"Nuclear
fuel cycle" means the operations defined to be associated with the
production of electrical power for public use by any fuel cycle through
utilization of nuclear energy.
"Organ"
means any human organ exclusive of the dermis, the epidermis, or the cornea.
"Site"
means the area contained within the boundary of a location under the control of
persons possessing or using radioactive material on which one or more
operations covered by this Part is conducted.
"Uranium
fuel cycle" means the operations of milling of uranium ore, chemical
conversion of uranium, isotopic enrichment of uranium, fabrication of uranium
fuel, generation of electricity by a light-water-cooled nuclear power plant
using uranium fuel, and reprocessing of spent uranium fuel, to the extent that
these directly support the production of electrical power for public use
utilizing nuclear energy. "Uranium fuel cycle" excludes mining
operations, operations at waste disposal sites, transportation of any
radioactive material in support of these operations, and the reuse of recovered
non-uranium special nuclear and byproduct materials from the cycle.
(Source:
Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.403 ENVIRONMENTAL STANDARDS FOR URANIUM FUEL CYCLE
Section 1000.403
Environmental Standards for Uranium Fuel Cycle
A person conducting operations
covered by this Subpart must conduct them in a way that provides reasonable
assurance that:
a) The annual dose equivalent does not exceed 25 millirems to the
whole body, 75 millirems to the thyroid, and 25 millirems to any other organ of
any member of the public as the result of exposures to planned discharges of
radioactive materials, radon and its daughters excepted, to the general
environment from uranium fuel cycle operations, and to radiation from these
operations.
b) The total quantity of radioactive materials entering the
general environment from the entire uranium fuel cycle, per gigawatt-year of
electrical energy produced by the fuel cycle, contains less than 50,000 curies
of krypton-85, 5 millicuries of iodine-129, and 0.5 millicuries combined of
plutonium-239 and other alpha-emitting transuranic radionuclides with the half-lives
greater than one year.
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
SUBPART E: RECORDS
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.501 RECORDS
Section 1000.501 Records
A person subject to this Part must
submit to IEMA, for any material or facility permitted or licensed by the NRC
or for which an NRC permit or license is sought:
a) Preliminary Safety Analysis Report and Final Safety Analysis
Report, as described in 10 CFR 50.34, incorporated by reference in Section
1000.202.
b) Application for Construction Permit and for all amendments to
that permit, including information required by 10 CFR 50.34a, 50.36, and 51.20,
incorporated by reference in Section 1000.202.
c) Environmental Impact Appraisal, Draft and Final Environmental
Impact Statement, Negative Declaration, or other document prepared by the NRC
under 10 CFR 51, incorporated by reference in Section 1000.202.
d) Operating Permit and all amendments to that permit, including
Technical Specifications under 10 CFR 50.36a, incorporated by reference in
Section 1000.202.
e) Application for Amendment to Operating License.
f) All data, records, and reports conducted by or for that person
and submitted to the NRC for determining or predicting radiation levels in the air
in unrestricted areas or the type or amount of radioactive materials emitted
into the air.
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.502 NOTIFICATION OF INCIDENTS
Section 1000.502
Notification of Incidents
A person subject to this Part must
immediately notify IEMA by telephone of any incident or condition arising from
the use or possession of licensed materials or facilities or the conducting of
licensed activities which may have caused or threatens to cause emissions or
radiation levels exceeding those allowed under this Part. IEMA’s 24-hour
Operations Center can be reached for notification of incidents at
1-217-782-7860.
(Source:
Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.503 OTHER PROVISIONS
Section 1000.503 Other
Provisions
a) The definitions specified in 35 Ill. Adm. Code 201.102 apply
to this Part.
b) All persons subject to this Part are subject to the
requirements and provisions of 35 Ill. Adm. Code 201.122, 201.123, 201.125,
201.126, 201.141, 201.150 and 201.151.
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
Section 1000.APPENDIX A Concentrations in Air Above Natural Background
| TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
CHAPTER I: POLLUTION CONTROL BOARD
PART 1000
RADIATION HAZARDS
SECTION 1000.APPENDIX A CONCENTRATIONS IN AIR ABOVE NATURAL BACKGROUND
Section 1000.APPENDIX A Concentrations
in Air Above Natural Background
|
Element (atomic number)
|
Isotope1
|
|
µCi/ml
|
|
Actinium (89)
|
AC 227
|
S
|
8 x 10-14
|
|
|
|
I
|
9 x 10-13
|
|
|
AC 228
|
S
|
3 x 10-9
|
|
|
|
I
|
6 x 10-10
|
|
Americium (95)
|
Am 241
|
S
|
2 x 10-13
|
|
|
|
I
|
4 x 10-12
|
|
|
Am 242m
|
S
|
2 x 10-13
|
|
|
|
I
|
9 x 10-12
|
|
|
Am 242
|
S
|
1 x 10-9
|
|
|
|
I
|
2 x 10-9
|
|
|
Am 243
|
S
|
2 x 10-13
|
|
|
|
I
|
4 x 10-12
|
|
|
Am 244
|
S
|
1 x 10-7
|
|
|
|
I
|
8 x 10-7
|
|
Antimony
|
Sb 122
|
S
|
6 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
|
Sb 124
|
S
|
5 x 10-9
|
|
|
|
I
|
7 x 10-10
|
|
|
Sb 125
|
S
|
2 x 10-8
|
|
|
|
I
|
9 x 10-10
|
|
Argon (18)
|
A 37
|
Sub2
|
1 x 10-4
|
|
|
A 41
|
Sub
|
4 x 10-8
|
|
Arsenic (33)
|
As 73
|
S
|
7 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
As 74
|
S
|
1 x 10-8
|
|
|
|
I
|
4 x 10-9
|
|
|
As 76
|
S
|
4 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
|
As 77
|
S
|
2 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
Astatine (85)
|
At 211
|
S
|
2 x 10-10
|
|
|
|
I
|
1 x 10-9
|
|
Barium (56)
|
Ba 131
|
S
|
4 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
Ba 140
|
S
|
4 x 10-9
|
|
|
|
I
|
1 x 10-9
|
|
Berkelium (97)
|
Bk 249
|
S
|
3 x 10-11
|
|
|
|
I
|
4 x 10-9
|
|
|
Bk 250
|
S
|
5 x 10-9
|
|
|
|
I
|
4 x 10-8
|
|
Berylium (4)
|
Be 7
|
S
|
2 x 10-7
|
|
|
|
I
|
4 x 10-8
|
|
Bismuth (83)
|
Bi 206
|
S
|
6 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
|
Bi 207
|
S
|
6 x 10-9
|
|
|
|
I
|
5 x 10-10
|
|
|
Bi 210
|
S
|
2 x 10-10
|
|
|
|
I
|
2 x 10-10
|
|
|
Bi 212
|
S
|
3 x 10-9
|
|
|
|
I
|
7 x 10-9
|
|
Bromine (35)
|
Br 82
|
S
|
4 x 10-8
|
|
|
|
I
|
6 x 10-9
|
|
Cadmium (48)
|
Cd 109
|
S
|
2 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
|
Cd 115m
|
S
|
1 x 10-9
|
|
|
|
I
|
1 x 10-9
|
|
|
Cd 115
|
S
|
8 x 10-9
|
|
|
|
|
I
|
6 x 10-9
|
|
Calcium (20)
|
Ca 45
|
S
|
1 x 10-9
|
|
|
|
|
I
|
4 x 10-9
|
|
|
Ca 47
|
S
|
6 x 10-9
|
|
|
|
|
I
|
6 x 10-9
|
|
Californium (98)
|
Cf 249
|
S
|
5 x 10-14
|
|
|
|
|
I
|
3 x 10-12
|
|
|
Cf 250
|
S
|
2 x 10-13
|
|
|
|
I
|
3 x 10-12
|
|
|
Cf 251
|
S
|
6 x 10-14
|
|
|
|
I
|
3 x 10-12
|
|
|
Cf 252
|
S
|
2 x 10-13
|
|
|
|
I
|
1 x 10-12
|
|
|
Cf 253
|
S
|
3 x 10-11
|
|
|
|
I
|
3 x 10-11
|
|
|
Cf 254
|
S
|
2 x 10-13
|
|
|
|
I
|
2 x 10-13
|
|
Carbon (6)
|
C 14
|
S
|
1 x 10-7
|
|
|
(CO2)
|
Sub
|
1 x 10-6
|
|
Cerium (58)
|
Ce 141
|
S
|
2 x 10-8
|
|
|
|
I
|
5 x 10-9
|
|
|
Ce 143
|
S
|
9 x 10-9
|
|
|
|
I
|
7 x 10-9
|
|
|
Ce 144
|
S
|
3 x 10-10
|
|
|
|
I
|
2 x 10-10
|
|
Cesium (55)
|
Cs 131
|
S
|
4 x 10-7
|
|
|
|
I
|
1 x 10-7
|
|
|
Cs 134m
|
S
|
1 x 10-6
|
|
|
|
I
|
2 x 10-7
|
|
|
Cs 134
|
S
|
1 x 10-9
|
|
|
|
I
|
4 x 10-10
|
|
|
Cs 135
|
S
|
2 x 10-8
|
|
|
|
I
|
3 x 10-9
|
|
|
Cs 136
|
S
|
1 x 10-8
|
|
|
|
I
|
6 x 10-9
|
|
|
Cs 137
|
S
|
2 x 10-9
|
|
|
|
I
|
5 x 10-10
|
|
Chlorine (17)
|
Cl 36
|
S
|
1 x 10-8
|
|
|
|
I
|
8 x 10-10
|
|
|
Cl 38
|
S
|
9 x 10-8
|
|
|
|
I
|
7 x 10-8
|
|
Chromium (24)
|
Cr 51
|
S
|
4 x 10-7
|
|
|
|
I
|
8 x 10-8
|
|
Cobalt (27)
|
Co 57
|
S
|
1 x 10-7
|
|
|
|
I
|
6 x 10-9
|
|
|
Co 58m
|
S
|
6 x 10-7
|
|
|
|
I
|
3 x 10-7
|
|
|
Co 58
|
S
|
3 x 10-8
|
|
|
|
I
|
2 x 10-9
|
|
|
Co 60
|
S
|
1 x 10-8
|
|
|
|
I
|
3 x 10-10
|
|
Copper (29)
|
Cu 64
|
S
|
7 x 10-8
|
|
|
|
I
|
4 x 10-8
|
|
Curium (96)
|
Cm 242
|
S
|
4 x 10-12
|
|
|
|
I
|
6 x 10-12
|
|
|
Cm 243
|
S
|
2 x 10-13
|
|
|
|
I
|
3 x 10-12
|
|
|
Cm 244
|
S
|
3 x 10-13
|
|
|
|
I
|
3 x 10-12
|
|
|
Cm 245
|
S
|
2 x 10-13
|
|
|
|
I
|
4 x 10-12
|
|
|
Cm 246
|
S
|
2 x 10-13
|
|
|
|
I
|
4 x 10-12
|
|
|
Cm 247
|
S
|
2 x 10-13
|
|
|
|
I
|
4 x 10-12
|
|
|
Cm 248
|
S
|
2 x 10-14
|
|
|
|
I
|
4 x 10-13
|
|
|
Cm 249
|
S
|
4 x 10-7
|
|
|
|
I
|
4 x 10-7
|
|
Dysprosium (66)
|
Dy 165
|
S
|
9 x 10-8
|
|
|
|
I
|
7 x 10-8
|
|
|
Dy 166
|
S
|
8 x 10-9
|
|
|
|
I
|
7 x 10-9
|
|
Einsteinium (99)
|
Es 253
|
S
|
3 x 10-11
|
|
|
|
I
|
2 x 10-11
|
|
|
Es 254m
|
S
|
2 x 10-10
|
|
|
|
I
|
2 x 10-10
|
|
|
Es 254
|
S
|
6 x 10-13
|
|
|
|
I
|
4 x 10-12
|
|
|
Es 255
|
S
|
2 x 10-11
|
|
|
|
I
|
1 x 10-11
|
|
Erbium (68)
|
Er 169
|
S
|
2 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
Er 171
|
S
|
2 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Europium (63)
|
Eu 152
|
S
|
1 x 10-8
|
|
|
(T/2 = 9.2 hrs)
|
I
|
1 x 10-8
|
|
|
Eu 152
|
S
|
4 x 10-10
|
|
|
(T/2 = 13 yrs)
|
I
|
6 x 10-10
|
|
|
Eu 154
|
S
|
1 x 10-10
|
|
|
|
I
|
2 x 10-10
|
|
|
Eu 155
|
S
|
3 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
Fermium (100)
|
Fm 254
|
S
|
2 x 10-9
|
|
|
|
I
|
2 x 10-9
|
|
|
Fm 255
|
S
|
6 x 10-10
|
|
|
|
I
|
4 x 10-10
|
|
|
Fm 256
|
S
|
1 x 10-10
|
|
|
|
I
|
6 x 10-11
|
|
Fluorine (9)
|
F 18
|
S
|
2 x 10-7
|
|
|
|
I
|
9 x 10-8
|
|
Gadolinium (64)
|
Gd 153
|
S
|
8 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
|
Gd 159
|
S
|
2 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
Gallium (31)
|
Ga 72
|
S
|
8 x 10-9
|
|
|
|
I
|
6 x 10-9
|
|
Germanium (32)
|
Ge 71
|
S
|
4 x 10-7
|
|
|
|
I
|
2 x 10-7
|
|
Gold (79)
|
Au 196
|
S
|
4 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
|
Au 198
|
S
|
1 x 10-8
|
|
|
|
I
|
8 x 10-9
|
|
|
Au 199
|
S
|
4 x 10-8
|
|
|
|
I
|
3 x 10-8
|
|
Hafnium (72)
|
Hf 181
|
S
|
1 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
Holmium (67)
|
Ho 166
|
S
|
7 x 10-9
|
|
|
|
I
|
6 x 10-9
|
|
Hydrogen (1)
|
H3
|
S
|
2 x 10-7
|
|
|
|
I
|
2 x 10-7
|
|
|
|
Sub
|
4 x 10-5
|
|
Indium (49)
|
In 113m
|
S
|
3 x 10-7
|
|
|
|
I
|
2 x 10-7
|
|
|
In 114m
|
S
|
4 x 10-9
|
|
|
|
I
|
7 x 10-10
|
|
|
In 115m
|
S
|
8 x 10-8
|
|
|
|
I
|
6 x 10-8
|
|
|
In 115
|
S
|
9 x 10-9
|
|
|
|
I
|
1 x 10-9
|
|
Iodine (53)
|
I 125
|
S
|
8 x 10-11
|
|
|
|
I
|
6 x 10-9
|
|
|
I 126
|
S
|
9 x 10-11
|
|
|
|
I
|
1 x 10-8
|
|
|
I 129
|
S
|
2 x 10-11
|
|
|
|
I
|
2 x 10-9
|
|
|
I 131
|
S
|
1 x 10-10
|
|
|
|
I
|
1 x 10-8
|
|
|
I 132
|
S
|
3 x 10-9
|
|
|
|
I
|
3 x 10-8
|
|
|
I 133
|
S
|
4 x 10-10
|
|
|
|
I
|
7 x 10-9
|
|
|
I 134
|
S
|
6 x 10-9
|
|
|
|
I
|
1 x 10-7
|
|
|
I 135
|
S
|
1 x 10-9
|
|
|
|
I
|
1 x 10-8
|
|
Iridium (77)
|
Ir 190
|
S
|
4 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
Ir 192
|
S
|
4 x 10-9
|
|
|
|
I
|
9 x 10-10
|
|
|
Ir 194
|
S
|
8 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
Iron (26)
|
Fe 55
|
S
|
3 x 10-8
|
|
|
|
I
|
3 x 10-8
|
|
|
Fe 59
|
S
|
5 x 10-9
|
|
|
|
I
|
2 x 10-9
|
|
Krypton (36)
|
Kr 85m
|
Sub
|
1 x 10-7
|
|
|
Kr 85
|
Sub
|
3 x 10-7
|
|
|
Kr 87
|
Sub
|
2 x 10-8
|
|
|
Kr 88
|
Sub
|
2 x 10-8
|
|
Lanthanum (57)
|
La 140
|
S
|
5 x 10-9
|
|
|
|
I
|
4 x 10-9
|
|
Lead (82)
|
Pb 203
|
S
|
9 x 10-8
|
|
|
|
I
|
6 x 10-8
|
|
|
Pb 210
|
S
|
4 x 10-12
|
|
|
|
I
|
8 x 10-12
|
|
|
Pb 212
|
S
|
6 x 10-10
|
|
|
|
I
|
7 x 10-10
|
|
Lutetium (71)
|
Lu 177
|
S
|
2 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Manganese (25)
|
Mn 52
|
S
|
7 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
|
Mn 54
|
S
|
1 x 10-8
|
|
|
|
I
|
1 x 10-9
|
|
|
Mn 56
|
S
|
3 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Mercury (80)
|
Hg 197m
|
S
|
3 x 10-8
|
|
|
|
I
|
3 x 10-8
|
|
|
Hg 197
|
S
|
4 x 10-8
|
|
|
|
I
|
9 x 10-8
|
|
|
Hg 203
|
S
|
2 x 10-9
|
|
|
|
I
|
4 x 10-9
|
|
Molybdenum (42)
|
Mo 99
|
S
|
3 x 10-8
|
|
|
|
I
|
7 x 10-9
|
|
Neodymium (60)
|
Nd 144
|
S
|
3 x 10-12
|
|
|
|
I
|
1 x 10-11
|
|
|
Nd 147
|
S
|
1 x 10-8
|
|
|
|
I
|
8 x 10-9
|
|
|
Nd 149
|
S
|
6 x 10-8
|
|
|
|
I
|
5 x 10-8
|
|
Neptunium (93)
|
Np 237
|
S
|
1 x 10-13
|
|
|
|
I
|
4 x 10-12
|
|
|
Np 239
|
S
|
3 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Nickel (28)
|
Ni 59
|
S
|
2 x 10-8
|
|
|
|
I
|
3 x 10-8
|
|
|
Ni 63
|
S
|
2 x 10-9
|
|
|
|
I
|
1 x 10-8
|
|
|
Ni 65
|
S
|
3 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Niobium (Columbium) (41)
|
Nb 93m
|
S
|
4 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
|
Nb 95
|
S
|
2 x 10-8
|
|
|
|
I
|
3 x 10-9
|
|
|
Nb 97
|
S
|
2 x 10-7
|
|
|
|
I
|
2 x 10-7
|
|
Osmium (76)
|
Os 185
|
S
|
2 x 10-8
|
|
|
|
I
|
2 x 10-9
|
|
|
Os 191m
|
S
|
6 x 10-7
|
|
|
|
I
|
3 x 10-7
|
|
|
Os 191
|
S
|
4 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
Os 193
|
S
|
1 x 10-8
|
|
|
|
I
|
9 x 10-9
|
|
Palladium (46)
|
Pd 103
|
S
|
5 x 10-8
|
|
|
|
I
|
3 x 10-8
|
|
|
Pd 109
|
S
|
2 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
Phosphorus (15)
|
P 32
|
S
|
2 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
Platinum (78)
|
Pt 191
|
S
|
3 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
|
Pt 193m
|
S
|
2 x 10-7
|
|
|
|
I
|
2 x 10-7
|
|
|
Pt 193
|
S
|
4 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
Pt 197m
|
S
|
2 x 10-7
|
|
|
|
I
|
2 x 10-7
|
|
|
Pt 197
|
S
|
3 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Plutonium (94)
|
Pu 238
|
S
|
7 x 10-14
|
|
|
|
I
|
1 x 10-12
|
|
|
Pu 239
|
S
|
6 x 10-14
|
|
|
|
I
|
1 x 10-12
|
|
|
Pu 240
|
S
|
6 x 10-14
|
|
|
|
I
|
1 x 10-12
|
|
|
Pu 241
|
S
|
3 x 10-12
|
|
|
|
I
|
1 x 10-9
|
|
|
Pu 242
|
S
|
6 x 10-14
|
|
|
|
I
|
1 x 10-12
|
|
|
Pu 243
|
S
|
6 x 10-8
|
|
|
|
I
|
8 x 10-8
|
|
|
Pu 244
|
S
|
6 x 10-14
|
|
|
|
I
|
1 x 10-12
|
|
Polonium (84)
|
Po 210
|
S
|
2 x 10-11
|
|
|
|
I
|
7 x 10-12
|
|
Potassium (19)
|
K 42
|
S
|
7 x 10-8
|
|
|
|
I
|
4 x 10-9
|
|
Praseodymium (59)
|
Pr 142
|
S
|
7 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
|
Pr 143
|
S
|
1 x 10-8
|
|
|
|
I
|
6 x 10-9
|
|
Promethium (61)
|
Pm 147
|
S
|
2 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
|
Pm 149
|
S
|
1 x 10-8
|
|
|
|
I
|
8 x 10-9
|
|
Protoactinium (91)
|
Pa 230
|
S
|
6 x 10-11
|
|
|
|
I
|
3 x 10-11
|
|
|
Pa 231
|
S
|
4 x 10-14
|
|
|
|
I
|
4 x 10-12
|
|
|
Pa 233
|
S
|
2 x 10-8
|
|
|
|
I
|
6 x 10-9
|
|
Radium (88)
|
Ra 223
|
S
|
6 x 10-11
|
|
|
|
I
|
8 x 10-12
|
|
|
Ra 224
|
S
|
2 x 10-10
|
|
|
|
I
|
2 x 10-11
|
|
|
Ra 226
|
S
|
3 x 10-12
|
|
|
|
I
|
2 x 10-12
|
|
|
Ra 228
|
S
|
2 x 10-12
|
|
|
|
I
|
1 x 10-12
|
|
Radon (86)
|
Rn 220
|
S
|
1 x 10-8
|
|
|
Rn 2223
|
I
|
3 x 10-9
|
|
Rhenium (75)
|
Re 183
|
S
|
9 x 10-8
|
|
|
|
I
|
5 x 10-9
|
|
|
Re 186
|
S
|
2 x 10-8
|
|
|
|
I
|
8 x 10-9
|
|
|
Re 187
|
S
|
3 x 10-7
|
|
|
|
I
|
2 x 10-8
|
|
|
Re 188
|
S
|
1 x 10-8
|
|
|
|
I
|
6 x 10-9
|
|
Rhodium (45)
|
Rh 103m
|
S
|
3 x 10-6
|
|
|
|
I
|
2 x 10-6
|
|
|
Rh 105
|
S
|
3 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Rubidium (37)
|
Rb 86
|
S
|
1 x 10-8
|
|
|
|
I
|
2 x 10-9
|
|
|
Rb 87
|
S
|
2 x 10-8
|
|
|
|
I
|
2 x 10-9
|
|
Ruthenium (44)
|
Ru 97
|
S
|
8 x 10-8
|
|
|
|
I
|
6 x 10-8
|
|
|
Ru 103
|
S
|
2 x 10-8
|
|
|
|
I
|
3 x 10-9
|
|
|
Ru 105
|
S
|
2 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
|
Ru 106
|
S
|
3 x 10-9
|
|
|
|
I
|
2 x 10-10
|
|
Samarium (62)
|
Sm 147
|
S
|
2 x 10-12
|
|
|
|
I
|
9 x 10-12
|
|
|
Sm 151
|
S
|
2 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
|
Sm 153
|
S
|
2 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
Scandium (21)
|
Sc 46
|
S
|
8 x 10-9
|
|
|
|
I
|
8 x 10-10
|
|
|
Sc 47
|
S
|
2 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
|
Sc 48
|
S
|
6 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
Selenium (34)
|
Se 75
|
S
|
4 x 10-8
|
|
|
|
I
|
4 x 10-9
|
|
Silicon (14)
|
Si 31
|
S
|
2 x 10-7
|
|
|
|
I
|
3 x 10-8
|
|
Silver (47)
|
Ag 105
|
S
|
2 x 10-8
|
|
|
|
I
|
3 x 10-9
|
|
|
Ag 110m
|
S
|
7 x 10-9
|
|
|
|
I
|
3 x 10-10
|
|
|
Ag 111
|
S
|
1 x 10-8
|
|
|
|
I
|
8 x 10-9
|
|
Sodium (11)
|
Na 22
|
S
|
6 x 10-9
|
|
|
|
I
|
3 x 10-10
|
|
|
Na 24
|
S
|
4 x 10-8
|
|
|
|
I
|
5 x 10-9
|
|
Strontium (38)
|
Sr 85m
|
S
|
1 x 10-6
|
|
|
|
I
|
1 x 10-6
|
|
|
Sr 85
|
S
|
8 x 10-9
|
|
|
|
I
|
4 x 10-9
|
|
|
Sr 89
|
S
|
3 x 10-10
|
|
|
|
I
|
1 x 10-9
|
|
|
Sr 90
|
S
|
3 x 10-11
|
|
|
|
I
|
2 x 10-10
|
|
|
Sr 91
|
S
|
2 x 10-8
|
|
|
|
I
|
9 x 10-9
|
|
|
Sr 92
|
S
|
2 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
Sulfur (16)
|
S 35
|
S
|
9 x 10-9
|
|
|
|
I
|
9 x 10-9
|
|
Tantalum (73)
|
Ta 182
|
S
|
1 x 10-9
|
|
|
|
I
|
7 x 10-10
|
|
Technetium (43)
|
Tc 96m
|
S
|
3 x 10-6
|
|
|
|
I
|
1 x 10-6
|
|
|
Tc 96
|
S
|
2 x 10-8
|
|
|
|
I
|
8 x 10-9
|
|
|
Tc 97m
|
S
|
8 x 10-8
|
|
|
|
I
|
5 x 10-9
|
|
|
Tc 97
|
S
|
4 x 10-7
|
|
|
|
I
|
1 x 10-8
|
|
|
Tc 99m
|
S
|
1 x 10-6
|
|
|
|
I
|
5 x 10-7
|
|
|
Tc 99
|
S
|
7 x 10-8
|
|
|
|
I
|
2 x 10-9
|
|
Tellurium (52)
|
Te 125m
|
S
|
1 x 10-8
|
|
|
|
I
|
4 x 10-9
|
|
|
Te 127m
|
S
|
5 x 10-9
|
|
|
|
|
I
|
1 x 10-9
|
|
|
|
Te 127
|
S
|
6 x 10-8
|
|
|
|
|
I
|
3 x 10-8
|
|
|
|
Te 129m
|
S
|
3 x 10-9
|
|
|
|
|
I
|
1 x 10-9
|
|
|
|
Te 129
|
S
|
2 x 10-7
|
|
|
|
|
I
|
1 x 10-7
|
|
|
|
Te 131m
|
S
|
1 x 10-8
|
|
|
|
|
I
|
6 x 10-9
|
|
|
|
Te 132
|
S
|
7 x 10-9
|
|
|
|
|
I
|
4 x 10-9
|
|
|
Terbium (65)
|
Tb 160
|
S
|
3 x 10-9
|
|
|
|
|
I
|
1 x 10-9
|
|
|
Thallium (81)
|
Tl 200
|
S
|
9 x 10-8
|
|
|
|
|
I
|
4 x 10-8
|
|
|
|
Tl 201
|
S
|
7 x 10-8
|
|
|
|
|
I
|
3 x 10-8
|
|
|
|
Tl 202
|
S
|
3 x 10-8
|
|
|
|
|
I
|
8 x 10-9
|
|
|
|
Tl 204
|
S
|
2 x 10-8
|
|
|
|
|
I
|
9 x 10-10
|
|
|
Thorium (90)
|
Th 227
|
S
|
1 x 10-11
|
|
|
|
|
I
|
6 x 10-12
|
|
|
|
Th 228
|
S
|
3 x 10-13
|
|
|
|
|
I
|
2 x 10-13
|
|
|
|
Th 230
|
S
|
8 x 10-14
|
|
|
|
|
I
|
3 x 10-13
|
|
|
|
Th 231
|
S
|
5 x 10-8
|
|
|
|
|
I
|
4 x 10-8
|
|
|
|
Th 232
|
S
|
1 x 10-12
|
|
|
|
|
I
|
1 x 10-12
|
|
|
|
Th natural
|
S
|
2 x 10-12
|
|
|
|
|
I
|
2 x 10-12
|
|
|
|
Th 234
|
S
|
2 x 10-9
|
|
|
|
|
I
|
1 x 10-9
|
|
|
Thulium (69)
|
Tm 170
|
S
|
1 x 10-9
|
|
|
|
|
I
|
1 x 10-9
|
|
|
|
Tm 171
|
S
|
4 x 10-9
|
|
|
|
|
I
|
8 x 10-9
|
|
|
Tin (50)
|
Sn 113
|
S
|
1 x 10-8
|
|
|
|
|
I
|
2 x 10-9
|
|
|
|
Sn 125
|
S
|
4 x 10-9
|
|
|
|
|
I
|
3 x 10-9
|
|
|
Tungsten (Wolfram) (74)
|
W 181
|
S
|
8 x 10-8
|
|
|
|
|
I
|
4 x 10-9
|
|
|
|
W 185
|
S
|
3 x 10-8
|
|
|
|
I
|
4 x 10-9
|
|
|
W 187
|
S
|
2 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
Uranium (92)
|
U 230
|
S
|
1 x 10-11
|
|
|
|
I
|
4 x 10-12
|
|
|
U 232
|
S
|
3 x 10-12
|
|
|
|
I
|
9 x 10-13
|
|
|
U 233
|
S
|
2 x 10-11
|
|
|
|
I
|
4 x 10-12
|
|
|
U 234
|
S4
|
2 x 10-11
|
|
|
|
I
|
4 x 10-12
|
|
|
U 235
|
S4
|
2 x 10-11
|
|
|
|
I
|
4 x 10-12
|
|
|
U 236
|
S
|
2 x 10-11
|
|
|
|
I
|
4 x 10-12
|
|
|
U 238
|
S4
|
3 x 10-12
|
|
|
|
I
|
5 x 10-12
|
|
|
U 240
|
S
|
8 x 10-9
|
|
|
|
I
|
6 x 10-9
|
|
|
U-natural
|
S4
|
5 x 10-12
|
|
|
|
I
|
5 x 10-12
|
|
Vanadium (23)
|
V 48
|
S
|
6 x 10-9
|
|
|
|
I
|
2 x 10-9
|
|
Xenon (54)
|
Xe 131m
|
Sub
|
4 x 10-7
|
|
|
Xe 133
|
Sub
|
3 x 10-7
|
|
|
Xe 133m
|
Sub
|
3 x 10-7
|
|
|
Xe 135
|
Sub
|
1 x 10-7
|
|
Ytterbium (70)
|
Yb 175
|
S
|
2 x 10-8
|
|
|
|
I
|
2 x 10-8
|
|
Yttrium (39)
|
Y 90
|
S
|
4 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
|
Y 91m
|
S
|
8 x 10-7
|
|
|
|
I
|
6 x 10-7
|
|
|
Y 91
|
S
|
1 x 10-9
|
|
|
|
I
|
1 x 10-9
|
|
|
Y 92
|
S
|
1 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
Y 93
|
S
|
6 x 10-9
|
|
|
|
I
|
5 x 10-9
|
|
Zinc (30)
|
Zn 65
|
S
|
4 x 10-9
|
|
|
|
I
|
2 x 10-9
|
|
|
Zn 69m
|
S
|
1 x 10-8
|
|
|
|
I
|
1 x 10-8
|
|
|
Zn 69
|
S
|
2 x 10-7
|
|
|
|
I
|
3 x 10-7
|
|
Zirconium (40)
|
Zr 93
|
S
|
4 x 10-9
|
|
|
|
I
|
1 x 10-8
|
|
|
Zr 95
|
S
|
4 x 10-9
|
|
|
|
I
|
1 x 10-9
|
|
|
Zr 97
|
S
|
4 x 10-9
|
|
|
|
I
|
3 x 10-9
|
|
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.
|
|
Sub
|
3 x 10-6
|
|
|
|
|
|
|
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.
|
|
|
1 x 10-10
|
|
|
|
|
|
|
Any single radionuclide not listed
above, that decays by alpha emission or spontaneous fission.
|
|
|
2 x 10-14
|
|
|
|
|
|
|
1Soluble (S);
Insoluble (I).
2"Sub" means that values given are for submersion in
a semispherical infinite cloud of airborne material.
3These radon concentrations are appropriate for protection
from radon-222 combined with its short-lived daughters. The value may be
replaced by one-thirtieth (1/30) of a "working level." A
"working level" is defined as any combination of short-lived
radon-222 daughters, polonium-218, lead-214, bismuth-214 and polonium-214, in
one liter of air, without regard to the degree of equilibrium, that will result
in the ultimate emission of 1.3 x 105 MeV of alpha particle energy.
4For soluble mixtures of U-238, U-234 and U-235 in air
chemical toxicity may be the limiting factor. The concentration value is 0.007
milligrams of uranium per cubic meter of air. The specific activity for
natural uranium is 6.77 x 10-7 curies per gram U. The specific
activity (SA) for other mixtures of U-238, U-235 and U-234, if not known, will
be:
SA = 3.6 x 10-7
curies/gram U........... U-depleted
SA = (0.4 +
0.38 E + 0.0034 E2) 10-6................................................
E ≥ 0.72
where E is
the percentage by weight of U-235, expressed as a percent.
NOTE: When a mixture in air of
more than one radionuclide exists, the limiting values of this Appendix should
be determined as follows:
1. If the identity and concentration of each radionuclide in the
mixture are known, the limiting values should be derived as follows:
Determine, for each radionuclide in the mixture, the ratio between the quantity
present in the mixture and the limit otherwise established in Appendix A for
the specific radionuclide when not in a mixture. The sum of the ratios for all
the radionuclides in the mixture may not exceed "1" (i.e.,
"unity").
EXAMPLE: If
radionuclides A, B, and C are present in concentrations CA, CB,
CC, and if the applicable MPCs are MPCA, and MPCB,
and MPCC respectively, then the concentrations must be limited so
that the following relationship exists:
(CA/MPCA)
+ (CB/MPCB) + (CC/MPCC) ≤ 1
2. If either the identity or the concentration of any
radionuclide in the mixture is not known, the limiting values of Appendix A must
be 2 x 10-14.
3. If any of the conditions specified below are met, the
corresponding values specified below may be used instead of those specified in
paragraph 2 above.
a. If the identity of each radionuclide in the mixture is known
but the concentration of one or more of the radionuclides in the mixture is not
known, the concentration limit for the mixture is the limit specified in
Appendix A for the radionuclide in the mixture having the lowest concentration
limit; or
b. If the identity of each radionuclide in the mixture is not
known but it is known that radionuclides specified in Appendix A are not
present in the mixture, the concentration limit for the mixture is the lowest
concentration limit specified in Appendix A for any radionuclide that is not
known to be absent from the mixture; or
c. Element (atomic number) and isotope. µCi/ml
|
If it is known that
alpha-emitters and Sr 90, I 129, Pb 210, Ac 227, Ra 228, Pa 230, Pu 241, and
Bk 249 are not present.
|
1 x 10-10
|
|
|
|
|
If it is known that
alpha-emitters and Pb 210, Ac 227, Ra 228, and Pu 241 are not present.
|
1 x 10-11
|
|
|
|
|
If it is known that
alpha-emitters and Ac 227 are not present.
|
1 x 10-12
|
|
|
|
|
If it is known that Ac 227, Th
230, Pa 231, Pu 238, Pu 239, Pu 240, Pu 242, Pu 244, Cm 248, Cf 249 and Cf
251 are not present.
|
1 x 10-13
|
4. If a
mixture of radionuclides consists of uranium and its daughters in ore dust before
chemical separation of the uranium from the ore, the following values may be
used for uranium and its daughters through radium-226, instead of those from
paragraphs 1, 2, or 3 above:
3 x 10-12 µCi/ml gross alpha
activity; 2 x 10-12 µCi/ml natural uranium; or 3 micrograms per cubic meter of
air natural uranium.
5. For
this note, a radionuclide may be considered as not present in a mixture if:
a. the
ratio of the concentration of that radionuclide in the mixture (CA)
to the concentration limit for that radionuclide specified in Appendix A (MPCA)
does not exceed 1/10 (i.e., CA/MPCA ≤ 1/10), and
b. the
sum of such ratios for all the radionuclides considered as not present in the
mixtures does not exceed 1/4, (i.e., (CA/MPCA + CB/MPCB
+ … ≤ 1/4).
(Source: Amended at 47 Ill. Reg. 6679, effective May 4, 2023)
|
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