TITLE 35: ENVIRONMENTAL PROTECTION
SUBPART A: GENERAL PROVISIONS SUBPART B: DEFINITIONS SUBPART C: STANDARDS AND LIMITATIONS
SUBPART D: ADDITIONAL REQUIREMENTS
SUBPART E: RECORDS |
AUTHORITY: Implementing Section 25b and authorized by Section 27 of the Environmental Protection Act [415 ILCS 5/25b and 27].
SOURCE: Adopted in R82-2 at 9 Ill. Reg. 19391, effective December 4, 1985; amended in R82-2(B) at 10 Ill. Reg. 12938, effective July 21, 1986; amended in R18-28 at 47 Ill. Reg. 6679, effective May 4, 2023.
SUBPART A: GENERAL PROVISIONS
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)
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)
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
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)
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
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)
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
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)
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)
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
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)
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)
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
|
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)