TITLE 35: ENVIRONMENTAL PROTECTION

TITLE 35: ENVIRONMENTAL PROTECTION
SUBTITLE I: ATOMIC RADIATION
1. CHAPTER I: POLLUTION CONTROL BOARD

TITLE 35: ENVIRONMENTAL PROTECTION

SUBTITLE I: ATOMIC RADIATION

CHAPTER I: POLLUTION CONTROL BOARD

RADIATION HAZARDS

SUBPART A: GENERAL PROVISIONS

1000.101 Authority

Purpose and Policy

SUBPART B: DEFINITIONS

1000.201 Definitions

SUBPART C: STANDARDS AND LIMITATIONS

Permissable Levels of Radiation in Unrestricted Areas

Radioactive Emissions to Unrestricted Areas

SUBPART D: ADDITIONAL REQUIREMENTS

1000.401 Applicability

1000.402 Definitions

Environmental Standards for Uranium Fuel Cycle

SUBPART E: RECORDS

1000.501 Records

Notification of Incidents

1000.503 Other Provisions

Concentrations in Air Above Natural Background

AUTHORITY: Implementing Section 25(b) and authorized by Section 27 of the

Environmental Protection Act (Ill. Rev. Stat. 1985, ch. 111 1/2, pars. 1025(b) and 1027).

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.

SUBPART A: GENERAL PROVISIONS

Section 1000.101 Authority

The Pollution Control Board adopts the rules and regulations contained in this title

pursuant to the authority of Title VI-A of the Environmental Protection Act. (Ill. Rev.

Stat. 1983, ch. 111- 1/2, par. 1025(b)).

Section 1000.102 Purpose and Policy

a) The regulations in this Part establish standards for protection against

radiological air pollutants associated with materials and activities under

licenses issued by the United States Nuclear Regulatory Commission

pursuant to the Atomic Energy Act of 1954 (42 U.S.C. 5801 et seq.) as

amended, and the Energy Reorganization Act of 1974 (42 U.S.C. 5801 et

b) It is the policy of the Pollution Control Board that persons subject to this

Part shall, in addition to complying with the requirements of this Part,

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 taking into account 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. Persons licensed by the United States Nuclear Regulatory

Commission to operate light-water-cooled nuclear power reactors shall be

deemed to satisfy the requirements of this subsection if they achieve the

design objectives and limiting conditions for operation set out in 10 CFR

50, Appendix I (1984). This Part incorporates no further amendments or

editions to those objectives and conditions for operation.

Section 1000.103 Scope

The requirements of this Part apply to all persons who receive, possess, use, or transfer

material licensed pursuant to Parts 30 through 35, 40, or 70, or who are licensed to

operate a production or utilization facility pursuant to 10 CFR 50 of the regulations of the

United States Nuclear Regulatory Commission.

SUBPART B: DEFINITIONS

Section 1000.201 Definitions

As used in this Part:

"Act" means the Environmental Protection Act, Ill. Rev. Stat., 1983, ch.

111- 1/2, pars 1001 et seq.

"Board" means the Illinois Pollution Control Board.

"Department" means the Illinois Department of Nuclear Safety.

"Dose" means the quantity of radiation absorbed, per unit of mass, by the

body or by any portion of the body. When these regulations specify a dose

during a period of time, the dose 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. Several different units of dose are in current

use. Definitions of units as used in these regulations are set forth in the

definitions of "Rad" and "Rem" in this Section.

"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" means 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 upon the

biological effect under consideration and upon the condition of irradiation.

For the purpose of 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 for purposes of this Part be assumed to be equivalent to 14

million neutrons per square centimeter incident upon the body; or,

if there exists sufficient information to estimate with reasonable

accuracy the approximate distribution in 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

No. of Neutron per

square centimeter

equivalent to a dose

Average flux to

deliver 100 millirem

"Restricted area" means any area access to which is controlled by the

licensee for purposes of protection of individuals from exposure to

radiation and radioactive materials. "Restricted area" shall 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 access to which is not controlled by

the licensee for purposes of protection of individuals from exposure to

radiation and radioactive materials, and any area used for residential

(Source: Amended at 10 Ill. Reg. 12938, effective July 21, 1986)

SUBPART C: STANDARDS AND LIMITATIONS

Section 1000.301 Permissible Levels of Radiation in Unrestricted Areas

No person shall possess, use, receive, or transfer licensed material or engage in licensed

activities in such manner as to create in any unrestricted area:

a) Radiation levels in air such that any individual would be likely, when all

radioactive emissions by the licensee are taken into account, to receive a

dose to the whole body in excess of 0.5 rem in any one year;

b) Radiation levels in air which, if an individual were continuously present in

the area, could result, when all radioactive emissions by the licensee are

taken into account, in his receiving a dose in excess of 2 millirems in any

c) Radiation levels in air which, if an individual were continuously present in

the area, could result, when all radioactive emissions by licensee are taken

into account, in his receiving a dose in excess of 100 millirems in any

seven consecutive days.

Section 1000.302 Radioactive Emissions to Unrestricted Areas

a) No person shall possess, use, receive, or transfer licensed material or

engage in licensed activities so as to release to air in an unrestricted area

radioactive material in concentrations which exceed the limits specified in

Appendix A of this Part. For purposes of this Section concentrations may

be averaged over a period not greater than one year.

b) For the purpose of this section the concentration limits in Appendix A of

this Part shall apply at the boundary of the restricted area. The

concentration of radioactive material discharged through a stack, pipe or

similar conduit may be determined with respect to 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.

SUBPART D: ADDITIONAL REQUIREMENTS

Section 1000.401 Applicability

The provisions of this part apply to radiation doses received by members of the public in

the general environment and to radioactive materials introduced into the general

environment as the result of operations which are part of a nuclear fuel cycle.

Section 1000.402 Definitions

As used in this Subpart:

"Curie" (Ci) means that quantity of radioactive material producing 37

billion nuclear transformations per second. (One millicurie (mCi)=0.001

"Dose equivalent" means the product of absorbed dose and appropriate

factors to account for differencies 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 which 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 that can receive a radiation

dose in the general environment, whether he may or may not also be

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 he is engaged in carrying out any operation which 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,

"Site" means the area contained within the boundary of a location under

the control of persons possessing or using radioactive material on which is

conducted one or more operations covered by this part.

"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, but excludes

mining operations, operations at waste disposal sites, transportation of any

radioactive material in support of these operations, and the reuse of

recovered nonuranium special nuclear and by-product materials from the

Section 1000.403 Environmental Standards for Uranium Fuel Cycle

Operations covered by this Subpart shall be conducted in such a manner as to provide

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 halflives greater than one year.

SUBPART E: RECORDS

Section 1000.501 Records

All persons subject to this Part shall submit to the Department, with respect to 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.

b) Application for Construction Permit and for all amendments thereto,

including information required by 10 CFR 50.34a, 50.36, and 51.20.

c) Environmental Impact Appraisal, Draft and Final Environmental Impact

Statement, Negative Declaration, or other document prepared by the NRC

under 10 CFR 51.

d) Operating Permit and all amendments thereto, including Technical

Specifications under 10 CFR 50.36a.

e) Application for Amendment to Operating License.

f) All data, records, and reports submitted to the NRC in connection with

determining or predicting radiation levels in air in unrestricted areas or the

type or amount of radioactive materials emitted into air conducted by or

for such persons.

Section 1000.502 Notification of Incidents

All person subject to this Part shall immediately notify by telephone and telegraph,

mailgram, or facsimile, the Manager of the Office of Nuclear Facility Safety of the

Illinois Department of Nuclear Safety, 1035 Outer Park Drive, Springfield, Illinois

62704, 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 in excess of those allowed under this Part.

Section 1000.503 Other Provisions

a) The definitions set out 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 35 Ill. Adm. Code 201.122, 201.123, 201.124, 201.125, 201.

126, 201.141, 201.150 and 201.151.

Section 1000.APPENDIX A Concentrations in Air Above Natural Background

Element (atomic

Californium (98)

Dysprosium (66)

Einsteinium (99)

(T/2=9 2 hrs) I

Gadolinium (64)

Molybdenum (42)

(Columbium) (41)

Phosphorus (15)

Praseodymium (59)

Promethium (61)

Protoactinium (91)

Technetium (43)

Tungsten (Wolfram)

radionuclide not

listed above with

decay mode other

than alpha emission

fission and with

radio-active half-life

less than 2 hours

radionuclide not

listed above with

decay mode other

than alpha emission

fission and with

radio- active half-

life greater than 2

radionuclide not

listed above, which

decays by alpha

spontaneous fission

Soluble (S); Insoluble (I).

"Sub" means that values given are for submersion in a semispherical infinite

cloud of airborne material.

These 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 10 MeV of alpha particle energy.)

For 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 uranium per cubic meter

of air. The specific activity for natural uranium is 6.77 x 10- curies per gram U. The

specific activity for other mixtures of U-238, U-235 and U-234, if not known, shall be:

curies/gram U.................. U-depleted

SA=(0.4 + 0.38 E + 0.0034 E

......... E > than 0.72

where E is the percentage by weight of U-235, expressed as percent.

NOTE: In any case where there is a mixture in air of more than one radionuclide,

the limiting values for purposes 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 such 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 MPC's are MPCA, and MPCB, and MPCC respectively, then the

concentrations shall be limited so that the following relationship exists:

(CA/MPCA) + (CB/MPCB) + (CC/MPCC) < than 1

2. If either the identity or the concentration of any radionuclide in the

mixture is not known the limiting values for purposes of Appendix A shall be 2 x 10

3. If any of the conditions specified below are met, the corresponding values

specified below may be used in lieu 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 now known, but it is

known that certain 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 which is not known to be absent from the mixture; or

c. Element (atomic number) and isotope.

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.

If it is known that alpha-emitters and Pb 210, Ac 227, Ra 228,

and Pu 241 are not present.

If it is known that alpha-emitters and Ac 227 are not present.

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.

4. If a mixture of radionuclides consists of uranium and its daughters in ore

dust prior to chemical separation of theuranium 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:

Ci/ml gross alpha activity; 2 x 10

uCi/ml natural uranium; or 3

micrograms per cubic meter of air natural uranium.

5. For purposes of 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 (C(A))

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....+< than 1/4).

(Source: Amended at 10 Ill. Reg. 12938, effective July 21, 1986)