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TITLE 32: ENERGY CHAPTER II: DEPARTMENT OF NUCLEAR SAFETY SUBCHAPTER b: RADIATION PROTECTION

PART 341 TRANSPORTATION OF RADIOACTIVE MATERIAL

Section 341.10 Purpose and Scope 341.20 Definitions 341.30 Requirement for License 341.40 Exemptions 341.50 Transportation of Licensed Material 341.60 General Licenses for Carriers 341.70 General License: Approved Packages 341.80 Previously Approved Type B Packages 341.90 General License: DOT Specification Container 341.100 General License: Use of Foreign Approved Package 341.110 General License: Type A, Fissile Class II Packages 341.120 General License: Restricted, Fissile Class II Package 341.130 Fissile Material: Assumptions as to Unknown Properties 341.140 Preliminary Determinations 341.150 Routine Determinations 341.160 Air Transport of Plutonium 341.170 Records 341.180 Reports 341.190 Advance Notification of Transport of Nuclear Waste 341.200 Quality Assurance Requirements

APPENDIX A DETERMINATION OF A1 AND A2 TABLE A A1 and A2 VALUES FOR RADIONUCLIDES TABLE B RELATIONSHIP BETWEEN A1 AND E max FOR BETA EMITTERS TABLE C RELATIONSHIP BETWEEN A3 AND THE ATOMIC NUMBER OF THE RADIONUCLIDE TABLE D ACTIVITY-MASS RELATIONSHIPS FOR URANIUM/THORIUM

AUTHORITY: Implementing and authorized by the Radiation Protection Act (Ill. Rev. Stat. 1986 Supp., ch. 111«, pars. 211 et seq.), and Section 9 of the Illinois Low-Level Radioactive Waste Management Act (Ill. Rev. Stat. 1986 Supp., ch. 111«, par. 241-9), and by Section 71 of The Civil Administrative Code of Illinois (Ill. Rev. Stat. 1986 Supp., ch. 127, par. 63b17G).

SOURCE: Adopted at 10 Ill. Reg. 17616, effective September 25, 1986; amended at 11 Ill. Reg. 5219, effective March 13, 1987; amended at 12 Ill. Reg. 2434, effective January 15, 1988.

Section 341.10 Purpose and Scope

The regulations in this Part establish requirements for packaging, preparation for shipment, and transportation of radioactive material and apply to any person who transports radioactive material or delivers radioactive material to a carrier for transport. Section 341.20 Definitions

As used in this Part, the following definitions apply:

"A(1)" means the maximum activity of special form radioactive material permitted in a Type A package.

"A(2)" means the maximum activity of radioactive material, other than special form radioactive material, permitted in a Type A package.

AGENCY NOTE: These values are either listed in Appendix A, Table A, or may be derived in accordance with the procedure prescribed in Appendix A of this Part.

"Carrier" means a person engaged in the transportation of passengers or property by land or water as a common, contract, or private carrier, or by civil aircraft.

"Exclusive use" (also referred to in regulations of the U.S. Department of Transportation as "sole use" or "full load") means the sole use of a conveyance by a single consignor and for which all initial, intermediate, and final loading and unloading are carried out in accordance with the direction of the consignor or consignee.

"Fissile material" means any special nuclear material* consisting of or containing one or more fissile radionuclides. Fissile radionuclides are plutonium-238, plutonium-239, plutonium-241, uranium-233, and uranium-235. Neither natural nor depleted uranium is fissile material.

*AGENCY NOTE: Department of Nuclear Safety (Department) jurisdiction extends to special nuclear material only if quantities are not sufficient to form a critical mass as defined in 32 Ill. Adm. Code 310.

Fissile Class I: A package which may be transported in unlimited numbers and in any arrangement, and which requires no nuclear criticality safety controls during transportation.

Fissile Class II: A package which may be transported together with other packages in any arrangement but, for criticality control, in numbers which do not exceed an aggregate transport index* of 50. These shipments require no other nuclear criticality safety control during transportation. Individual packages may have a transport index not less than 0.1 and not more than 10.

*AGENCY NOTE: A transport index is not assigned for purposes of nuclear criticality safety but may be required because of external radiation levels.

"Low specific activity material" means any of the following:

Uranium or thorium ores and physical or chemical concentrates of those ores;

Unirradiated natural or depleted uranium or unirradiated natural thorium;

Tritium oxide in aqueous solutions provided the concentration does not exceed 5.0 millicuries (185 MBq) per milliliter;

Material in which the radioactivity is essentially uniformly distributed and in which the estimated average concentration per gram of contents does not exceed:

0.0001 millicurie (3.7 kBq) of radionuclides for which the A2 quantity in Appendix A of this Part is not more than 0.05 curie (1.85 GBq);

0.005 millicurie (185 kBq) of radionuclides for which the A2 quantity in Appendix A of this Part is more than 0.05 curie (1.85 GBq), but not more than 1 curie (37 GBq); or

0.3 millicurie (11.1 MBq) of radionuclides for which the A2 quantity in Appendix A of this Part is more than 1 curie (37 GBq).

Objects of non-radioactive material externally contaminated with radioactive material, provided that the radioactive material is not readily dispersible and the surface contamination, when averaged over an area of 1 square meter, does not exceed 0.0001 millicurie (220,000 transformations per minute) (3.7 kBq) per square centimeter of radionuclides for which the A2 quantity in Appendix A of this Part is not more than 0.05 curie (1.85 GBq), or 0.001 millicurie (2,200,000 disintegrations per minute) (37 kBq) per square centimeter for other radionuclides.

"Normal form radioactive material" means radioactive material which has not been demonstrated to qualify as "special form radioactive material."

"Package" means the packaging together with its radioactive contents as presented for transport.

"Packaging" means the assembly of components necessary to ensure compliance with the packaging requirements of this Part. It may consist of one or more receptacles, absorbent materials, spacing structures, thermal insulation, radiation shielding, and devices for cooling or absorbing mechanical shocks. The vehicle, tie down system, and auxiliary equipment may be designated as part of the packaging.

"Regulations of the U.S. Department of Transportation (U.S. DOT)" means the regulations in 49 CFR 100-189, revised as of October 1, 1986, exclusive of subsequent amendments or editions. A copy of 49 CFR 100-189 is available for public inspection at the Department of Nuclear Safety.

"Special form radioactive material" means radioactive material which satisfies the following conditions:

It is either a single solid piece or is contained in a sealed capsule that can be opened only by destroying the capsule;

The piece or capsule has at least one dimension not less than 5 millimeters (0.197 inch); and

All special form radioactive material must meet the requirements of the U.S. Nuclear Regulatory Commission (NRC) regulations 10 CFR 71.75 and 71.77, revised as of January 1, 1987, exclusive of subsequent amendments or editions, except that special form radioactive material designed or constructed prior to July 1, 1985 need only meet the requirements of 10 CFR 71.75 and 71.77 in effect on June 30, 1983. A copy of 10 CFR 71 is available for public inspection at the Department of Nuclear Safety.

"Specific activity" of a radionuclide means the radioactivity of the radionuclide per unit mass of that nuclide. The specific activity of a material in which the radionuclide is essentially uniformly distributed is the radioactivity per unit mass of the material.

"Transport index" means the dimensionless number (rounded up to the decimal place) placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation. The transport index is the number expressing the maximum radiation level in millirem per hour at 1 meter from the external surface of the package.

"Type A quantity" means a quantity of radioactive material, the aggregate radioactivity of which does not exceed A1 for special form radioactive material or A2 for normal form radioactive material, where A1 and A2 are given in Appendix A of this Part or may be determined by procedures described in Appendix A of this Part.

"Type B package" means a Type B packaging together with its radio- active contents. A Type B package design is designated as B(U) or B(M). B(U) refers to the need for unilateral approval of interna- tional shipments; B(M) refers to the need for multilateral approval. There is no distinction made in how packages with these designations may be used in domestic transportation. To determine their distinction for international transportation, see DOT regulations in 49 CFR 173. A Type B package approved prior to September 6, 1983, was designated only as Type B. Limitations on its use are specified in Section 341.80.

"Type B packaging" means a packaging designed to retain the integrity of containment and shielding required by U.S. NRC regulations when subjected to the normal conditions of transport and hypothetical accident test conditions set forth in 10 CFR 71, revised as of January 1, 1987, exclusive of subsequent amendments or editions. A copy of 10 CFR 71 is available for public inspection at the Department of Nuclear Safety.

"Type B quantity" means a quantity of radioactive material greater than a Type A quantity.

(Source: Amended at 12 Ill. Reg. 2434, effective January 15, 1988)

Section 341.30 Requirement for License

No person shall transport radioactive material or deliver radioactive material to a carrier for transport except as authorized in a general or specific license issued by the Department or as exempted in Section 341.40.

Section 341.40 Exemptions

a) Common and contract carriers, freight forwarders, and warehousemen who are subject to the requirements of the U.S. DOT in 49 CFR 170 through 189 or the U.S. Postal Service in the Postal Service Manual (Domestic Mail Manual), Section 124.3 incorporated by reference, 39 CFR 111.1 (1984), are exempt from 32 Ill. Adm. Code 310, 320, 330, 340, 350, 400 and this Part to the extent that they transport or store radioactive material in the regular course of their carriage for another or storage incident thereto. Common and contract carriers who are not subject to the requirements of the U.S. DOT or U.S. Postal Service are subject to Section 341.30 and other applicable sections of this Part.

b) Any licensee is exempt from the requirements of this Part to the extent that the licensee delivers to a carrier for transport a package containing radioactive material having a specific activity not greater than 0.002 microcurie (74 Bq) per gram.

c) A licensee is exempt from all requirements of this Part, other than Sections 341.50 and 341.160 with respect to shipment or carriage of the following:

1) Packages containing no more than Type A quantities of radioactive material if the package contains no fissile material; or

2) Packages, transported between locations within the United States, which contain only americium or plutonium in special form with an aggregate radioactivity not to exceed 20 curies.

Section 341.50 Transportation of Licensed Material

a) No licensee may transport licensed material outside the confines of his plant or other place of use or deliver licensed material to a carrier for transport unless:

1) such transport and delivery is in compliance with the regulations of the U.S. DOT, 49 CFR revised as of October 1, 1986, exclusive of subsequent amendments or editions, and;

2) any special instructions needed to safely open the package have been made available to the consignee.

b) If, for any reason, the regulations of the U.S. DOT are not applicable to a shipment of licensed material, the licensee shall conform to the standards and requirements of those regulations to the same extent as if the shipment were subject to the regulations.

(Source: Amended at 12 Ill. Reg. 2434, effective January 15, 1988)

Section 341.60 General Licenses for Carriers

a) A general license is hereby issued to any common or contract carrier not exempt under Section 341.40 to receive, possess, transport, and store radioactive material in the regular course of its carriage for another or storage incident thereto, provided the transportation and storage is in accordance with U.S. DOT regulations (49 CFR 171 through 178, revised as of November 1, 1984, exclusive of subsequent amendments or editions), insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting.* Copies of 49 CFR 171 through 178 are available for inspection at the Department of Nuclear Safety.

b) A general license is hereby issued to any private carrier to transport radioactive material, provided the transportation is in accordance with U.S. DOT regulations (49 CFR 171 through 178, revised as of November 1, 1984, exclusive of subsequent amendments or editions), insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting.* Copies of 49 CFR 171 through 178 are available for inspection at the Department of Nuclear Safety,

*AGENCY NOTE: Any notification of incidents referred to in those U.S. DOT requirements shall be filed with, or made to, the Department.

c) Persons who transport radioactive material pursuant to the general licenses in Section 341.60(a) or 341.60(b) are exempt from the requirements of 32 Ill. Adm. Code 340 and 400 to the extent that they transport radioactive material.

Section 341.70 General License: Approved Packages

a) A general license is hereby issued to any licensee of the Department to transport, or to deliver to a carrier for transport, licensed material in a package for which a license, certificate of compliance, or other approval has been issued by the U.S. Nuclear Regulatory Commission.

b) This general license applies only to a licensee who:

1) Has a copy of the specific license, certificate of compliance, or other approval of the package, and has the drawings and other documents referenced in the approval relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment;

2) Complies with the terms and conditions of the license, certificate, or other approval, as applicable, and the applicable requirements of Subsections 341.70(a), (b)(1), (b)(3), (b)(4), (c), (d) and Sections 341.50, 341.140, 341.150, 341.170, 341.180, 341.190 and 341.200;

3) Prior to the licensee's first use of the package, has registered with the U.S. Nuclear Regulatory Commission; and

4) Has a quality assurance program as required by Section 341.200 approved by the Department.

c) The general license in Subparagraph (a) applies only when the package approval authorizes use of the package under this general license.

d) For previously approved Type B packages which are not designated as either B(U) or B(M) in the NRC Certificate of Compliance, this general license is subject to additional restrictions of Section 341.80.

Section 341.80 Previously Approved Type B Packages

A Type B package previously approved by the NRC, but not designated as B(U) or B(M) in the NRC Certificate of Compliance, may be used under the general license of Section 341.70 with the following additional limitations:

a) Fabrication of the packaging was satisfactorily completed before August 31, 1986, as demonstrated by application of its model number in accordance with U.S. NRC regulations 10 CFR 71, Subparts E, F, G, and H, revised as of January 1, 1985, exclusive of subsequent amendments or editions. A copy of 10 CFR 71 is available for public inspection at the Department of Nuclear Safety; and

b) The package may not be used for a shipment to a location outside the United States after August 31, 1986, except under special arrangement approved by the U.S. DOT in accordance with 49 CFR 173.471, revised as of November 1, 1984, exclusive of subsequent amendments or editions. A copy of 49 CFR 173 is available for public inspection at the Department of Nuclear Safety.

Section 341.90 General License: DOT Specification Container

a) A general license is issued to any licensee of the Department to transport or to deliver to a carrier for transport licensed material in a specification container for a Type B quantity of radioactive material as specified in the regulations of the U.S. DOT in 49 CFR 173 and 178, revised as of November 1, 1984, exclusive of subsequent amendments or editions. Copies of 49 CFR 173 and 178 are available for public inspection at the Department of Nuclear Safety.

b) This general license applies only to a licensee who has a quality assurance program approved by the Department as satisfying the provisions of Section 341.200.

c) This general license applies only to a licensee who:

1) Has a copy of the specifications in accordance with 49 CFR 178; and

2) Complies with the terms and conditions of the specifications in accordance with 49 CFR 178 and the requirements of this Part.

d) The general license in subsection (a) is subject to the limitation that the specification container may not be used for a shipment to a location outside the United States after August 31, 1986, except under special arrangements approved by U.S. DOT in accordance with 49 CFR 173.472, revised as of November 1, 1984, exclusive of subsequent amendments or editions. A copy of 49 CFR 173 is available for public inspection at the Department of Nuclear Safety.

Section 341.100 General License: Use of Foreign Approved Package

a) A general license is issued to any licensee of the Department to transport or to deliver to a carrier for transport licensed material in a package the design of which has been approved in a foreign national competent authority certificate which has been revalidated by the U.S. DOT as meeting the applicable requirements of 49 CFR 171.12, revised as of November 1, 1984, exclusive of subsequent amendments or editions.

b) This general license applies only to shipments made to or from locations outside the United States.

c) This general license applies only to a licensee who:

1) Has a copy of the certificate, the revalidation, and the drawings and other documents referenced in the certificate

relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment; and

2) Complies with the terms and conditions of the certificate and revalidation and with the requirements of this Part.

Section 341.110 General License: Type A, Fissile Class II Packages

a) A general license is hereby issued to any licensee to transport fissile material, or to deliver fissile material to a carrier for transport, if the material is shipped as a Fissile Class II package.

b) This general license applies only when a package contains no more than a Type A quantity of radioactive material, including only one of the following:

1) Up to 40 grams of uranium-235; or

2) Up to 30 grams of uranium-233; or

3) Up to 25 grams of the fissile radionuclides of plutonium, except that for encapsulated plutonium-beryllium neutron sources in special form, an A1 quantity of plutonium may be present; or

4) A combination of fissile radionuclides in which the sum of the ratios of the amount of each radionuclide to the corresponding maximum amounts in Section 341.110(b)(1), (2), and (3) does not exceed unity.

c) This general license applies only when:

1) A package containing more than 15 grams of fissile radionuclides is labeled with a transport index not less than the number given by the following equation, where the package contains x grams of uranium-235, y grams of uranium-233, and z grams of the fissile radionuclides of plutonium:

minimum transport index = (0.4x + 0.67y + z)(1- 15 ) x+y+z

The transport index must be rounded up to one decimal place, and may not exceed 10.0; or

2) For a package in which the only fissile material is in the form of encapsulated plutonium-beryllium neutron sources in special form, the transport index based on criticality considerations shall be taken as 0.026 times the number of grams of the fissile radionuclides of plutonium in excess of 15 grams. The transport index must be rounded up to one decimal place, and shall not exceed 10.0.

Section 341.120 General License: Restricted, Fissile Class II Package

a) A general license is hereby issued to any licensee to transport fissile material, or to deliver fissile material to a carrier for transport, if the material is shipped as a Fissile Class II package.

b) This general license applies only when:

1) The package contains no more than a Type A quantity of radioactive material; and

2) Neither beryllium nor hydrogenous material enriched in deuterium is present; and

3) The total mass of graphite present does not exceed 150 times the total mass of uranium-235 plus plutonium; and

4) Substances having a higher hydrogen density than water, e.g. certain hydrocarbon oils, are not present, except that polyethylene may be used for packing or wrapping; and

5) Uranium-233 is not present, and the amount of plutonium does not exceed 1% of the amount of uranium-235; and

6) The amount of uranium-235 is limited as follows:

A) If the fissile radionuclides are not uniformly distributed, the maximum amount of uranium-235 per package may not exceed the value given as follows:

Uranium enrichment in Permissible maximum weight percent of grams of uranium-235 uranium-235 per package not exceeding

24 40 20 42 15 45 11 48 10 51 9.5 52 9 54 8.5 55 8 57 7.5 59 7 60 6.5 62 6 65 5.5 68 5 72 4.5 76 4 80 3.5 88 3 100 2.5 120 2 164 1.5 272 1.35 320 1 680* 0.92 1200*

*AGENCY NOTE: Pursuant to its agreement with the U.S. Nuclear Regulatory Commission, Department jurisdiction extends only to 350 grams of uranium-235.

B) If the fissile radionuclides are distributed uniformly (i.e., cannot form a lattice arrangement within the packaging) the maximum amount of uranium-235 per package may not exceed the value given as follows:

Uranium enrichment Permissible maximum in weight percent of grams of uranium-235 uranium-235 not per package exceeding

4 84 3.5 92 3 112 2.5 148 2 240 1.5 560* 1.35 800*

*AGENCY NOTE: Pursuant to its agreement with the U.S. Nuclear Regulatory Commission, Department jurisdiction extends only to 350 grams of uranium-235.

7) The transport index of each package based on criticality considerations is taken as ten (10) times the number of grams of uranium-235 in the package divided by the maximum allowable number of grams per package in accordance with Subsection (b)(6)(A) or (b)(6)(B) above as applicable.

Section 341.130 Fissile Material: Assumptions as to Unknown Properties

When the isotopic abundance, mass, concentration, degree of irradiation, degree of moderation, or other pertinent property of fissile material in any package is not known, the licensee shall package the fissile material as if the unknown properties have credible values that will cause the maximum nuclear reactivity.

Section 341.140 Preliminary Determinations

Prior to the first use of any packaging for the shipment of radioactive material:

a) The licensee shall ascertain that there are no defects in the packaging which could impact on compliance with the standards specified in 10 CFR 71, Subparts (E) and (F), revised as of January 1985, exclusive of subsequent amendments or editions;

b) Where the maximum normal operating pressure will exceed 34.3 kilopascal (5 psi) gauge, the licensee shall test the containment system at an internal pressure at least 50% higher than the maximum normal operating pressure to verify the capability of that system to maintain its structural integrity at that pressure.

c) The licensee shall conspicuously and durably mark the packaging with its model number, gross weight, and a package identification number assigned by the U.S. Nuclear Regulatory Commission. Prior to applying the model number, the licensee shall determine that the packaging has been fabricated in accordance with the design approved in the certificate of compliance issued by the U.S. Nuclear Regulatory Commission.

Section 341.150 Routine Determinations

Prior to each shipment of licensed material, the licensee shall ensure that the package with its contents satisfies the requirements of this Part and of the license. The licensee shall determine that:

a) The package is proper for the contents to be shipped in accordance with 49 CFR 173.401 through 173.435;

b) The package is in unimpaired physical condition except for superficial defects such as marks or dents;

c) Each closure device of the packaging, including any required gasket, is properly installed and secured and free of defects;

d) Any system for containing liquid is sealed and has space or other specified provision for expansion of the liquid in accordance with 10 CFR 71, Subpart F, revised as of January 1985, exclusive of subsequent amendments or editions;

e) Any pressure relief device is operable and set in accordance with the certificate of compliance;

f) The package has been loaded and closed in accordance with written procedures;

g) Any structural part of the package which could be used to lift or tie down the package during transport is rendered inoperable for that purpose unless it satisfies design requirements specified in accordance with 10 CFR 71.45, revised as of January 1985, exclusive of subsequent amendments or editions;

h) The package meets the following requirements for removable contamination:

1) The level of non-fixed (removable) radioactive contamination on the external surfaces of each package offered for shipment is as low as reasonably achievable. The level of non-fixed radioactive contamination may be determined by wiping an area of 300 square centimeters of the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the wiping material. Sufficient measurements must be taken in the most appropriate locations to yield a representative assessment of the non-fixed contamination levels.* Except as provided under Section 341.150(h) (2), the amount of radioactivity measured on any single wiping material when averaged over the surface wiped, must not exceed the limits given in Subsection (h)(1) of this Part at any time during transport. Other methods of assessment of equal or greater efficiency may be used. When other methods are used, the detection efficiency of the method used must be taken into account and in no case may the non-fixed contamination on the external surfaces of the package exceed ten (10) times the limits listed as follows:

REMOVABLE EXTERNAL RADIOACTIVE CONTAMINATION WIPE LIMITS

Maximum Permissible Limits

Contaminant uCi/cm2 dpm/cm2

Beta-gamma emitting radionuclides; all radio- nuclides with half-lives less than ten (10) days; natural uranium; natural thorium; uranium-235; uranium-238; thorium-232; thorium-228; and thorium-230 when contained in ores or physical concentrates......... 10-5 22

All other alpha emitting radionuclides............ 10-6 2.2

2) In the case of packages transported as exclusive use shipments by rail or highway only, the non-fixed radioactive contamination at any time during transport must not exceed ten (10) times the levels prescribed in Section 341.150(h) (1). The levels at the beginning of transport must not exceed the levels prescribed in Section 341.150(h)(1);

*AGENCY NOTE: One generally acceptable technique is to perform one wipe test per square meter of surface area of the package. Appropriate locations for wipes include the areas where the package might leak through sealing gaskets or a location where water might stand on the container.

i) External radiation levels around the package and around the vehicle, if applicable, will not exceed 200 millirem per hour at any point on the external surface of the package at any time during transportation. The transport index shall not exceed ten (10).

j) For a package transported as exclusive use by rail, highway, or water, radiation levels external to the package may exceed the limits specified in Subparagraph (i) but must not exceed any of the following:

1) 200 millirem/hour on the accessible external surface of the package unless the following conditions are met, in which case the limit is 1000 millirem per hour.

A) The shipment is made in a closed transport vehicle;

B) Provisions are made to secure the package so that its position within the vehicle remains fixed during transportation; and

C) There are no loading or unloading operations between the beginning and end of the transportation;

2) 200 millirem/hour at any point on the outer surface of the vehicle, including the upper and lower surfaces, or, in the case of an open vehicle, at any point on the vertical planes projected from the outer edges of the vehicle, on the upper surface of the load, and on the lower external surface of the vehicle;

3) 10 millirem/hour at any point two meters from the vertical planes represented by the outer lateral surfaces of the vehicle, or, in the case of an open vehicle, at any point two meters from the vertical planes projected from the outer edges of the vehicle; and

4) 2 millirem/hour in any normally occupied position of the vehicle, except that this provision does not apply to private motor carriers when persons occupying these positions are provided with special health supervision, personnel radiation exposure monitoring devices, and training in accordance with 32 Ill. Adm. Code 400.

k) A package must be prepared for transport so that in still air at lOOøF (38øC) and in the shade, no accessible surface of a package would have a temperature exceeding 122øF (50øC) in a nonexclusive use shipment or 180øF (82øC) in an exclusive use shipment. Accessible package surface temperatures shall not exceed these limits at any time during transportation.

Section 341.160 Air Transport of Plutonium

Notwithstanding the provisions of any general licenses and notwithstanding any exemptions stated directly in this part or included indirectly by citation of U.S. DOT regulations, as may be applicable, the licensee shall assure that plutonium in any form is not transported by air or delivered to a carrier for air transport unless:

a) The plutonium is contained in a medical device designed for individual human application; or

b) The plutonium is contained in a material in which the specific activity is not greater than 0.002 microcuries (74 Bq) per gram of material and in which the radioactivity is essentially uniformly distributed; or

c) The plutonium is shipped in a single package containing no more than an A2 quantity of plutonium in any isotope or form and is shipped in accordance with Section 341.50; or

d) The plutonium is shipped in a package specifically authorized for the shipment of plutonium by air in the Certificate of Compliance for that package issued by the U.S. Nuclear Regulatory Commission.

Section 341.170 Records

a) Each licensee shall maintain for a period of two (2) years after shipment a record of each shipment of licensed material not exempt under Section 341.40, showing, where applicable:

1) Identification of the packaging by model number;

2) Verification that there are no defects in the packaging, as shipped which would prevent the package from meeting the standards of 10 CFR 71, Subparts E and F, revised as of January 1985, exclusive of subsequent amendments or editions;

3) Volume and identification of coolant;

4) Type and quantity of licensed material in each package, and the total quantity of each shipment;

5) Date of the shipment;

6) Name and address of the transferee;

7) Address to which the shipment was made; and

8) Results of the determinations required by Section 341.130.

b) The licensee shall make available to the Department for inspection, at any time during shipment or upon three days notice after shipment, all records required by this Part.

Section 341.180 Reports

The licensee shall report to the Department within 30 days:

a) Any instance in which a reduction in the effectiveness of any authorized packaging impacts upon compliance with 10 CFR 71, Subparts E and F, revised as of January 1985, exclusive of subsequent amendments or editions; and

b) Details of any defects in the packaging after first use impacting upon compliance with 10 CFR 71, Subparts E and F, with the means employed to repair the defects and prevent their recurrence.

Section 341.190 Advance Notification of Transport of Nuclear Waste

a) Licensees who transport radioactive waste or deliver radioactive waste to a carrier for transport outside of the confines of the licensee's facility or other place of use or storage, must provide advance notification of such transport to the governor, or governor's designee* in accordance with subsection (b). Such notification shall include the governors or governors' designees of all states through which the radioactive waste is to be transported.

*AGENCY NOTE: A list of the mailing addresses of the governors and governors' designees is available upon request from the Director, Office of State Programs, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.

b) Advance notification is required only when:

1) The nuclear waste is required to be in Type B packaging for transportation;

2) The nuclear waste is being transported to, through, or across state boundaries to a disposal site or to a collection point for transport to a disposal site;

3) The quantity of licensed material in a single package exceeds:

A) 5,000 curies (185 TBq) of special form radionuclides;

B) 5,000 curies (185 TBq) of uncompressed gases of argon-41, krypton-85m, krypton-87, xenon-131m, or xenon-135;

C) 50,000 curies (1.85 PBq) of argon-37, or of uncompressed gases of krypton-85 or xenon-133, or of hydrogen-3 as a gas, as luminous paint, or adsorbed on solid material;

D) 20 curies (740 GBq) of other non-special form radionuclides for which A2 is less than or equal to four (4) curies (148 GBq); or

E) 200 curies (7.4 TBq) of other non-special form radionu- clides for which A2 is greater than four (4) curies (148 GBq).

c) Each advance notification required by Section 341.190(a) shall contain the following information:

1) The name, address, and telephone number of the shipper, carrier, and receiver of the shipment;

2) A description of the nuclear waste contained in the shipment as required by the regulations of the U.S. DOT, 49 CFR 172.202 and 172.203(d), revised as of November 1, 1984*;

*AGENCY NOTE: Requirements contained in subsequent amendments or editions of 49 CFR 172 are not incorporated into this rule. A copy of 49 CFR 172 is available for public inspection at the Department of Nuclear Safety.

3) The point of origin of the shipment and the seven-day period during which departure of the shipment is estimated to occur;

4) The seven-day period during which arrival of the shipment at state boundaries is estimated to occur;

5) The destination of the shipment, and the seven-day period during which arrival of the shipment is estimated to occur; and

6) A point of contact, with a telephone number, for current shipment information.

d) The notification required by Section 341.190(a) shall be made in writing to the office of the Governor or Governor's designee and to the Department. A notification delivered by mail must be postmarked at least seven days before the beginning of the seven- day period during which departure of the shipment is estimated to occur. A notification delivered by messenger must reach the office of the governor, or governor's designee, at least four (4) days before the beginning of the seven-day period during which departure of the shipment is estimated to occur. A copy of the notification shall be retained by the licensee for one (1) year.

e) The licensee shall notify the Governor, or Governor's designee, and the Department of any changes to schedule information provided pursuant to Section 341.190(a). Such notification shall be by telephone to a responsible individual in the Office of the Governor, or Governor's designee, and in the Department. The licensee shall maintain for one (1) year a record of the name of the individual contacted.

f) Each licensee who cancels a nuclear waste shipment, for which advance notification has been sent, shall send a cancellation notice to the Governor, or Governor's designee, and to the Department. A copy of the notice shall be retained by the licensee for one (1) year.

Section 341.200 Quality Assurance Requirements

a) Each person licensed pursuant to this Part shall establish, maintain, and execute a quality assurance program to verify, by procedures such as checking, auditing, and inspection, that deficiencies, deviations, and defective material and equipment relating to the shipment of packages containing radioactive materials are promptly identified and corrected. Prior to the use of any package for the shipment of radioactive material, each licensee shall obtain Department approval of its quality assurance program. Such approval shall be in accordance with the U.S. Nuclear Regulatory Commission standards contained in their Regulatory Guide on Quality Assurance, Reg. Guide #7.10, Establishing Quality Assurance Programs for Packaging used in the Transport of Radioactive Material, published January, 1983, exclusive of subsequent amendments or editions. A copy of the Regulatory Guide is available for public inspection at the Department of Nuclear Safety.

b) Each person licensed pursuant to this Part shall document the quality assurance program by written procedures or instructions and shall carry out the program in accordance with those procedures throughout the period during which packaging is used. The licensee shall identify the material and components to be covered by the quality assurance program.

c) A person licensed pursuant to this Part shall maintain sufficient written records to demonstrate compliance with the quality assurance program. Records pertaining to the use of a package for shipment of radioactive material must be retained for a period of two (2) years after shipment.

(Source: Amended at 11 Ill. Reg. 5219, effective March 13, 1987)

SECTION 341. APPENDIX A DETERMINATION OF A1 and A2

a) Single radionuclides.

1) For a single radionuclide of known identity, the values of A1 and A2 are taken from Table A-1 if listed there. The values of A1 and A2 in Table A-1 are also applicable for radionuclides contained in alpha neutron or gamma neutron sources.

2) For any single radionuclide whose identity is known but which is not listed in Table A-1, the values of A1 and A2 are determined according to the following procedure:

A) If the radionuclide emits only one type of radiation, A1 is determined according to the rules in paragraphs (i), (ii), (iii), and (iv) of this paragraph. For radionuclides emitting different kinds of radiation, A1 is the most restrictive value of those determined for each kind of radiation. However, in both cases, A1 is restricted to a maximum of 1000 Ci (37 TBq). If a parent nuclide decays into a shorter-lived daughter with a half-life not greater than ten (10) days, A1 is calculated for both the parent and the daughter, and the more limiting of the two (2) values is assigned to the parent nuclide.

i) For gamma emitters, A1 is determined by the expression:

A1 = 9 curies K

where K is the gamma-ray constant, corresponding to the dose in R/h at 1 m per Ci; the number 9 results from the choice of 1 rem/h at a distance of 3 m as the reference dose-equivalent rate.

ii) For X-ray emitters, A1 is determined by the atomic number of the nuclide;

for Z less than or equal to 55, A1=1000 Ci (37 TBq)

for Z greater than 55, A1=200 Ci (7.4 TBq)

where Z is the atomic number of the nuclide.

iii) For beta emitters, A1 is determined by the maximum beta energy (Emax) according to Table A- 2;

iv) For alpha emitters, A1 is determined by the expression:

A1 = 1000 A3

where A3 is the value listed in Table A-3;

B) A2 is the more restrictive of the following two (2) values:

i) The corresponding A1; and

ii) The value A3 obtained from Table A-3.

3) For any single radionuclide whose identity is unknown, the value of A1 is taken to be 2 Ci (74 GBq) and the value of A2 is taken to be 0.002 Ci (74 MBq). However, if the atomic number of the radionuclide is known to be less than 82, the value of A1 is taken to be 10 Ci (370 GBq) and the value of A2 is taken to be 0.4 Ci (14.8 GBq).

b) Mixtures of radionuclides, including radioactive decay chains.

1) For mixed fission products the following activity limits may be assumed if a detailed analysis of the mixture is not carried out:

A1 = 10 Ci (370 GBq)

A2 = 0.4 Ci (14.8 GBq)

2) A single radioactive decay chain is considered to be a single radionuclide when the radionuclides are present in their naturally occurring proportions and no daughter nuclide has a half-life either longer than ten (10) days or longer than that of the parent nuclide. The activity to be taken into account and the A1 or A2 value from Table A-1 to be applied are those corresponding to the parent nuclide of that chain. When calculating A1 or A2 values, radiation emitted by daughters must be considered. However, in the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than ten (10) days or greater than that of the parent nuclide, the parent and daughter nuclides are considered to be mixtures of different nuclides.

3) In the case of a mixture of different radionuclides, where the identity and activity of each radionuclide are known, the permissible activity of each radionuclide R1, R2...Rn is such that F1 + F2 +...Fn is greater than unity, where

F1 = Total activity of R1 Ai(R1)

F2 = Total activity of R2 Ai(R2)

Fn = Total Activity of Rn Ai(Rn)

Ai(R1, R2...Rn) is the value of A1 or A2 as appropriate for the nuclide R1, R2...Rn.

4) When the identity of each radionuclide is known but the individual activities of some of the radionuclides are not known, the formula given in subparagraph (3) is applied to establish the values of A1 or A2 as appropriate. All the radionuclides whose individual activities are not known (their total activity will, however, be known) are classed in a single group and the most restrictive value of A1 or A2 applicable to any one of them is used as the value of A1 or A2 in the denominator of the fraction.

5) Where the identity of each radionuclide is known but the individual activity of none of the radionuclides is known, the most restrictive value of A1 or A2 applicable to any one of the radionuclides present is adopted as the applicable value.

6) When the identity of none of the nuclides is known, the value of A1 is taken to be 2 Ci (74 GBq) and the value of A2 is taken to be 0.002 Ci (74 MBq). However, if alpha emitters are known to be absent, the value of A2 is taken to be 0.4 Ci (14.8 GBq).

(Source: Amended at 12 Ill. Reg. 2434, effective January 15, 1988)

SECTION 341. TABLE A

A1 and A2 VALUES FOR RADIONUCLIDES

(See Agency Notes At End Of Table)

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

227Ac Actinium (89) 1000 0.003 7.2 x 10

228Ac 10 4 2.2 x 106

105Ag Silver (47) 40 40 3.1 x 104

110mAg 7 7 4.7 x 103

111Ag 100 20 1.6 x 105

241Am Americium (95) 8 0.008 3.2

243Am 8 0.008 1.9 x 10-1

37Ar (compressed or Argon (18) 1000 1000 1.0 x 105 uncompressed)*

41Ar (uncompressed)* 20 20 4.3 x 107

41Ar (compressed)* 1 1 4.3 x 107

73As Arsenic (33) 1000 400 2.4 x 104

74As 20 20 1.0 x 105

76As 10 10 1.6 x 106

77As 300 20 1.1 x 106

211At Astatine (85) 200 7 2.1 x 106

193Au Gold (79) 200 200 9.3 x 105

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

196Au 30 30 1.2 x 105

198Au 40 20 2.5 x 105

199Au 200 25 2.1 x 105

131Ba Barium (56) 40 40 8.7 x 104

133Ba 40 10 4.0 x 102

140Ba 20 20 7.3 x 104

7Be Beryllium (4) 300 300 3.5 x 105

206Bi Bismuth (83) 5 5 9.9 x 104

207Bi 10 10 2.2 x 102

210Bi (RaE) 100 4 1.2 x 105

212Bi 6 6 1.5 x 107

249Bk Berkelium (97) 1000 1 1.8 x 103

77Br Bromine (35) 70 25 7.1 x 105

82Br 6 6 1.1 x 106

11C Carbon (6) 20 20 8.4 x 108

14C 1000 60 4.6

45Ca Calcium (20) 1000 25 1.9 x 104

47Ca 20 20 5.9 x 105

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

109Cd Cadmium (48) 1000 70 2.6 x 103

115mCd 30 30 2.6 x 104

115Cd 80 20 5.1 x 105

139Ce Cerium (58) 100 100 6.5 x 103

141Ce 300 25 2.8 x 104

143Ce 60 20 6.6 x 105

144Ce 10 7 3.2 x 103

249Cf Californium (98) 2 0.002 3.1

250Cf 7 0.007 1.3 x 102

252Cf 2 0.009 6.5 x 102

36Cl Chlorine (17) 300 10 3.2 x 10-2

38Cl 10 10 1.3 x 108

242Cm Curium (96) 200 0.2 3.3 x 103

243Cm 9 0.009 4.2 x 10

244Cm 10 0.01 8.2 x 10

245Cm 6 0.006 1.0 x 10-1

246Cm 6 0.006 3.6 x 10-1

56Co Cobalt (27) 5 5 3.0 x 104

57Co 90 90 8.5 x 103

58mCo 1000 1000 5.9 x 106

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

58Co 20 20 3.1 x 104

60Co 7 7 1.1 x 103

51Cr Chromium (24) 600 600 9.2 x 104

129Cs Cesium (55) 40 40 7.6 x 105

131Cs 1000 1000 1.0 x 105

134mCs 1000 10 7.4 x 106

134Cs 10 10 1.2 x 103

135Cs 1000 25 8.8 x 10-4

136Cs 7 7 7.4 x 104

137Cs 30 10 9.8 x 10

64Cu Copper (29) 80 25 3.8 x 106

67Cu 200 25 7.9 x 105

165Dy Dysprosium (66) 100 20 8.2 x 106

166Dy 1000 200 2.3 x 105

169Er Erbium (68) 1000 25 8.2 x 104

171Er 50 20 2.4 x 106

152mEu Europium (63) 30 30 2.2 x 106

152Eu 20 10 1.9 x 102

154Eu 10 5 1.5 x 102

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

155Eu 400 60 1.4 x 103

18F Fluorine (9) 20 20 9.3 x 107

52Fe Iron (26) 5 5 7.3 x 106

55Fe 1000 1000 2.2 x 103

59Fe 10 10 4.9 x 104

67Ga Gallium (31) 100 100 6.0 x 105

68Ga 20 20 4.0 x 107

72Ga 7 7 3.1 x 106

153Gd Gadolinium (64) 200 100 3.6 x 103

159Gd 300 20 1.1 x 106

68Ge Germanium (32) 20 10 7.0 x 103

71Ge 1000 1000 1.6 x 105

3H Hydrogen (1) see T-Tritium

181Hf Hafnium (72) 30 25 1.6 x 104

197mHg Mercury (80) 200 200 6.6 x 105

197Hg 200 200 2.5 x 105

203Hg 80 25 1.4 x 104

166Ho Holmium (67) 30 30 6.9 x 105

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

123I Iodine (53) 50 50 1.9 x 106

125I 1000 70 1.7 x 104

126I 40 10 7.8 x 104

129I 1000 2 1.6 x 10-4

131I 40 10 1.2 x 105

132I 7 7 1.1 x 107

133I 30 30 1.1 x 106

134I 8 8 2.7 x 107

135I 10 10 3.5 x 106

111In Indium (49) 30 25 4.2 x 105

113mIn 60 60 1.6 x 107

114mIn 30 20 2.3 x 104

115mIn 100 20 6.1 x 106

190Ir Iridium (77) 10 10 6.2 x 104

192Ir 20 10 9.1 x 103

194Ir 10 10 8.5 x 105

42K Potassium (19) 10 10 6.0 x 106

43K 20 10 3.3 x 106

85mKr (uncompressed)* Krypton (36) 100 100 8.4 x 106

85mKr (compressed)* 3 3 8.4 x 106

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

85Kr (uncompressed)* 1000 1000 4.0 x 102

85Kr (compressed)* 5 5 4.0 x 102

87Kr (uncompressed)* 20 20 2.8 x 107

87Kr (compressed)* 0.6 0.6 2.8 x 107

140La Lanthanum (57) 30 30 5.6 x 105

177Lu Lutetium (71) 300 25 1.1 x 105

MFP Mixed Fission 10 0.4 -- Products

28Mg Magnesium (12) 6 6 5.2 x 106

52Mn Manganese (25) 5 5 4.4 x 105

54Mn 20 20 8.3 x 103

56Mn 5 5 2.2 x 107

99Mo Molybdenum (42) 100 20 4.7 x 105

13N Nitrogen (7) 20 10 1.5 x 109

22Na Sodium (11) 8 8 6.3 x 103

24Na 5 5 8.7 x 106

93mNb Niobium (41) 1000 200 1.1 x 103

95Nb 20 20 3.9 x 104

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

97Nb 20 20 2.6 x 107

147Nd Neodymium (60) 100 20 8.0 x 104

149Nd 30 20 1.1 x 107

59Ni Nickel (28) 1000 900 8.1 x 10-2

63Ni 1000 100 4.6 x 10

65Ni 10 10 1.9 x 107

237Np Neptunium (93) 5 0.005 6.9 x 10-4

239Np 200 25 2.3 x 105

1850s Osmium (76) 20 20 7.3 x 103

1910s 600 200 4.6 x 104

191mOs 200 200 1.2 x 106

1930s 100 20 5.3 x 105

32P Phosphorus (15) 30 30 2.9 x 105

230Pa Protactinium (91) 20 0.8 3.2 x 104

231Pa 2 0.002 4.5 x 10-2

233Pa 100 100 2.1 x 104

201Pb Lead (82) 20 20 1.7 x 106

210Pb 100 0.2 8.8 x 10

212Pb 6 5 1.4 x 106

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

103Pd Palladium (46) 1000 700 7.5 x 104

109Pd 100 20 2.1 x 106

147Pm Promethium (61) 1000 25 9.4 x 102

149Pm 100 20 4.2 x 105

210Po Polonium (84) 200 0.2 4.5 x 103

142Pr Praseodymium (59) 10 10 1.2 x 104

143Pr 300 20 6.6 x 104

191Pt Platinum (78) 100 100 2.3 x 105

193mPt 200 200 2.0 x 105

197mPt 300 20 1.2 x 107

197Pt 300 20 8.8 x 105

238Pu Plutonium (94) 3 0.003 1.7 x 10

239Pu 2 0.002 6.2 x 10-2

240Pu 2 0.002 2.3 x 10-1

241Pu 1000 0.1 1.1 x 102

242Pu 3 0.003 3.9 x 10-3

223Ra Radium (88) 50 0.2 5.0 x 104

224Ra 6 0.5 1.6 x 105

226Ra 10 0.05 1.0

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

228Ra 10 0.05 2.3 x 102

81Rb Rubidium (37) 30 25 8.2 x 106

86Rb 30 30 8.1 x 104

87Rb Unlimited Unlimited 6.6 x 10-8

Rb (natural) Unlimited Unlimited 1.8 x 10-8

186Re Rhenium (75) 100 20 1.9 x 105

187Re Unlimited Unlimited 3.8 x 10-8

188Re 10 10 1.0 x 106

Re (natural) Unlimited Unlimited 2.4 x 10-8

103mRh Rhodium (45) 1000 1000 3.2 x 107

105Rh 200 25 8.2 x 105

222Rn Radon (86) 10 2 1.5 x 105

97Ru Ruthenium (44) 80 80 5.5 x 105

103Ru 30 25 3.2 x 104

105Ru 20 20 6.6 x 106

106Ru 10 7 3.4 x 103

35S Sulfur (16) 1000 60 4.3 x 104

122Sb Antimony (51) 30 30 3.9 x 105

124Sb 5 5 1.8 x 104

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

125Sb 40 25 1.4 x 103

46Sc Scandium (21) 8 8 3.4 x 104

47Sc 200 20 8.2 x 105

48Sc 5 5 1.5 x 106

75Se Selenium (34) 40 40 1.4 x 104

31Si Silicon (14) 100 20 3.9 x 107

147Sm Samarium (62) Unlimited Unlimited 2.0 x 10-8

151Sm 1000 90 2.6 x 10

153Sm 300 20 4.4 x 105

113Sn Tin (50) 60 60 1.0 x 104

119mSn 100 100 4.4 x 103

125Sn 10 10 1.1 x 105

85mSr Strontium (38) 80 80 3.2 x 107

85Sr 30 30 2.4 x 104

87mSr 50 50 1.2 x 107

89Sr 100 10 2.9 x 104

90Sr 10 0.4 1.5 x 102

91Sr 10 10 3.6 x 106

92Sr 10 10 1.3 x 107

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

T (uncompressed)* Tritium (1) 1000 1000 9.7 x 103

T (compressed)* 1000 1000 9.7 x 103

T (activated 1000 1000 9.7 x 103 luminous paint)

T (adsorbed on 1000 1000 9.7 x 103 solid carrier)

T (tritiated water) 1000 1000 9.7 x 103

T (other forms) 20 20 9.7 x 103

182Ta Tantalum (73) 20 20 6.2 x 103

160Tb Terbium (65) 20 10 1.1 x 104

96mTc Technetium (43) 1000 1000 3.8 x 107

96Tc 6 6 3.2 x 105

97mTc 1000 200 1.5 x 104

97Tc 1000 400 1.4 x 10-3

99mTc 100 100 5.2 x 106

99Tc 1000 25 1.7 x 10-2

125mTe Tellurium (52) 1000 100 1.8 x 104

127mTe 300 20 4.0 x 104

127Te 300 20 2.6 x 106

129mTe 30 10 2.5 x 104

129Te 100 20 2.0 x 107

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

131mTe 10 10 8.0 x 105

132Te 7 7 3.1 x 105

227Th Thorium (90) 200 0.2 3.2 x 104

228Th 6 0.008 8.3 x 102

230Th 3 0.003 1.9 x 10-2

231Th 1000 25 5.3 x 105

232Th Unlimited Unlimited 1.1 x 10-7

234Th 10 10 2.3 x 104

Th (natural) Unlimited Unlimited 2.2 x 10-7

Th (irradiated)** ----- ------ ------

200Tl Thallium (81) 20 20 5.8 x 105

201Tl 200 200 2.2 x 105

202Tl 40 40 5.4 x 104

204Tl 300 10 4.3 x 102

170Tm Thulium (69) 300 10 6.0 x 103

171Tm 1000 100 1.1 x 103

230U Uranium (92) 100 0.1 2.7 x 104

232U 30 0.03 2.1 x 10

233U 100 0.1 9.5 x 10-3

234U 100 0.1 6.2 x 10-3

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

235U 100 0.2 2.1 x 10-6

236U 200 0.2 6.3 x 10-5

238U Unlimited Unlimited 3.3 x 10-7

U (natural) Unlimited Unlimited (See Table A-4)

U (enriched) < 20% Unlimited Unlimited (See Table A-4)

U (enriched) 100 0.1 (See Table 20% or greater A-4)

U (depleted) Unlimited Unlimited (See Table A-4)

U (irradiated)*** ----- ----- -----

48V Vanadium (23) 6 6 1.7 x 105

181W Tungsten (74) 200 100 5.0 x 103

185W 1000 25 9.7 x 10-3

187W 40 20 7.0 x 105

127Xe (uncompressed)* Xenon (54) 70 70 2.8 x 104

127Xe (compressed)* 5 5 2.8 x 104

131mXe (compressed)* 10 10 1.0 x 105

131mXe (uncompressed)* 100 100 1.0 x 105

133Xe (uncompressed)* 1000 1000 1.9 x 105

133Xe (compressed)* 5 5 1.9 x 105

135Xe (uncompressed)* 70 70 2.5 x 105

Symbol of Element and A1(Ci) A2(Ci) Specific Radionuclide Atomic Number Activity (Ci/g)

135Xe (compressed)* 2 2 2.5 x 105

87Y Yttrium (39) 20 20 4.5 x 10

90Y 10 10 2.5 x 105

91mY 30 30 4.1 x 107

91Y 30 30 2.5 x 104

92Y 10 10 9.5 x 106

93Y 10 10 3.2 x 106

169Yb Ytterbium (70) 80 80 2.3 x 105

175Yb 400 25 1.8 x 105

65Zn Zinc (30) 30 30 8.0 x 103

69mZn 40 20 3.3 x 106

69Zn 300 20 5.3 x 107

93Zr Zirconium (40) 1000 200 3.5 x 10-3

95Zr 20 20 2.1 x 104

97Zr 20 20 2.0 x 106

*AGENCY NOTE: For the purpose of Table A, compressed gas means a gas at a pressure which exceeds the ambient atmospheric pressure at the location where the containment system was closed.

**AGENCY NOTE: The values of A1 and A2 must be calculated in accordance with the procedure specified in Appendix A, paragraph b(3), taking into account the activity of the fission products and of the uranium-233 in addition to that of the thorium.

***AGENCY NOTE: The values of A1 and A2 must be calculated in accordance with the procedure specified in Appendix A, paragraph b(3), taking into account the activity of the fission products and plutonium isotopes in addition to that of the uranium.

SECTION 341. TABLE B

RELATIONSHIP BETWEEN A1 AND Emax FOR BETA EMITTERS

Emax (MeV) A1 (Ci)

less than 0.5 1000

0.5 - less than 1.0 300

1.0 - less than 1.5 100

1.5 - less than 2.0 30

greater than or equal to 2.0 10

SECTION 341. TABLE C

RELATIONSHIP BETWEEN A3 AND THE ATOMIC NUMBER

OF THE RADIONUCLIDE

A3

Atomic Half-life less Half-life 1000 days Half-life greater

Number than 1000 days to 106 years than 106 years

1 to 81 3 Ci .05 Ci 3 Ci

82 and above .002 Ci .002 Ci 3 Ci

SECTION 341. TABLE D

ACTIVITY-MASS RELATIONSHIPS FOR URANIUM/THORIUM

Thorium and Specific Activity Uranium Enrichment* wt % 235U present Ci/g g/Ci

0.45 5.0 x 10-7 2.0 x 106

0.72 (natural) 7.06 x 10-7 1.42 x 106

1.0 7.6 x 10-7 1.3 x 106

1.5 1.0 x 10-6 1.0 x 106

5.0 2.7 x 10-6 3.7 x 105

10.0 4.8 x 10-6 2.1 x 105

20.0 1.0 x 10-5 1.0 x 105

35.0 2.0 x 10-5 5.0 x 104

50.0 2.5 x 10-5 4.0 x 104

90.0 5.8 x 10-5 1.7 x 104

93.0 7.0 x 10-5 1.4 x 104

95.0 9.1 x 10-5 1.1 x 104

Natural Thorium 2.2 x 10-7 4.6 x 106

*The figures for uranium include representative values for the activity of the uranium-234 which is concentrated during the enrichment process. The activity for thorium includes the equilibrium concentration of thorium-228.