Rule 391-3-17-.06. Transportation of Radioactive Material

1. (1) General.

   1. (a) Purpose. The Regulations in this Rule, 391-3-17-.06, establish requirements for packaging, preparation for shipment, and transportation of radioactive material.
   2. (b) Scope. This Rule applies to any licensee authorized by specific or general license issued by the Director, Agreement State, or NRC to receive, possess, use, or transfer licensed material to a carrier for transport of the material outside the site of usage as specified in the license, or transports that material on public highways or public access roads. No provision of this part authorizes possession of licensed material.
2. (2) 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 Director or as exempted in (4).

3. (3) Definitions. As used in this Rule, the following definitions apply:

   1. (a) "A1" and "A2" mean, respectively, the maximum activity of special form radioactive material (A1) and the maximum activity of radioactive material, other than special form material, LSA, and SCO material (A2), permitted in a Type A package.
   2. (b) "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.
   3. (c) "Certificate holder" means a person who has been issued a certificate of compliance or other package approval by the U.S. Nuclear Regulatory Commission.
   4. (d) "Certificate of Compliance (CoC)" means the certificate issued by the U.S Nuclear Regulatory Commission, which approves the design of a package for the transportation of radioactive material.
   5. (e) "Close reflection by water" means immediate contact by water of sufficient thickness for maximum reflection of neutrons.
   6. (f) "Closed transport vehicle" means a transport vehicle equipped with a securely attached exterior enclosure that during normal transportation restricts the access of unauthorized persons to the cargo space containing the radioactive material. The enclosure may be either temporary or permanent but shall limit access from top, sides, and ends. In the case of packaged materials, it may be of the "see-through" type.
   7. (g) "Consignment" means each shipment of a package or groups of packages or load of radioactive material offered by a shipper for transport.
   8. (h) "Containment system" means the assembly components of the packaging intended to retain the radioactive material during transport.

   9. (i) "Conveyance" means:

      1. 1. For transport by public highway or rail any transport vehicle or large freight container;
      2. 2. For transport by water any vessel, or any hold, compartment, or defined deck area of a vessel including any transport vehicle on board the vessel; and
      3. 3. For transport by any aircraft.
   10. (j) "Criticality Safety Index (CSI)" means the dimensionless number (rounded up to the next tenth) assigned to and placed on the label of a fissile material package, to designate the degree of control of accumulation of packages, overpacks or freight containers containing fissile material during transportation. Determination of the criticality safety index is described in 391-3-17-.06(11) and (12) and 10 CFR 71.59. The criticality safety index for an overpack, freight container, consignment or conveyance containing fissile material packages is the arithmetic sum of the criticality safety indices of all the fissile material packages contained within the overpack, freight container, consignment or conveyance.
   11. (k) "Deuterium" means deuterium and any deuterium compounds, including heavy water, in which the ratio of deuterium atoms to hydrogen atoms exceeds 1:5,000.
   12. (l) "DOT" means the U.S. Department of Transportation.
   13. (m) "Exclusive use" 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. The consignor and the carrier must ensure that any loading or unloading is performed by personnel having radiological training and resources appropriate for safe handling of the consignment. The consignor must issue specific instructions, in writing, for maintenance of exclusive use shipment controls, and include them with the shipping paper information provided to the carrier by the consignor.1
   14. (n) "Fissile material" means the radionuclides uranium-233, uranium-235, plutonium-239, and plutonium-241, or any combination of these radionuclides. Fissile material means the fissile nuclides themselves, not material containing fissile nuclides. Neither natural nor depleted uranium is fissile material.2 Unirradiated natural uranium or depleted uranium that has been irradiated in thermal reactors only are not included in this definition. Certain exclusions from fissile material controls are provided in 10 CFR 71.15.
   15. (o) "Graphite" means graphite with a boron equivalent content less than five (5) parts per million and density greater than 1.5 grams per cubic centimeter.
   16. (p) "Indian Tribe" means an Indian or Alaska Native Tribe, band, nation, pueblo, village, or community that the Secretary of the Interior acknowledges to exist as an Indian Tribe pursuant to the Federally Recognized Indian Tribe List Act of 1994, 25 U.S.C. 479a.
   17. (q) "Licensed material" means byproduct, source, or special nuclear material received, possessed, used, or transferred under a general or specific license issued by the U.S. Nuclear Regulatory Commission or an Agreement State pursuant to the regulations in 10 CFR or this Chapter, respectively.

   18. (r) "Low specific activity material" means radioactive material with limited specific activity which is nonfissile or is excepted under 391-3-17-.06(4)(f), and which satisfies the descriptions and limits set forth below. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. The LSA material must be in one of three groups:

       1. 1. LSA-I

          1. (i) Uranium and thorium ores, concentrates of uranium and thorium ores, and other ores containing naturally occurring radionuclides that are intended to be processed for the use of these radionuclides; or
          2. (ii) Natural uranium, depleted uranium, natural thorium or their compounds or mixtures, provided they are unirradiated and in solid or liquid form; or
          3. (iii) Radioactive material, other than fissile material, for which the A2 value is unlimited; or
          4. (iv) Other radioactive material in which the activity is distributed throughout and the estimated average specific activity does not exceed 30 times the value for exempt material activity concentration determined in accordance with 391-3-17-.06(23).

       2. 2. LSA-II

          1. (i) Water with tritium concentration up to 20.0 Ci/L (0.8 TBq/liter); or
          2. (ii) Other radioactive material in which the activity is distributed throughout and the estimated average specific activity does not exceed 10-4 A2/g for solids and gases, and 10-5 A2/g for liquids.

       3. 3. LSA-III. Solids (e.g., consolidated wastes, activated materials), excluding powders, that satisfy the requirements of 10 CFR 71.77, in which:

          1. (i) The radioactive material is distributed throughout a solid or a collection of solid objects, or is essentially uniformly distributed in a solid compact binding agent (such as concrete, bitumen, ceramic, etc);
          2. (ii) The radioactive material is relatively insoluble, or it is intrinsically contained in a relatively insoluble material, so that, even under loss of packaging, the loss of radioactive material per package by leaching, when placed in water for seven days, would not exceed 0.1 A2; and
          3. (iii) The estimated average specific activity of the solid, excluding any shielding material, does not exceed 2x10-3 A2/g.
   19. (s) "Low toxicity alpha emitters" means natural uranium, depleted uranium, natural thorium; uranium-235, uranium-238, thorium-232, thorium-228 or thorium-230 when contained in ores or physical or chemical concentrates or tailings; or alpha emitters with a half-life of less than 10 days.
   20. (t) "Maximum normal operating pressure" means the maximum gauge pressure that would develop in the containment system in a period of one year under the heat condition specified in 10 CFR 71.71(c)(1), in the absence of venting, external cooling by an ancillary system, or operational controls during transport.
   21. (u) "Natural thorium" means thorium with the naturally occurring distribution of thorium isotopes (essentially 100 weight percent thorium-232).
   22. (v) "Normal form radioactive material" means radioactive material that has not been demonstrated to qualify as "special form radioactive material."
   23. (w) "Nuclear waste" means a quantity of source, byproduct or special nuclear material3 required to be in US Nuclear Regulatory Commission-approved specification packaging while transported to, through or across a state boundary to a disposal site, or to a collection point for transport to a disposal site.
   24. (x) "Optimum interspersed hydrogenous moderation" means the presence of hydrogenous material between packages to such an extent that the maximum nuclear reactivity results.

   25. (y) "Package" means the packaging together with its radioactive contents as presented for transport.

       1. 1. "Fissile material package or Type AF package, Type BF package, Type B(U)F package, or Type B(M)F package" means a fissile material packaging together with its fissile material contents.
       2. 2. "Type A package" means a Type A packaging together with its radioactive contents. A Type A package is defined and must comply with the DOT regulations in 49 CFR Part 173 .
       3. 3. "Type B package" means a Type B packaging together with its radioactive contents. On approval, a Type B package design is designated by NRC as B(U) unless the package has a maximum normal operating pressure of more than 700 kPa (100 lb/in2) gauge or a pressure relief device that would allow the release of radioactive material to the environment under the tests specified in 10 CFR Part 71 (hypothetical accident conditions), in which case it will receive a designation B(M). B(U) refers to the need for unilateral approval of international shipments; B(M) refers to the need for multilateral approval of international shipments. 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 Part 173. A Type B package approved before September 6, 1983, was designated only as Type B. Limitations on its use are specified in .06(8).
   26. (z) "Packaging" means the assembly of components necessary to ensure compliance with the packaging requirements of this Rule. 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.
   27. (aa) "Regulations of the U.S. Department of Transportation" means the regulations in 49 CFR Parts 100-189 and Parts 390-397.
   28. (bb) "Regulations of the U.S. Nuclear Regulatory Commission" means the regulations in 10 CFR 71 for purposes of this Rule.

   29. (cc) "Special form radioactive material" means radioactive material that satisfies the following conditions:

       1. 1. It is either a single solid piece or is contained in a sealed capsule that can be opened only by destroying the capsule;
       2. 2. The piece or capsule has at least one dimension not less than 5 millimeters (0.2 in.); and
       3. 3. It satisfies the requirements specified by the Nuclear Regulatory Commission in 10 CFR 71.75. A special form encapsulation designed in accordance with the requirements of 10 CFR 71.4 in effect on June 30, 1983 (see 10 CFR 71, revised as of January 1, 1983), and constructed prior to July 1, 1985, may continue to be used. A special form encapsulation designed in accordance with the Nuclear Regulatory Commission requirements in 10 CFR 71.4 in effect on March 31, 1996 (see 10 CFR 71, revised as of January 1, 1996), and constructed prior to April 1, 1998, may continue to be used. A special form material that was successfully tested before September 10, 2015 in accordance with the requirements of 10 CFR 71.75(d) in effect before September 10, 2015 may continue to be used. Any other special form must meet requirements of this definition applicable at the time of its design or construction.
   30. (dd) "Specific activity" of a radionuclide means the radioactivity of a 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.
   31. (ee) "Spent nuclear fuel or Spent fuel" means fuel that has been withdrawn from a nuclear reactor following irradiation, has undergone at least one (1) year's decay since being used as a source of energy in a power reactor, and has not been chemically separated into its constituent elements by reprocessing. Spent fuel includes the special nuclear material, byproduct material, source material, and other radioactive materials associated with fuel assemblies.

   32. (ff) "Surface Contaminated Object (SCO)" means a solid object that is not itself classed as radioactive material, but which has radioactive material distributed on any of its surfaces. SCO must be in one of two groups with surface activity not exceeding the following limits:

       1. 1. SCO-I: A solid object on which:

          1. (i) The non-fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 10-4 microcurie/cm2 (4 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 10-5 microcurie/cm2 (0.4 Bq/cm2) for all other alpha emitters;
          2. (ii) The fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 1.0 microcurie/cm2 (4x104 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 0.1 microcurie/cm2 (4x103 Bq/cm2) for all other alpha emitters; and
          3. (iii) The non-fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 1.0 microcurie/cm2 (4x104 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 0.1 microcurie/cm2 (4x103 Bq/cm2) for all other alpha emitters.

       2. 2. SCO-II: A solid object on which the limits for SCO-I are exceeded and on which:

          1. (i) The non-fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 10-2 microcurie/cm2 (400 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 10-3 microcurie/cm2 (40 Bq/cm2) for all other alpha emitters;
          2. (ii) The fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 20 microcurie/cm2 (8x105 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 2 microcurie/cm2 (8x104 Bq/cm2) for all other alpha emitters; and
          3. (iii) The non-fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 20 microcurie/cm2 (8x105 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 2 microcurie/cm2 (8x104 Bq/cm2) for all other alpha emitters.
   33. (gg) "Transport index" means the dimension-less number (rounded up to the next tenth) placed on the label of a package, to designate the degree of control to be exercised by the carrier during transportation. The transportation index is the number expressing the maximum radiation level in millirem per hour at 1 meter from the external surface of the package.
   34. (hh) "Tribal official" means the highest ranking individual that represents Tribal leadership, such as the Chief, President, or Tribal Council leadership.
   35. (ii) "Type A package" means a packaging that, together with its radioactive contents limited to A1 or A2 as appropriate, meets the requirements of 49 CFR 173.410 and 173.412 and is designed to retain the integrity of containment and shielding required by this Rule under normal conditions of transport as demonstrated by the tests set forth in 49 CFR 173.465 or 173.466, as appropriate.
   36. (jj) "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 Table 4, "A1 and A2 Values for Radionuclides" or may be determined by procedures described in (23) of this Rule.
   37. (kk) "Type B package" is defined in Rule 391-3-17-.01(2)(ttt).
   38. (ll) "Type B packaging" means a packaging designed to retain the integrity of containment and shielding when subjected to the normal conditions of transport and hypothetical accident test conditions set forth in 10 CFR Part 71.
   39. (mm) "Type B quantity" means a quantity of radioactive material greater than a Type A quantity.
   40. (nn) "Unirradiated uranium" means uranium containing not more than 2x103 Bq of plutonium per gram of uranium-235, not more than 9x106 Bq of fission products per gram of uranium-235, and not more than 5x10-3 grams of uranium-236 per gram of uranium-235.

   41. (oo) "Uranium-natural, depleted, enriched" means:

       1. 1. Natural uranium means uranium (which may be chemically separated) with the naturally occurring distribution of uranium isotopes (approximately 0.711 weight percent uranium-235, and the remainder by weight essentially uranium-238).
       2. 2. Depleted uranium means uranium containing less uranium-235 than the naturally occurring distribution of uranium isotopes.
       3. 3. Enriched uranium means uranium containing more uranium-235 than the naturally occurring distribution of uranium isotopes.

   42. (pp) "Contamination" means the presence of a radioactive substance on a surface in quantities in excess of 0.4 Bq/cm2 (1x10-5 µCi/cm2) for beta and gamma emitters and low toxicity alpha emitters, or 0.04 Bq/cm2 (1x10-6 µCi/cm2) for all other alpha emitters.

       1. 1. Fixed contamination means contamination that cannot be removed from a surface during normal conditions of transport
       2. 2. Non-fixed contamination means contamination that can be removed from a surface during normal conditions of transport

4. (4) Exemptions.

   1. (a) Common and contract carriers, freight forwarders, and warehousemen who are subject to the requirements of the U.S. Department of Transportation (DOT) in 49 CFR 170 through 189 or the U.S. Postal Service in the Postal Service Manual (Domestic Mail Manual), Section C-023.9.0, and the U.S. Postal Service, are exempt from the requirements of this Rule and as stated in 10 CFR 30.13 to the extent that they transport or store radioactive material in the regular course of their carriage for others or storage incident thereto. Common and contract carriers who are not subject to the requirements of the U.S. Department of Transportation or U.S. Postal Service are subject to (2) of this Rule and other applicable requirements of these Regulations.
   2. (b) Any licensee is exempt from the requirements of this Rule 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 per gram (70 Bq/gm).
   3. (c) Any physician licensed by Georgia to dispense drugs in the practice of medicine is exempt from Rule .06 with respect to transport by the physician of licensed material for use in the practice of medicine. However, any physician operating under this exemption must be licensed under Rule .05.

   4. (d) A licensee is exempt from the requirements of Rule .06 with respect to shipment or carriage of the following low-level materials:

      1. 1. Natural material and ores containing naturally occurring radionuclides that are either in their natural state, or have only been processed for purposes other than for the extraction of the radionuclides, and which are not intended to be processed for use of these radionuclides, provided the activity concentration of the material does not exceed 10 times the applicable radionuclide activity concentration values specified in Table 5 and 7.
      2. 2. Materials for which the activity concentration is not greater than the activity concentration values specified in Table 5 and 7, or for which the consignment activity is not greater than the limit for an exempt consignment found in Table 5 and 7.
      3. 3. Non-radioactive solid objects with radioactive substances present on any surfaces in quantities not in excess of the levels cited in the definition of contamination in 391-3-17-.06(3)(pp).

   5. (e) A licensee is exempt from the requirements of Rule .06, other than .06(5) and .06(17), with respect to shipment or carriage of the following packages, providing the packages do not contain any fissile material, or the material is exempt from classification as fissile material in .06(4)(f):

      1. 1. A package that contains no more than a Type A quantity of radioactive material;
      2. 2. A package transported within the United States that contains no more than 20 Ci (0.74 TBq) of special form plutonium-244; or
      3. 3. A package contains LSA or SCO radioactive material, provided that the LSA or SCO material has an external radiation dose of less than or equal to 1 rem/hr (10 mSv/hr) at a distance of 3 meters from the unshielded material or that the package contains only LSA-I or SCO-I material.

   6. (f) Fissile material meeting the requirements of at least one of the following six paragraphs in this part are exempt from classification as fissile material and from the fissile material package standards of 10 CFR 71.55 and 71.59, but are subject to all other requirements of this part, except as noted.

      1. 1. Individual package containing two (2) grams or less of fissile material.
      2. 2. Individual or bulk packaging containing fifteen (15) grams or less of fissile material provided the package has at least 200 grams of solid nonfissile material for every gram of fissile material. Lead, beryllium, graphite, and hydrogenous material enriched in deuterium may be present in the package but must not be included in determining the required mass for solid nonfissile material.
      3. 3. Low concentrations of solid fissile material commingled with solid nonfissile material, provided that (i) there is at least 2,000 grams of solid nonfissile material for every gram of fissile material, and (ii) there is no more than 180 grams of fissile material distributed within 360 kg of contiguous nonfissile material. Lead, beryllium, graphite, and hydrogenous material enriched in deuterium may be present in the package but must not be included in determining the required mass for solid nonfissile material.
      4. 4. Uranium enriched in uranium-235 to a maximum of one (1) percent by weight, and with a total plutonium and uranium-233 content of up to one (1) percent of the mass of uranium-235, provided that the mass of any beryllium, graphite, and hydrogenous material enriched in deuterium constitutes less than five (5) percent of the uranium mass, and that the fissile material is distributed homogeneously and does not form a lattice arrangement within the package.
      5. 5. Liquid solutions of uranyl nitrate enriched in uranium-235 to a maximum of two (2) percent by mass, with a total plutonium and uranium-233 content not exceeding 0.002 percent of the mass of uranium, and with a minimum nitrogen to uranium atomic ratio (N/U) of 2. The material must be contained in at least a DOT Type A package.
      6. 6. Packages containing, individually, a total plutonium mass of not more than 1,000 grams, of which not more than twenty (20) percent by mass may consist of plutonium-239, plutonium-241, or any combination of these radionuclides.

5. (5) Transportation of Licensed Material.

   1. (a) Each licensee who transports licensed material outside the site of usage, as specified in a Division license, or where transport is on public highway, or public access road, or who delivers licensed material to a carrier for transport, shall:

      1. 1. Comply with the applicable requirements, appropriate to the mode of transport, of the regulations of the US Department of Transportation (DOT).

         1. (i) The licensee shall particularly note DOT regulations in the following areas:

            1. (I) Packaging - 49 CFR Part 173, Subparts A and B and I.
            2. (II) Marking and Labeling - 49 CFR Part 172 : Subpart D, and §§ 49 CFR 172.400 through 172.407, §§ 172.436 through 172.440 of Subpart E.
            3. (III) Placarding - 49 CFR Part 172 : Subpart F, especially §§ 172.500 through 172.519, 172.556 and Appendices B and C.
            4. (IV) Accident Reporting - 49 CFR Part 171: §§ 171.15 and 171.16.
            5. (V) Shipping Papers and Emergency Information - 49 CFR Part 172, Subpart C and Subpart G.
            6. (VI) Hazardous material employee training - 49 CFR Part 172: Subpart H.
            7. (VII) Security Plans - 49 CFR Part 172: Subpart I.
            8. (VIII) Hazardous material shipper/carrier registration - 49 CFR Part 107 : Subpart G.

         2. (ii) The licensee shall also note DOT regulations pertaining to the following modes of transportation:

            1. (I) Rail - 49 CFR Part 174, Subparts A through D and K.
            2. (II) Air - 49 CFR Part 175.
            3. (III) Vessel - 49 CFR Part 176, Subparts A through F and M.
            4. (IV) Public Highway - 49 CFR Part 177 and Parts 390 through 397.
      2. 2. Assure that any special instructions needed to safely open the package are sent to or have been made available to the consignee in accordance with Rule 391-3-17-.03(12)(f).
   2. (b) If, for any reason, the regulations of the DOT are not applicable to a shipment of licensed material, the licensee shall conform to the standards and requirements of 49 CFR Parts 170-189 appropriate to the mode of transport to the same extent as if the shipment was subject to the regulations.

6. (6) General Licenses for Carriers.

   1. (a) A general license is hereby issued to any common or contract carrier not exempt under (4) to receive, possess, transport, and store radioactive material in the regular course of their carriage for others or storage incident thereto, provided the transportation and storage is in accordance with the applicable requirements, appropriate to the mode of transport, of the DOT insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting.4
   2. (b) A general license is hereby issued to any private carrier to transport radioactive material, provided the transportation is in accordance with the applicable requirements, appropriate to the mode of transport, of the DOT insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting.
   3. (c) Persons who transport radioactive material pursuant to the general licenses in (6)(a) or (b) are exempt from the requirements of Rules 391-3-17-.03 and .07 to the extent that they transport radioactive material.

7. (7) General License: NRC-Approved Packages.

   1. (a) A general license is hereby issued to any licensee 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 (NRC).

   2. (b) Each licensee issued a general license under .06(7)(a) shall:

      1. 1. Possess a copy of the specific license, certificate of compliance, or other approval of the package and 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. 2. Comply with the terms and conditions of the license, certificate, or other approval by the Nuclear Regulatory Commission, as applicable, and the applicable requirements of this Rule;
      3. 3. Submit in writing before the first use of the package to: ATTN: Document Control Desk, Director, Division of Fuel Management, Office of Nuclear Material Safety and Safeguards, using an appropriate method listed in 10 CFR 71.71(a), the licensee's name and license number and the package identification number specified in the package approval.
   3. (c) This general license applies only to a licensee who has a quality assurance program required by the Georgia Department of Natural Resources Radioactive Materials Program satisfying the provisions of (22).
   4. (d) The general license in (7)(a) applies only when the package approval authorizes use of the package under this general license.
   5. (e) For a Type B or fissile material package the design of which was approved by NRC before April 1, 1996 the general license is subject to additional restrictions of 10 CFR 71.19.
8. (8) [Reserved].

9. (9) General License: DOT Specification Container.

   1. (a) A general license is issued to any licensee of the Division to transport, or to deliver to a carrier for transport, licensed material in a specification container for fissile material or for a Type B quantity of radioactive material as specified in 49 CFR Parts 173 and 178.

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

      1. 1. Has a copy of the specification;
      2. 2. Complies with the terms and conditions of the specification and the applicable requirements of this Rule; and
      3. 3. Has a quality assurance program required by (22).
   3. (c) The general license in (9)(a) is subject to the limitation that the specification container may not be used for a shipment to a location outside the United States, except by multilateral approval, as defined in DOT regulations at 49 CFR 173.403.

10. (10) General License: Use of Foreign-Approved Package.

    1. (a) A general license is issued to any licensee of the Division 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 DOT as meeting the applicable requirements of 49 CFR 171.23.
    2. (b) This general license applies only to international shipments.

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

       1. 1. Has a copy of the applicable certificate, the revalidation, and the drawings and other documents referenced in the certificate relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment;
       2. 2. Complies with the terms and conditions of the certificate and revalidation and with the applicable requirements of this Rule; and
       3. 3. Has a quality assurance program approved by the Georgia Department of Natural Resources, Environmental Protection Division, Radioactive Materials Program satisfying the requirements of (22).

11. (11) General License: Fissile Material, Limited Quantity per Package.

    1. (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 in accordance with this section. The material must be contained in a Type A package. The Type A package must also meet the DOT requirements of 49 CFR 173.417(a).
    2. (b) This general license applies only to a licensee who has a quality assurance program required by (22).
    3. (c) This general license applies only when a package contains no more than a Type A quantity of fissile material and contains less than 500 grams total of beryllium, graphite, or hydrogenous material enriched in deuterium.

    4. (d)

       1. 1.

          This general license applies only to packages containing fissile material that are labeled with a Criticality Safety Index (CSI), defined as

          

          where the values of X, Y, and Z used in the CSI equation must be taken from Tables 1 or 2, as appropriate. If Table 2 is used to obtain the value of X, then the values for the terms for uranium-233 and plutonium must be assumed to be zero. Table 1 values for X, Y, and Z must be used to determine the CSI if:

          1. i. Uranium-233 is present in the package;
          2. ii. The mass of plutonium exceeds one (1) percent of the mass of uranium-235;
          3. iii. The uranium is of unknown uranium-235 enrichment or greater than 24 weight percent enrichment; or
          4. iv. Substances having a moderating effectiveness (i.e., an average hydrogen density greater than water) (e.g., certain hydrocarbon oils or plastics) are present in any form, except as polyethylene used for packing or wrapping.
       2. 2. In all cases, the Criticality Safety Index must be rounded up to one decimal place and may not exceed 10.0.

       3. 3. For a shipment of multiple packages containing fillies material, the sum of the CSIs must be less than or equal to 50 (for shipment on a non-exclusive use conveyance) and less than or equal to 100 (for shipment on an exclusive use conveyance).

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          Table 1 Mass Limits for General License Packages Containing Mixed Quantities Of Fissile Material or Uranium-235 of Unknown Enrichment Fissile Material Fissile Material mass mixed with moderating substances having an average hydrogen density less than or equal to water (in grams) Fissile Material mass mixed with moderating substances having an average hydrogen density greater than water^(a) (in grams) ²³⁵U (X) 60 38 ²³³U (Y) 43 27 ²³⁹Pu or ²⁴¹Pu (Z) 37 24

          1. (a) - When mixtures of moderating substances are present, the lower mass limits shall be used if more than 15 percent of the moderating substances has an average hydrogen density greater than water.

             ______________________________________________________

             Table 2 Mass Limits for General License Packages Containing Uranium-235 of Known Enrichment Uranium Enrichment in weight percent of ²³⁵U not exceeding Fissile Material mass of ²³⁵U (X) (in grams) 24 60 20 63 15 67 11 72 10 76 9.5 78 9 81 8.5 82 8 85 7.5 88 7 90 6.5 93 6 97 5.5 102 5 108 4.5 114 4 120 3.5 132 3 150 2.5 180 2 246 1.5 408* 1.35 480* 1 1,020* 0.92 1,800*

             *- Pursuant to the Division's agreement with the USNRC, jurisdiction extends only to 350 grams of uranium-235.

             ______________________________________________________

12. (12) General License: Plutonium-Beryllium Special Form Material.

    1. (a) A general license is hereby issued to any licensee to transport fissile material in the form of plutonium-beryllium (Pu-Be) special form sealed sources, or to deliver Pu-Be sealed sources to a carrier for transport, if the material is shipped in accordance with this section. The material must be contained in a Type A package. The Type A package must also meet the DOT requirements of 49 CFR 173.417(a).

    2. (b) This general license applies only when all of the following requirements are met:

       1. 1. The package contains no more than a Type A quantity of radioactive material.
       2. 2. The package contains less than 1,000 grams of plutonium, provided that: plutonium-239, plutonium-241, or any combination of these radionuclides, constitutes less than 240 grams of the total quantity of plutonium in the package.

    3. (c)

       1. 1. This general license applies only to packages that are labeled with a Criticality Safety Index, calculated by:

          CSI = (10 / 24) x (grams ²³⁹Pu + grams ²⁴¹Pu)

          where the CSI value is less than or equal to 100 and must be rounded up to the first decimal place.

       2. 2. For a shipment of multiple packages containing Pu-Be sealed sources, the sum of the CSIs must be less than or equal to 50 (for shipment on a nonexclusive use conveyance) and less than or equal to 100 (for shipment on an exclusive use conveyance).
    4. (d) The general license has a quality assurance program required by (22).
13. (13) Assumptions as to Unknown Properties of Fissile Material. 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 had credible values that will cause the maximum neutron multiplication.

14. (14) External Radiation Standards For All Packages.

    1. (a) Except as provided in (14)(b), each package of radioactive materials offered for transportation must be designed and prepared for shipment so that under conditions normally incident to transportation the radiation level does not exceed 200 mrem/hr (2 mSv/hr) at any point on the external surface of the package, and the transport index does not exceed 10.

    2. (b) A package that exceeds the radiation level limits specified in (14)(a) must be transported by exclusive use shipment only, and the radiation levels for such shipment must not exceed the following during transportation:

       1. 1. 200 mrem/hr (2 mSv/hr) on the external surface of the package, unless the following conditions are met, in which case the limit is 1,000 mrem/hr (10 mSv/hr):

          1. (i) The shipment is made in a closed transport vehicle;
          2. (ii) The package is secured within the vehicle so that its position remains fixed during transportation; and
          3. (iii) There are no loading or unloading operations between the beginning and end of the transportation;
       2. 2. 200 mrem/hr (2 mSv/hr) at any point on the outer surface of the vehicle, including the top and underside of the vehicle; or in the case of a flat-bed style vehicle, at any point on the vertical planes projected from the outer edges of the vehicle, on the upper surface of the load or enclosure, if used, and on the lower external surface of the vehicle; and
       3. 3. 10 mrem/hr (0.1 mSv/hr) at any point two (2) meters (80 inches) from the outer lateral surfaces of the vehicle (excluding the top and underside of the vehicle); or in the case of a flat-bed style vehicle, at any point two (2) meters (6.6 feet) from the vertical planes projected by the outer edges of the vehicle (excluding the top and underside of the vehicle); and
       4. 4. 2 mrem/hr (0.02 mSv/hr) in any normally occupied space, except that this provision does not apply to private carriers, if exposed personnel under their control wear radiation dosimetry devices in conformance with Rule 391-3-17-.03(8)(b).
    3. (c) For shipments made under the provisions of (14)(b), the shipper will provide specific written instructions to the carrier for maintenance of the exclusive use shipment controls. The instructions must be included with the shipping paper information.
    4. (d) The written instructions required for exclusive use shipments must be sufficient so that, when followed, they will cause the carrier to avoid actions that will unnecessarily delay delivery or unnecessarily result in increased radiation levels or radiation exposures to transport workers or members of the general public.

15. (15) Preliminary Determinations. Prior to the first use of any packaging for the shipment of radioactive material:

    1. (a) The licensee shall ascertain that the determinations in 10 CFR 71.85(a) through (c) have been made.

16. (16) Routine Determinations. Prior to each shipment of licensed material, the licensee shall determine that:

    1. (a) The package is proper for the contents to be shipped;
    2. (b) The package is in unimpaired physical condition except for superficial defects such as marks or dents;
    3. (c) Each closure device of the packaging, including any required gasket, is properly installed and secured and free of defects;
    4. (d) Any system for containing liquid is adequately sealed and has adequate space or other specified provision for expansion of the liquid;
    5. (e) Any pressure relief device is operable and set in accordance with written procedures;
    6. (f) The package has been loaded and closed in accordance with written procedures;
    7. (g) For fissile material, any moderator or neutron absorber, if required, is present and in proper condition;
    8. (h) 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 by 10 CFR 71.45;

    9. (i) The level of non-fixed radioactive contamination on the external surfaces of each package offered for shipment is as low as reasonably achievable.

       1. 1. 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 removable contamination levels. Except as provided in (16)(i)2., the amount of radioactivity measured on any single wiping material, when averaged over the surface wiped, must not exceed the limits given in Table 3 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 removable contamination on the external surfaces of the package exceed 10 times the limits listed in Table 3.

       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 10 times the levels prescribed in (16)(i)1. The levels at the beginning of transport must not exceed the levels in (16)(i)1.;

          _____________________________________________________

          Table 3 Non-Fixed (Removable) External Radioactive Contamination-Wipe Limits    Maximum Permissible limits Contaminant µCi/cm² dpm/cm² Bq/cm² Beta-/gamma-emitting radionuclides; and low toxicity alpha emitters................ 10^-5 22 0.4 All other alpha-emitting radionuclides.......................................... 10^-6 2.2 0.04

          ______________________________________________________

    10. (j) External radiation levels around the package and around the vehicle, if applicable, will not exceed 200 millirem per hour (2 mSv/hr) at any point on the external surface of the package at any time during transportation. The transport index shall not exceed 10.

    11. (k) For package transported as exclusive use by rail, highway, or water, radiation levels external to the package may exceed the limits specified in (16)(j). but shall not exceed any of the following:

        1. 1. 200 millirem per hour (2 mSv/hr) on the accessible external surface of the package unless the following conditions are met, in which case the limit is 1,000 millirem per hour (10 mSv/hr):

           1. (i) The shipment is made in a closed transport vehicle,
           2. (ii) Provisions are made to secure the package so that its position within the vehicle remains fixed during transportation, and
           3. (iii) There are no loading or unloading operations between the beginning and end of the transportation;
        2. 2. 200 millirem per hour (2 mSv/hr) at any point on the outer surface of the vehicle, including the top and underside of the vehicle, or, in the case of a flat-bed style vehicle with a personnel barrier5, at any point on the vertical planes projected from the outer edges of the vehicle, on the upper surface of the load (or enclosure, if used), and on the lower external surface of the vehicle;
        3. 3. 10 millirem per hour (0.1 mSv/hr) at any point 2 meters from the vertical planes represented by the outer lateral surfaces of the vehicle; or in the case of a flat-bed style vehicle, at any point 2 meters from the vertical planes projected from the outer edges of the vehicle; and
        4. 4. 2 millirem per hour (0.02 mSv/hr) in any normally occupied positions 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 391-3-17-.07(3) of this Chapter; and
    12. (l) A package must be prepared for transport so that in still air at 100 degrees Fahrenheit (38 degrees Celsius) and in the shade, no accessible surface of a package would have a temperature exceeding 122 degrees Fahrenheit (50 degrees Celsius) in a nonexclusive use shipment or 185 degrees Fahrenheit (85 degrees Celsius) in an exclusive use shipment. Accessible package surface temperatures shall not exceed these limits at any time during transportation.
    13. (m) A package may not incorporate a feature intended to allow continuous venting during transport.

17. (17) Air Transport of Plutonium. Notwithstanding the provisions of any general licenses and notwithstanding any exemptions stated directly in this Rule or included indirectly by citation of the 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:

    1. (a) The plutonium is contained in a medical device designed for individual human application;
    2. (b) The plutonium is contained in a material in which the specific activity is not greater than the activity concentration values for plutonium as specified in Table 7, and in which the radioactivity is essentially uniformly distributed;
    3. (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 (5); or
    4. (d) The plutonium is shipped in a package specifically authorized, in the certificate of compliance, issued by the Nuclear Regulatory Commission, for the shipment of plutonium by air and the licensee requires, through special arrangement with the carrier, compliance with 49 CFR 175.704, the US Department of Transportation regulations applicable to the air transport of plutonium.
18. (18) Opening instructions. Before delivery of a package to a carrier for transport, the licensee shall ensure that any special instructions needed to safely open the package have been sent to, or otherwise made available to, the consignee for the consignee's use in accordance with Rule 391-3-17-.03(12)(f).

19. (19) Shipment Records. Each licensee shall maintain for a period of three years after shipment a record of each shipment of licensed material not exempt under (4), showing, where applicable:

    1. (a) Identification of the packaging by model number;
    2. (b) Verification that there were no significant defects in the packaging, as shipped;
    3. (c) Volume and identification of coolant;
    4. (d) Type and quantity of licensed material in each package, and the total quantity of each shipment;
    5. (e) Date of the shipment;
    6. (f) Name and address of the transferee;
    7. (g) Address to which the shipment was made; and
    8. (h) Results of the determinations required by (16) and the conditions of the package approval.
    9. (i) The licensee shall make available to the Division for inspection, upon reasonable notice, all records required by this part. Records are only valid if stamped, initialed, or signed and dated by authorized personnel, or otherwise authenticated.
    10. (j) The licensee shall maintain sufficient written records to furnish evidence of the quality of packaging. The records to be maintained include results of the determinations required by 391-3-17-.06(15) and 10 CFR 71.85; design, fabrication, and assembly records; results of reviews, inspections, tests, and audits; results of monitoring work performance and materials analyses; and results of maintenance, modification, and repair activities. Inspection, test, and audit records must identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any deficiencies noted. These records must be retained for 3 years after the life of the packaging to which they apply.

    11. (k) For each item of irradiated fissile material -

        1. 1. Identification by model number and serial number;
        2. 2. Irradiation and decay history to the extent appropriate to demonstrate that its nuclear and thermal characteristics comply with license conditions; and
        3. 3. Any abnormal or unusual condition relevant to radiation safety;
    12. (l) For fissile packages and for Type B packages, any special controls exercised.

20. (20) Reports. The licensee shall report to the Division within 30 days:

    1. (a) Any instance in which there is significant reduction in the effectiveness of any authorized packaging during use; and
    2. (b) Details of any defects with safety significance in the packaging after first use, with the means employed to repair the defects and prevent their recurrence.

21. (21) Advance Notification of Transport of Nuclear Waste.

    1. (a) As specified in paragraphs (b), (c), and (d) of this section, each licensee shall provide advance notification to the governor of a State, or the governor's designee6, of the shipment of licensed material, within or across the boundary of the State, before the transport, or delivery to a carrier, for transport, of licensed material outside the confines of the licensee's plant or other place of use or storage.

       1. 1. As specified in paragraphs (b), (c), and (d) of this section, after June 11, 2013, each licensee shall provide advance notification to the Tribal official of participating Tribes referenced in paragraph (d)3.(iii) of this section, or the official's designee, of the shipment of licensed material, within or across the boundary of the Tribe's reservation, before the transport, or delivery to a carrier, for transport, of licensed material outside the confines of the licensee's plant or other place of use or storage.

    2. (b) Advance notification is also required when:

       1. 1. The licensed material is required to be in Type B packaging for transportation;
       2. 2. The licensed material is being transported into, within, or through, a state en route to a disposal facility or to a collection point for transport to a disposal facility; and

       3. 3. The quantity of licensed material in a single package exceeds the least of the following:

          1. (i) 3000 times the A1 value of the radionuclides as specified in Table 7, for special form radioactive material;
          2. (ii) 3000 times the A2 value of the radionuclides as specified in Table 7 for normal form radioactive material; or
          3. (iii) 27,000 Ci (1000 TBq);

    3. (c) Each advance notification required by .06(21)(a) shall contain the following information:

       1. 1. The name, address, and telephone number of the shipper, carrier, and receiver of the shipment;
       2. 2. A description of the nuclear waste contained in the shipment as required by 49 CFR 172.202 and 172.203(d);
       3. 3. The point of origin of the shipment and the seven-day period during which departure of the shipment is estimated to occur;
       4. 4. The seven-day period during which arrival of the shipment at state boundaries or Tribal reservation boundaries is estimated to occur;
       5. 5. The destination of the shipment, and the seven-day period during which arrival of the shipment is estimated to occur; and
       6. 6. A point of contact with a telephone number for current shipment information.

    4. (d) Procedures for Submitting Advance Notification:

       1. 1. The notification required by .06(21)(a) shall be made in writing to the office of each appropriate governor, or governor's designee, to the office of each appropriate Tribal official or Tribal official's designee, and to the Division.
       2. 2. 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.

       3. 3. A notification delivered by any other means than mail must reach the office of the governor or of the governor's designee or the Tribal official or Tribal official's designee at least four days before the beginning of the seven-day period during which departure of the shipment is estimated to occur.

          1. (i) [Reserved]
          2. (ii) The list of governor's designees and Tribal official's designees of participating Tribes will be published annually in the Federal Register on or about June 30th to reflect any changes in information.
          3. (iii) A list of the names and mailing addresses of the governors' designees and Tribal officials' designees of participating Tribes, including telephone and mailing addresses of Tribal official's designees, is available on the NRC Web site at: https://scp.nrc.gov/special/designee.pdf.
       4. 4. A copy of the notification shall be retained by the licensee for three years.
    5. (e) A licensee who finds that schedule information previously furnished to a governor or governor's designee or a Tribal official or Tribal official's designee, in accordance with this section, will not be met, shall telephone a responsible individual in the office of the governor of the State or of the governor's designee or the Tribal official or the Tribal official's designee and inform that individual of the extent of the delay beyond the schedule originally reported. The licensee shall maintain a record of the name of the individual contacted for three years.

    6. (f) Each licensee who cancels a nuclear waste shipment for which advance notification has been sent shall send a cancellation notice to the governor of each State or to the governor's designee previously notified, each Tribal official or to the Tribal official's designee previously notified, and to the Division.

       1. 1. The licensee shall state in the notice that it is a cancellation and identify the advance notification that is being cancelled. The licensee shall retain a copy of the notice as a record for 3 years.

22. (22) Quality Assurance Requirements.

    This paragraph describes quality assurance requirements applying to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging that are important to safety. As used in this paragraph, "quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a system or component will perform satisfactorily in service. Quality assurance includes quality control, which comprises those quality assurance actions related to control of the physical characteristics and quality of the material or component to predetermined requirements. Each licensee is responsible for satisfying the quality assurance requirements that apply to its use of a packaging for the shipment of licensed material subject to this subpart.

    1. (a) Unless otherwise authorized by the Division, each licensee 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 material are promptly identified and corrected.
    2. (b) The licensee shall identify the material and components to be covered by the quality assurance program.
    3. (c) Each licensee 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.
    4. (d) Prior to the use of any package for the shipment of radioactive material, each licensee shall obtain approval by the Division of its quality assurance program.
    5. (e) The licensee shall maintain sufficient written records to demonstrate compliance with the quality assurance program. Records of quality assurance pertaining to the use of a package for shipment of radioactive material shall be maintained for a period of three years after shipment.
    6. (f) Radiography containers. A program for transport container inspection and maintenance limited to radiographic exposure devices, source changers, or packages transporting these devices and meeting the requirements of rule 391-3-17-.04(11)(d) and (e) or equivalent NRC or Agreement State requirement, is deemed to satisfy the requirements of 391-3-17-.06(7) and .06(22)(g).
    7. (g) Establishment of program. Each licensee shall establish, maintain, and execute a quality assurance program satisfying each of the applicable criteria of 391-3-17-.06(22) and satisfying any specific provisions that are applicable to the licensee's activities including procurement of packaging. The licensee shall execute the applicable criteria in a graded approach to an extent that is commensurate with the quality assurance requirement's importance to safety.

    8. (h) Approval of program.

       1. 1. Before the use of any package for the shipment of licensed material subject to this paragraph, each licensee shall obtain Division approval of its quality assurance program. Using an appropriate method listed in 391-3-17-.06(22), each licensee shall file a description of its quality assurance program, including a discussion of which requirements of this subpart are applicable and how they will be satisfied, by submitting the description to: Georgia Department of Natural Resources/Environmental Protection Division, Radioactive Materials Program, at 4244 International Parkway, Suite 120, Atlanta, Georgia 30354.

    9. (i) Quality Assurance Organization

       1. 1. The licensee shall be responsible for the establishment and execution of the quality assurance program. The licensee may delegate to others, such as contractors, agents, or consultants, the work of establishing and executing the quality assurance program, or any part of the quality assurance program, but shall retain responsibility for the program. These activities include performing the functions associated with attaining quality objectives and the quality assurance functions.

       2. 2. The quality assurance functions are:

          1. (i) Assuring that an appropriate quality assurance program is established and effectively executed; and
          2. (ii) Verifying, by procedures such as checking, auditing, and inspection, that activities affecting the functions that are important to safety have been correctly performed.

    10. (j) Changes to Quality Assurance Programs

        1. 1. Each quality assurance program approval holder shall submit, in accordance with the requirements of 391-3-17-.01(13) and 391-3-17-.06(19), a description of a proposed change to its Georgia Department of Natural Resources Radioactive Materials Program approved quality assurance program that will reduce commitments in the program description as approved by the Georgia Department of Natural Resources Radioactive Materials Program. The quality assurance program approval holder shall not implement the change before receiving Georgia Department of Natural Resources Radioactive Materials Program approval.

           1. (i) The description of a proposed change to the Georgia Department of Natural Resources Radioactive Materials Program approved quality assurance program must identify the change, the reason for the change, and the basis for concluding that the revised program incorporating the change continues to satisfy the applicable requirements of 391-3-17-.06(22).
           2. (ii) [Reserved]

        2. 2. Each quality assurance program approval holder may change a previously approved quality assurance program without prior Georgia Department of Natural Resources Radioactive Materials Program approval, if the change does not reduce the commitments in the quality assurance program previously approved by the Georgia Department of Natural Resources Radioactive Materials Program. Changes to the quality assurance program that do not reduce the commitments shall be submitted to the Georgia Department of Natural Resources Radioactive Materials Program every 24 months, in accordance with 391-3-17-.01(13). In addition to quality assurance program changes involving administrative improvements and clarifications, spelling corrections, and non-substantive changes to punctuation or editorial items, the following changes are not considered reductions in commitment:

           1. (i) The use of a quality assurance standard approved by the Georgia Department of Natural Resources Radioactive Materials Program that is more recent than the quality assurance standard in the applicant's current quality assurance program at the time of the change;
           2. (ii) The use of generic organizational position titles that clearly denote the position function, supplemented as necessary by descriptive text, rather than specific titles, provided that there is no substantive change to either the functions of the position or reporting responsibilities;
           3. (iii) The use of generic organizational charts to indicate functional relationships, authorities, and responsibilities, or alternatively, the use of descriptive text, provided that there is no substantive change to the functional relationships, authorities, or responsibilities;
           4. (iv) The elimination of quality assurance program information that duplicates language in quality assurance regulatory guides and quality assurance standards to which the quality assurance program approval holder has committed to on record; and
           5. (v) Organizational revisions that ensure that persons and organizations performing quality assurance functions continue to have the requisite authority and organizational freedom, including sufficient independence from cost and schedule when opposed to safety considerations.
        3. 3. Each quality assurance program approval holder shall maintain records of quality assurance program changes.

    11. (k) Quality Assurance Records

        1. 1. The licensee shall maintain sufficient written records to describe the activities affecting quality. These records must include changes to the quality assurance program as required by 391-3-17-.06(22)(j), the instructions, procedures, and drawings required by 10 CFR 71.111 to prescribe quality assurance activities, and closely related specifications such as required qualifications of personnel, procedures, and equipment. The records must include the instructions or procedures that establish a records retention program that is consistent with applicable regulations and designates factors such as duration, location, and assigned responsibility. The licensee shall retain these records for 3 years beyond the date when the licensee last engage in the activity for which the quality assurance program was developed. If any portion of the quality assurance program, written procedures or instructions is superseded, the licensee shall retain the superseded material for 3 years after it is superseded.

(23) Determination of A₁ and A₂. (a) Values of A₁ and A₂ for individual radionuclides, which are the bases for many activity limits elsewhere in these regulations, are given in Table 4. The curie (Ci) values specified are obtained by converting from the Terabecquerel (TBq) value. The curie values are expressed to three significant figures to assure that the difference in the TBq and Ci quantities is one tenth of one percent or less. Where values of A₁ or A₂ are unlimited, it is for radiation control purposes only. For nuclear criticality safety, some materials are subject to controls placed on fissile material. (b) 1. For individual radionuclides whose identities are known but are not listed in Table 4, the A₁ and A₂ values contained in Table 5 may be used. Otherwise, the licensee shall obtain prior Division approval of the A₁ and A₂ values for radionuclides not listed in Table 4, before shipping the material 2. For individual radionuclides whose identities are known but are not listed in Table 7, the exempt material activity concentration and exempt consignment activity values contained in Table 5 may be used. Otherwise, the licensee shall obtain prior Division approval of the exempt material activity concentration and exempt consignment activity values for radionuclides not listed in Table 7, before shipping the material. (c) In calculations of A₁ and A₂ for a radionuclide not in Table 4, a single radioactive decay chain, in which radionuclides are present in their naturally occurring proportions, and in which no daughter nuclide has a half-life either longer than 10 days, or longer than that of the parent nuclide, shall be considered as a single radionuclide, and the activity to be taken into account, and the A₁ and A₂ value to be applied shall be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than ten days, or greater than of the parent nuclide, the parent and those daughters nuclides shall be considered as a mixture of different nuclides. (d) Mixtures of radionuclides. 1. For mixture of radionuclides whose identities and respective activities are known, following conditions apply: (i) For a special form radioactive material, the maximum quantity transported in a Type A package is as follows: where B(i) is the activity of radionuclide i in special form, and A₁(i) is the A₁ value for radionuclide i. (ii) For normal form radioactive material, the maximum quantity transported in a Type A package is as follows: where B(i) is the activity of radionuclide i in normal form, and A₂(i) is the A₂ value for radionuclide i. (iii) If the package contains both special and normal form radioactive material, the activity that may be transported in a Type A package is as follows: where B(i) is the activity of radionuclide i as special form radioactive material, A₁(i) is the A₁ value for radionuclide i, C(j) is the activity of radionuclide j as normal form radioactive material, and A₂(j) is the A₂ value for radionuclide j. (iv) Alternatively, the A₁ value for mixtures of special form material may be determined as follows: A₁ for mixture = where f(i) is the fraction of activity for radionuclide i in the mixture and A₁ (i) is the appropriate A₁ value for radionuclide i. (v) Alternatively, the A₂ value for mixtures of normal form material may be determined as follows: A₂ for mixture = where f(i) is the fraction of activity of radionuclide i in the mixture and A₂(i) is the appropriate A₂ value for radionuclide i. (e) The exempt activity concentration for mixtures of radionuclides may be determined as follows: Exempt activity concentration for mixture = where f(i) is the fraction activity concentration of radionuclide i in the mixture and [A](i) is the activity concentration for exempt material containing radionuclide i. (f) The activity limit for an exempt consignment for mixtures of radionuclides may be determined as follows: Exempt consignment activity limit for mixture = where f(i) is the fraction of activity of radionuclide i in the mixture and [A] is the activity limit for exempt consignments for radionuclide i. (g) 1. When the identity of each radionuclide is known, but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped, and the lowest A₁ or A₂ value, as appropriate, for the radionuclides in each group may be used in applying formulas above. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest A₁ or A₂ values for the alpha emitters and beta/gamma emitters. 2. When the identity of each radionuclide is known, but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped, and the lowest [A] (activity concentration for exempt material) or A (activity limit for exempt consignment) value, as appropriate, for the radionuclides in each group may be used in applying the formulas in paragraph 391-3-17-.06(23). Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest [A] or A values for the alpha emitters and beta/gamma emitters, respectively. Table 4 - A₁ and A₂ VALUES FOR RADIONUCLIDES Symbol of radionuclide Element and atomic number A₁ (TBq) A₁(Ci)^b A₂ (TBq) A₂(Ci)^b Specific activity (TBq/g) (Ci/g) Ac-225 (a) Actinium (89) 8.0X10^-1 2.2X10¹ 6.0X10^-3 1.6X10^-1 2.1X10³ 5.8X10⁴ Ac-227 (a)    9.0X10^-1 2.4X10¹ 9.0X10^-5 2.4X10^-3 2.7 7.2X10¹ Ac-228    6.0X10^-1 1.6X10¹ 5.0X10^-1 1.4X10¹ 8.4X10⁴ 2.2X10⁶ Ag-105 Silver (47) 2.0 5.4X10¹ 2.0 5.4X10¹ 1.1X10³ 3.0X10⁴ Ag-108m (a)    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 9.7X10^-1 2.6X10¹ Ag-110m (a)    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 1.8X10² 4.7X10³ Ag-111    2.0 5.4X10¹ 6.0X10^-1 1.6X10¹ 5.8X10³ 1.6X10⁵ Al-26 Aluminum (13) 1.0X10^-1 2.7 1.0X10^-1 2.7 7.0X10^-4 1.9X10^-2 Am-241 Americium (95) 1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 1.3X10^-1 3.4 Am-242m (a)    1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 3.6X10^-1 1.0X10¹ Am-243 (a)    5.0 1.4X10² 1.0X10^-3 2.7X10^-2 7.4X10^-3 2.0X10^-1 Ar-37 Argon (18) 4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 3.7X10³ 9.9X10⁴ Ar-39    4.0X10¹ 1.1X10³ 2.0X10¹ 5.4X10² 1.3 3.4X10¹ Ar-41    3.0X10^-1 8.1 3.0X10^-1 8.1 1.5X10⁶ 4.2X10⁷ As-72 Arsenic (33) 3.0X10^-1 8.1 3.0X10^-1 8.1 6.2X10⁴ 1.7X10⁶ As-73    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 8.2X10² 2.2X10⁴ As-74    1.0 2.7X10¹ 9.0X10^-1 2.4X10¹ 3.7X10³ 9.9X10⁴ As-76    3.0X10^-1 8.1 3.0X10^-1 8.1 5.8X10⁴ 1.6X10⁶ As-77    2.0X10¹ 5.4X10² 7.0X10^-1 1.9X10¹ 3.9X10⁴ 1.0X10⁶ At-211 (a) Astatine (85) 2.0X10¹ 5.4X10² 5.0X10^-1 1.4X10¹ 7.6X10⁴ 2.1X10⁶ Au-193 Gold (79) 7.0 1.9X10² 2.0 5.4X10¹ 3.4X10⁴ 9.2X10⁵ Au-194    1.0 2.7X10¹ 1.0 2.7X10¹ 1.5X10⁴ 4.1X10⁵ Au-195    1.0X10¹ 2.7X10² 6.0 1.6X10² 1.4X10² 3.7X10³ Au-198    1.0 2.7X10¹ 6.0X10^-1 1.6X10¹ 9.0X10³ 2.4X10⁵ Au-199    1.0X10¹ 2.7X10² 6.0X10^-1 1.6X10¹ 7.7X10³ 2.1X10⁵ Ba-131 (a) Barium (56) 2.0 5.4X10¹ 2.0 5.4X10¹ 3.1X10³ 8.4X10⁴ Ba-133    3.0 8.1X10¹ 3.0 8.1X10¹ 9.4 2.6X10² Ba-133m    2.0X10¹ 5.4X10² 6.0X10^-1 1.6X10¹ 2.2X10⁴ 6.1X10⁵ Ba-140 (a)    5.0X10^-1 1.4X10¹ 3.0X10^-1 8.1 2.7X10³ 7.3X10⁴ Be-7 Beryllium (4) 2.0X10¹ 5.4X10² 2.0X10¹ 5.4X10² 1.3X10⁴ 3.5X10⁵ Be-10    4.0X10¹ 1.1X10³ 6.0X10^-1 1.6X10¹ 8.3X10^-4 2.2X10^-2 Bi-205 Bismuth (83) 7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 1.5X10³ 4.2X10⁴ Bi-206    3.0X10^-1 8.1 3.0X10^-1 8.1 3.8X10³ 1.0X10⁵ Bi-207    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 1.9 5.2X10¹ Bi-210    1.0 2.7X10¹ 6.0X10^-1 1.6X10¹ 4.6X10³ 1.2X10⁵ Bi-210m (a)    6.0X10^-1 1.6X10¹ 2.0X10^-2 5.4X10^-1 2.1X10^-5 5.7X10^-4 Bi-212 (a)    7.0X10^-1 1.9X10¹ 6.0X10^-1 1.6X10¹ 5.4X10⁵ 1.5X10⁷ Bk-247 Berkelium (97) 8.0 2.2X10² 8.0X10^-4 2.2X10^-2 3.8X10^-2 1.0 Bk-249 (a)    4.0X10¹ 1.1X10³ 3.0X10^-1 8.1 6.1X10¹ 1.6X10³ Br-76 Bromine (35) 4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 9.4X10⁴ 2.5X10⁶ Br-77    3.0 8.1X10¹ 3.0 8.1X10¹ 2.6X10⁴ 7.1X10⁵ Br-82    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 4.0X10⁴ 1.1X10⁶ C-11 Carbon (6) 1.0 2.7X10¹ 6.0X10^-1 1.6X10¹ 3.1X10⁷ 8.4X10⁸ C-14    4.0X10¹ 1.1X10³ 3.0 8.1X10¹ 1.6X10^-1 4.5 Ca-41 Calcium (20) Unlimited Unlimited Unlimited Unlimited 3.1X10^-3 8.5X10^-2 Ca-45    4.0X10¹ 1.1X10³ 1.0 2.7X10¹ 6.6X10² 1.8X10⁴ Ca-47 (a)    3.0 8.1X10¹ 3.0X10^-1 8.1 2.3X10⁴ 6.1X10⁵ Cd-109 Cadmium (48) 3.0X10¹ 8.1X10² 2.0 5.4X10¹ 9.6X10¹ 2.6X10³ Cd-113m    4.0X10¹ 1.1X10³ 5.0X10^-1 1.4X10¹ 8.3 2.2X10² Cd-115 (a)    3.0 8.1X10¹ 4.0X10^-1 1.1X10¹ 1.9X10⁴ 5.1X10⁵ Cd-115m    5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 9.4X10² 2.5X10⁴ Ce-139 Cerium (58) 7.0 1.9X10² 2.0 5.4X10¹ 2.5X10² 6.8X10³ Ce-141    2.0X10¹ 5.4X10² 6.0X10^-1 1.6X10¹ 1.1X10³ 2.8X10⁴ Ce-143    9.0X10^-1 2.4X10¹ 6.0X10^-1 1.6X10¹ 2.5X10⁴ 6.6X10⁵ Ce-144 (a)    2.0X10^-1 5.4 2.0X10^-1 5.4 1.2X10² 3.2X10³ Cf-248 Californium (98) 4.0X10¹ 1.1X10³ 6.0X10^-3 1.6X10^-1 5.8X10¹ 1.6X10³ Cf-249    3.0 8.1X10¹ 8.0X10^-4 2.2X10^-2 1.5X10^-1 4.1 Cf-250    2.0X10¹ 5.4X10² 2.0X10^-3 5.4X10^-2 4.0 1.1X10² Cf-251    7.0 1.9X10² 7.0X10^-4 1.9X10^-2 5.9X10^-2 1.6 Cf-252    1.0X10^-1 2.7 3.0X10^-3 8.1X10^-2 2.0X10¹ 5.4X10² Cf-253 (a)    4.0X10¹ 1.1X10³ 4.0X10^-2 1.1 1.1X10³ 2.9X10⁴ Cf-254    1.0X10^-3 2.7X10^-2 1.0X10^-3 2.7X10^-2 3.1X10² 8.5X10³ Cl-36 Chlorine (17) 1.0X10¹ 2.7X10² 6.0X10^-1 1.6X10¹ 1.2X10^-3 3.3X10^-2 Cl-38    2.0X10^-1 5.4 2.0X10^-1 5.4 4.9X10⁶ 1.3X10⁸ Cm-240 Curium (96) 4.0X10¹ 1.1X10³ 2.0X10^-2 5.4X10^-1 7.5X10² 2.0X10⁴ Cm-241    2.0 5.4X10¹ 1.0 2.7X10¹ 6.1X10² 1.7X10⁴ Cm-242    4.0X10¹ 1.1X10³ 1.0X10^-2 2.7X10^-1 1.2X10² 3.3X10³ Cm-243    9.0 2.4X10² 1.0X10^-3 2.7X10^-2 1.9X10^-3 5.2X10¹ Cm-244    2.0X10¹ 5.4X10² 2.0X10^-3 5.4X10^-2 3.0 8.1X10¹ Cm-245    9.0 2.4X10² 9.0X10^-4 2.4X10^-2 6.4X10^-3 1.7X10^-1 Cm-246    9.0 2.4X10² 9.0X10^-4 2.4X10^-2 1.1X10^-2 3.1X10^-1 Cm-247 (a)    3.0 8.1X10¹ 1.0X10^-3 2.7X10^-2 3.4X10^-6 9.3X10^-5 Cm-248    2.0X10^-2 5.4X10^-1 3.0X10^-4 8.1X10^-3 1.6X10^-4 4.2X10^-3 Co-55 Cobalt (27) 5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 1.1X10⁵ 3.1X10⁶ Co-56    3.0X10^-1 8.1 3.0X10^-1 8.1 1.1X10³ 3.0X10⁴ Co-57    1.0X10¹ 2.7X10² 1.0X10¹ 2.7X10² 3.1X10² 8.4X10³ Co-58    1.0 2.7X10¹ 1.0 2.7X10¹ 1.2X10³ 3.2X10⁴ Co-58m    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 2.2X10⁵ 5.9X10⁶ Co-60    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 4.2X10¹ 1.1X10³ Cr-51 Chromium (24) 3.0X10¹ 8.1X10² 3.0X10¹ 8.1X10² 3.4X10³ 9.2X10⁴ Cs-129 Cesium (55) 4.0 1.1X10² 4.0 1.1X10² 2.8X10⁴ 7.6X10⁵ Cs-131    3.0X10¹ 8.1X10² 3.0X10¹ 8.1X10² 3.8X10³ 1.0X10⁵ Cs-132    1.0 2.7X10¹ 1.0 2.7X10¹ 5.7X10³ 1.5X10⁵ Cs-134    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 4.8X10¹ 1.3X10³ Cs-134m    4.0X10¹ 1.1X10³ 6.0X10^-1 1.6X10¹ 3.0X10⁵ 8.0X10⁶ Cs-135    4.0X10¹ 1.1X10³ 1.0 2.7X10¹ 4.3X10^-5 1.2X10^-3 Cs-136    5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 2.7X10³ 7.3X10⁴ Cs-137 (a)    2.0 5.4X10¹ 6.0X10^-1 1.6X10¹ 3.2 8.7X10¹ Cu-64 Copper (29) 6.0 1.6X10² 1.0 2.7X10¹ 1.4X10⁵ 3.9X10⁶ Cu-67    1.0X10¹ 2.7X10² 7.0X10^-1 1.9X10¹ 2.8X10⁴ 7.6X10⁵ Dy-159 Dysprosium (66) 2.0X10¹ 5.4X10² 2.0X10¹ 5.4X10² 2.1X10² 5.7X10³ Dy-165    9.0X10^-1 2.4X10¹ 6.0X10^-1 1.6X10¹ 3.0X10⁵ 8.2X10⁶ Dy-166 (a)    9.0X10^-1 2.4X10¹ 3.0X10^-1 8.1 8.6X10³ 2.3X10⁵ Er-169 Erbium (68) 4.0X10¹ 1.1X10³ 1.0 2.7X10¹ 3.1X10³ 8.3X10⁴ Er-171    8.0X10^-1 2.2X10¹ 5.0X10^-1 1.4X10¹ 9.0X10⁴ 2.4X10⁶ Eu-147 Europium (63) 2.0 5.4X10¹ 2.0 5.4X10¹ 1.4X10³ 3.7X10⁴ Eu-148    5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 6.0X10² 1.6X10⁴ Eu-149    2.0X10¹ 5.4X10² 2.0X10¹ 5.4X10² 3.5X10² 9.4X10³ Eu-150 (short lived)    2.0 5.4X10¹ 7.0X10^-1 1.9X10¹ 6.1X10⁴ 1.6X10⁶ Eu-150 (long lived)    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 6.1X10⁴ 1.6X10⁶ Eu-152    1.0 2.7X10¹ 1.0 2.7X10¹ 6.5 1.8X10² Eu-152m    8.0X10^-1 2.2X10¹ 8.0X10^-1 2.2X10¹ 8.2X10⁴ 2.2X10⁶ Eu-154    9.0X10^-1 2.4X10¹ 6.0X10^-1 1.6X10¹ 9.8 2.6X10² Eu-155    2.0X10¹ 5.4X10² 3.0 8.1X10¹ 1.8X10¹ 4.9X10² Eu-156    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 2.0X10³ 5.5X10⁴ F-18 Fluorine (9) 1.0 2.7X10¹ 6.0X10^-1 1.6X10¹ 3.5X10⁶ 9.5X10⁷ Fe-52 (a) Iron (26) 3.0X10^-1 8.1 3.0X10^-1 8.1 2.7X10⁵ 7.3X10⁶ Fe-55    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 8.8X10¹ 2.4X10³ Fe-59    9.0X10^-1 2.4X10¹ 9.0X10^-1 2.4X10¹ 1.8X10³ 5.0X10⁴ Fe-60 (a)    4.0X10¹ 1.1X10³ 2.0X10^-1 5.4 7.4X10^-4 2.0X10^-2 Ga-67 Gallium (31) 7.0 1.9X10² 3.0 8.1X10¹ 2.2X10⁴ 6.0X10⁵ Ga-68    5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 1.5X10⁶ 4.1X10⁷ Ga-72    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 1.1X10⁵ 3.1X10⁶ Gd-146 (a) Gadolinium (64) 5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 6.9X10² 1.9X10⁴ Gd-148    2.0X10¹ 5.4X10² 2.0X10^-3 5.4X10^-2 1.2 3.2X10¹ Gd-153    1.0X10¹ 2.7X10² 9.0 2.4X10² 1.3X10² 3.5X10³ Gd-159    3.0 8.1X10¹ 6.0X10^-1 1.6X10¹ 3.9X10⁴ 1.1X10⁶ Ge-68 (a) Germanium (32) 5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 2.6X10² 7.1X10³ Ge-71    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 5.8X10³ 1.6X10⁵ Ge-77    3.0X10^-1 8.1 3.0X10^-1 8.1 1.3X10⁵ 3.6X10⁶ Hf-172 (a) Hafnium (72) 6.0X10^-1 1.6X10¹ 6.0X10^-1 1.6X10¹ 4.1X10¹ 1.1X10³ Hf-175    3.0 8.1X10¹ 3.0 8.1X10¹ 3.9X10² 1.1X10⁴ Hf-181    2.0 5.4X10¹ 5.0X10^-1 1.4X10¹ 6.3X10² 1.7X10⁴ Hf-182    Unlimited Unlimited Unlimited Unlimited 8.1X10^-6 2.2X10^-4 Hg-194 (a) Mercury (80) 1.0 2.7X10¹ 1.0 2.7X10¹ 1.3X10^-1 3.5 Hg-195m (a)    3.0 8.1X10¹ 7.0X10^-1 1.9X10¹ 1.5X10⁴ 4.0X10⁵ Hg-197    2.0X10¹ 5.4X10² 1.0X10¹ 2.7X10² 9.2X10³ 2.5X10⁵ Hg-197m    1.0X10¹ 2.7X10² 4.0X10^-1 1.1X10¹ 2.5X10⁴ 6.7X10⁵ Hg-203    5.0 1.4X10² 1.0 2.7X10¹ 5.1X10² 1.4X10⁴ Ho-166 Holmium (67) 4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 2.6X10⁴ 7.0X10⁵ Ho-166m    6.0X10^-1 1.6X10¹ 5.0X10^-1 1.4X10¹ 6.6X10^-2 1.8 I-123 Iodine (53) 6.0 1.6X10² 3.0 8.1X10¹ 7.1X10⁴ 1.9X10⁶ I-124    1.0 2.7X10¹ 1.0 2.7X10¹ 9.3X10³ 2.5X10⁵ I-125    2.0X10¹ 5.4X10² 3.0 8.1X10¹ 6.4X10² 1.7X10⁴ I-126    2.0 5.4X10¹ 1.0 2.7X10¹ 2.9X10³ 8.0X10⁴ I-129    Unlimited Unlimited Unlimited Unlimited 6.5X10^-6 1.8X10^-4 I-131    3.0 8.1X10¹ 7.0X10^-1 1.9X10¹ 4.6X10³ 1.2X10⁵ I-132    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 3.8X10⁵ 1.0X10⁷ I-133    7.0X10^-1 1.9X10¹ 6.0X10^-1 1.6X10¹ 4.2X10⁴ 1.1X10⁶ I-134    3.0X10^-1 8.1 3.0X10^-1 8.1 9.9X10⁵ 2.7X10⁷ I-135 (a)    6.0X10^-1 1.6X10¹ 6.0X10^-1 1.6X10¹ 1.3X10⁵ 3.5X10⁶ In-111 Indium (49) 3.0 8.1X10¹ 3.0 8.1X10¹ 1.5X10⁴ 4.2X10⁵ In-113m    4.0 1.1X10² 2.0 5.4X10¹ 6.2X10⁵ 1.7X10⁷ In-114m (a)    1.0X10¹ 2.7X10² 5.0X10^-1 1.4X10¹ 8.6X10² 2.3X10⁴ In-115m    7.0 1.9X10² 1.0 2.7X10¹ 2.2X10⁵ 6.1X10⁶ Ir-189 (a) Iridium (77) 1.0X10¹ 2.7X10² 1.0X10¹ 2.7X10² 1.9X10³ 5.2X10⁴ Ir-190    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 2.3X10³ 6.2X10⁴ Ir-192    ^c1.0 ^c2.7X10¹ 6.0X10^-1 1.6X10¹ 3.4X10² 9.2X10³ Ir-194    3.0X10^-1 8.1 3.0X10^-1 8.1 3.1X10⁴ 8.4X10⁵ K-40 Potassium (19) 9.0X10^-1 2.4X10¹ 9.0X10^-1 2.4X10¹ 2.4X10^-7 6.4X10^-6 K-42    2.0X10^-1 5.4 2.0X10^-1 5.4 2.2X10⁵ 6.0X10⁶ K-43    7.0X10^-1 1.9X10¹ 6.0X10^-1 1.6X10¹ 1.2X10⁵ 3.3X10⁶ Kr-79 Krypton (36) 4.0 1.1X10² 2.0 5.4X10¹ 4.2X10⁴ 1.1X10⁶ Kr-81    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 7.8X10^-4 2.1X10^-2 Kr-85    1.0X10¹ 2.7X10² 1.0X10¹ 2.7X10² 1.5X10¹ 3.9X10² Kr-85m    8.0 2.2X10² 3.0 8.1X10¹ 3.0X10⁵ 8.2X10⁶ Kr-87    2.0X10^-1 5.4 2.0X10^-1 5.4 1.0X10⁶ 2.8X10⁷ La-137 Lanthanum (57) 3.0X10¹ 8.1X10² 6.0 1.6X10² 1.6X10^-3 4.4X10^-2 La-140    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 2.1X10⁴ 5.6X10⁵ Lu-172 Lutetium (71) 6.0X10^-1 1.6X10¹ 6.0X10^-1 1.6X10¹ 4.2X10³ 1.1X10⁵ Lu-173    8.0 2.2X10² 8.0 2.2X10² 5.6X10¹ 1.5X10³ Lu-174    9.0 2.4X10² 9.0 2.4X10² 2.3X10¹ 6.2X10² Lu-174m    2.0X10¹ 5.4X10² 1.0X10¹ 2.7X10² 2.0X10² 5.3X10³ Lu-177    3.0X10¹ 8.1X10² 7.0X10^-1 1.9X10¹ 4.1X10³ 1.1X10⁵ Mg-28 (a) Magnesium (12) 3.0X10^-1 8.1 3.0X10^-1 8.1 2.0X10⁵ 5.4X10⁶ Mn-52 Manganese (25) 3.0X10^-1 8.1 3.0X10^-1 8.1 1.6X10⁴ 4.4X10⁵ Mn-53    Unlimited Unlimited Unlimited Unlimited 6.8X10^-5 1.8X10^-3 Mn-54    1.0 2.7X10¹ 1.0 2.7X10¹ 2.9X10² 7.7X10³ Mn-56    3.0X10^-1 8.1 3.0X10^-1 8.1 8.0X10⁵ 2.2X10⁷ Mo-93 Molybdenum (42) 4.0X10¹ 1.1X10³ 2.0X10¹ 5.4X10² 4.1X10^-2 1.1 Mo-99 (a) (h)    1.0 2.7X10¹ 6.0X10^-1 1.6X10¹ 1.8X10⁴ 4.8X10⁵ N-13 Nitrogen (7) 9.0X10^-1 2.4X10¹ 6.0X10^-1 1.6X10¹ 5.4X10⁷ 1.5X10⁹ Na-22 Sodium (11) 5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 2.3X10² 6.3X10³ Na-24    2.0X10^-1 5.4 2.0X10^-1 5.4 3.2X10⁵ 8.7X10⁶ Nb-93m Niobium (41) 4.0X10¹ 1.1X10³ 3.0X10¹ 8.1X10² 8.8 2.4X10² Nb-94    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 6.9X10^-3 1.9X10^-1 Nb-95    1.0 2.7X10¹ 1.0 2.7X10¹ 1.5X10³ 3.9X10⁴ Nb-97    9.0X10^-1 2.4X10¹ 6.0X10^-1 1.6X10¹ 9.9X10⁵ 2.7X10⁷ Nd-147 Neodymium (60) 6.0 1.6X10² 6.0X10^-1 1.6X10¹ 3.0X10³ 8.1X10⁴ Nd-149    6.0X10^-1 1.6X10¹ 5.0X10^-1 1.4X10¹ 4.5X10⁵ 1.2X10⁷ Ni-59 Nickel (28) Unlimited Unlimited Unlimited Unlimited 3.0X10^-3 8.0X10^-2 Ni-63    4.0X10¹ 1.1X10³ 3.0X10¹ 8.1X10² 2.1 5.7X10¹ Ni-65    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 7.1X10⁵ 1.9X10⁷ Np-235 Neptunium (93) 4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 5.2X10¹ 1.4X10³ Np-236 (short-lived)    2.0X10¹ 5.4X10² 2.0 5.4X10¹ 4.7X10^-4 1.3X10^-2 Np-236 (long-lived)    9.0X10⁰ 2.4X10² 2.0X10^-2 5.4X10^-1 4.7X10^-4 1.3X10^-2 Np-237    2.0X10¹ 5.4X10² 2.0X10^-3 5.4X10^-2 2.6X10^-5 7.1X10^-4 Np-239    7.0 1.9X10² 4.0X10^-1 1.1X10¹ 8.6X10³ 2.3X10⁵ Os-185 Osmium (76) 1.0 2.7X10¹ 1.0 2.7X10¹ 2.8X10² 7.5X10³ Os-191    1.0X10¹ 2.7X10² 2.0 5.4X10¹ 1.6X10³ 4.4X10⁴ Os-191m    4.0X10¹ 1.1X10³ 3.0X10¹ 8.1X10² 4.6X10⁴ 1.3X10⁶ Os-193    2.0 5.4X10¹ 6.0X10^-1 1.6X10¹ 2.0X10⁴ 5.3X10⁵ Os-194 (a)    3.0X10^-1 8.1 3.0X10^-1 8.1 1.1X10¹ 3.1X10² P-32 Phosphorus (15) 5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 1.1X10⁴ 2.9X10⁵ P-33    4.0X10¹ 1.1X10³ 1.0 2.7X10¹ 5.8X10³ 1.6X10⁵ Pa-230 (a) Protactinium (91) 2.0 5.4X10¹ 7.0X10^-2 1.9 1.2X10³ 3.3X10⁴ Pa-231    4.0 1.1X10² 4.0X10^-4 1.1X10^-2 1.7X10^-3 4.7X10^-2 Pa-233    5.0 1.4X10² 7.0X10^-1 1.9X10¹ 7.7X10² 2.1X10⁴ Pb-201 Lead (82) 1.0 2.7X10¹ 1.0 2.7X10¹ 6.2X10⁴ 1.7X10⁶ Pb-202    4.0X10¹ 1.1X10³ 2.0X10¹ 5.4X10² 1.2X10^-4 3.4X10^-3 Pb-203    4.0 1.1X10² 3.0 8.1X10¹ 1.1X10⁴ 3.0X10⁵ Pb-205    Unlimited Unlimited Unlimited Unlimited 4.5X10^-6 1.2X10^-4 Pb-210 (a)    1.0 2.7X10¹ 5.0X10^-2 1.4 2.8 7.6X10¹ Pb-212 (a)    7.0X10^-1 1.9X10¹ 2.0X10^-1 5.4 5.1X10⁴ 1.4X10⁶ Pd-103 (a) Palladium (46) 4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 2.8X10³ 7.5X10⁴ Pd-107    Unlimited Unlimited Unlimited Unlimited 1.9X10^-5 5.1X10^-4 Pd-109    2.0 5.4X10¹ 5.0X10^-1 1.4X10¹ 7.9X10⁴ 2.1X10⁶ Pm-143 Promethium (61) 3.0 8.1X10¹ 3.0 8.1X10¹ 1.3X10² 3.4X10³ Pm-144    7.0X10^-1 1.9X10¹ 7.0X10^-1 1.9X10¹ 9.2X10¹ 2.5X10³ Pm-145    3.0X10¹ 8.1X10² 1.0X10¹ 2.7X10² 5.2 1.4X10² Pm-147    4.0X10¹ 1.1X10³ 2.0 5.4X10¹ 3.4X10¹ 9.3X10² Pm-148m (a)    8.0X10^-1 2.2X10¹ 7.0X10^-1 1.9X10¹ 7.9X10² 2.1X10⁴ Pm-149    2.0 5.4X10¹ 6.0X10^-1 1.6X10¹ 1.5X10⁴ 4.0X10⁵ Pm-151    2.0 5.4X10¹ 6.0X10^-1 1.6X10¹ 2.7X10⁴ 7.3X10⁵ Po-210 Polonium (84) 4.0X10¹ 1.1X10³ 2.0X10^-2 5.4X10^-1 1.7X10² 4.5X10³ Pr-142 Praseodymium (59) 4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 4.3X10⁴ 1.2X10⁶ Pr-143    3.0 8.1X10¹ 6.0X10^-1 1.6X10¹ 2.5X10³ 6.7X10⁴ Pt-188 (a) Platinum (78) 1.0 2.7X10¹ 8.0X10^-1 2.2X10¹ 2.5X10³ 6.8X10⁴ Pt-191    4.0 1.1X10² 3.0 8.1X10¹ 8.7X10³ 2.4X10⁵ Pt-193    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 1.4 3.7X10¹ Pt-193m    4.0X10¹ 1.1X10³ 5.0X10^-1 1.4X10¹ 5.8X10³ 1.6X10⁵ Pt-195m    1.0X10¹ 2.7X10² 5.0X10^-1 1.4X10¹ 6.2X10³ 1.7X10⁵ Pt-197    2.0X10¹ 5.4X10² 6.0X10^-1 1.6X10¹ 3.2X10⁴ 8.7X10⁵ Pt-197m    1.0X10¹ 2.7X10² 6.0X10^-1 1.6X10¹ 3.7X10⁵ 1.0X10⁷ Pu-236 Plutonium (94) 3.0X10¹ 8.1X10² 3.0X10^-3 8.1X10^-2 2.0X10¹ 5.3X10² Pu-237    2.0X10¹ 5.4X10² 2.0X10¹ 5.4X10² 4.5X10² 1.2X10⁴ Pu-238    1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 6.3X10^-1 1.7X10¹ Pu-239    1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 2.3X10^-3 6.2X10^-2 Pu-240    1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 8.4X10^-3 2.3X10^-1 Pu-241 (a)    4.0X10¹ 1.1X10³ 6.0X10^-2 1.6 3.8 1.0X10² Pu-242    1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 1.5X10^-4 3.9X10^-3 Pu-244 (a)    4.0X10^-1 1.1X10¹ 1.0X10^-3 2.7X10^-2 6.7X10^-7 1.8X10^-5 Ra-223 (a) Radium (88) 4.0X10^-1 1.1X10¹ 7.0X10^-3 1.9X10^-1 1.9X10³ 5.1X10⁴ Ra-224 (a)    4.0X10^-1 1.1X10¹ 2.0X10^-2 5.4X10^-1 5.9X10³ 1.6X10⁵ Ra-225 (a)    2.0X10^-1 5.4 4.0X10^-3 1.1X10^-1 1.5X10³ 3.9X10⁴ Ra-226 (a)    2.0X10^-1 5.4 3.0X10^-3 8.1X10^-2 3.7X10^-2 1.0 Ra-228 (a)    6.0X10^-1 1.6X10¹ 2.0X10^-2 5.4X10^-1 1.0X10¹ 2.7X10² Rb-81 Rubidium (37) 2.0 5.4X10¹ 8.0X10^-1 2.2X10¹ 3.1X10⁵ 8.4X10⁶ Rb-83 (a)    2.0 5.4X10¹ 2.0 5.4X10¹ 6.8X10² 1.8X10⁴ Rb-84    1.0 2.7X10¹ 1.0 2.7X10¹ 1.8X10³ 4.7X10⁴ Rb-86    5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 3.0X10³ 8.1X10⁴ Rb-87    Unlimited Unlimited Unlimited Unlimited 3.2X10^-9 8.6X10^-8 Rb(nat)    Unlimited Unlimited Unlimited Unlimited 6.7X10⁶ 1.8X10⁸ Re-184 Rhenium (75) 1.0 2.7X10¹ 1.0 2.7X10¹ 6.9X10² 1.9X10⁴ Re-184m    3.0 8.1X10¹ 1.0 2.7X10¹ 1.6X10² 4.3X10³ Re-186    2.0 5.4X10¹ 6.0X10^-1 1.6X10¹ 6.9X10³ 1.9X10⁵ Re-187    Unlimited Unlimited Unlimited Unlimited 1.4X10^-9 3.8X10^-8 Re-188    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 3.6X10⁴ 9.8X10⁵ Re-189 (a)    3.0 8.1X10¹ 6.0X10^-1 1.6X10¹ 2.5X10⁴ 6.8X10⁵ Re(nat)    Unlimited Unlimited Unlimited Unlimited 0.0 2.4X10^-8 Rh-99 Rhodium (45) 2.0 5.4X10¹ 2.0 5.4X10¹ 3.0X10³ 8.2X10⁴ Rh-101    4.0 1.1X10² 3.0 8.1X10¹ 4.1X10¹ 1.1X10³ Rh-102    5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 4.5X10¹ 1.2X10³ Rh-102m    2.0 5.4X10¹ 2.0 5.4X10¹ 2.3X10² 6.2X10³ Rh-103m    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 1.2X10⁶ 3.3X10⁷ Rh-105    1.0X10¹ 2.7X10² 8.0X10^-1 2.2X10¹ 3.1X10⁴ 8.4X10⁵ Rn-222 (a) Radon (86) 3.0X10^-1 8.1 4.0X10^-3 1.1X10^-1 5.7X10³ 1.5X10⁵ Ru-97 Ruthenium (44) 5.0 1.4X10² 5.0 1.4X10² 1.7X10⁴ 4.6X10⁵ Ru-103 (a)    2.0 5.4X10¹ 2.0 5.4X10¹ 1.2X10³ 3.2X10⁴ Ru-105    1.0 2.7X10¹ 6.0X10^-1 1.6X10¹ 2.5X10⁵ 6.7X10⁶ Ru-106 (a)    2.0X10^-1 5.4 2.0X10^-1 5.4 1.2X10² 3.3X10³ S-35 Sulphur (16) 4.0X10¹ 1.1X10³ 3.0 8.1X10¹ 1.6X10³ 4.3X10⁴ Sb-122 Antimony (51) 4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 1.5X10⁴ 4.0X10⁵ Sb-124    6.0X10^-1 1.6X10¹ 6.0X10^-1 1.6X10¹ 6.5X10² 1.7X10⁴ Sb-125    2.0 5.4X10¹ 1.0 2.7X10¹ 3.9X10¹ 1.0X10³ Sb-126    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 3.1X10³ 8.4X10⁴ Sc-44 Scandium (21) 5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 6.7X10⁵ 1.8X10⁷ Sc-46    5.0X10^-1 1.4X10¹ 5.0X10^-1 1.4X10¹ 1.3X10³ 3.4X10⁴ Sc-47    1.0X10¹ 2.7X10² 7.0X10^-1 1.9X10¹ 3.1X10⁴ 8.3X10⁵ Sc-48    3.0X10^-1 8.1 3.0X10^-1 8.1 5.5X10⁴ 1.5X10⁶ Se-75 Selenium (34) 3.0 8.1X10¹ 3.0 8.1X10¹ 5.4X10² 1.5X10⁴ Se-79    4.0X10¹ 1.1X10³ 2.0 5.4X10¹ 2.6X10^-3 7.0X10^-2 Si-31 Silicon (14) 6.0X10^-1 1.6X10¹ 6.0X10^-1 1.6X10¹ 1.4X10⁶ 3.9X10⁷ Si-32    4.0X10¹ 1.1X10³ 5.0X10^-1 1.4X10¹ 3.9 1.1X10² Sm-145 Samarium (62) 1.0X10¹ 2.7X10² 1.0X10¹ 2.7X10² 9.8X10¹ 2.6X10³ Sm-147    Unlimited Unlimited Unlimited Unlimited 8.5X10^-10 2.3X10^-8 Sm-151    4.0X10¹ 1.1X10³ 1.0X10¹ 2.7X10² 9.7X10^-1 2.6X10¹ Sm-153    9.0 2.4X10² 6.0X10^-1 1.6X10¹ 1.6X10⁴ 4.4X10⁵ Sn-113 (a) Tin (50) 4.0 1.1X10² 2.0 5.4X10¹ 3.7X10² 1.0X10⁴ Sn-117m    7.0 1.9X10² 4.0X10^-1 1.1X10¹ 3.0X10³ 8.2X10⁴ Sn-119m    4.0X10¹ 1.1X10³ 3.0X10¹ 8.1X10² 1.4X10² 3.7X10³ Sn-121m (a)    4.0X10¹ 1.1X10³ 9.0X10^-1 2.4X10¹ 2.0 5.4X10¹ Sn-123    8.0X10^-1 2.2X10¹ 6.0X10^-1 1.6X10¹ 3.0X10² 8.2X10³ Sn-125    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 4.0X10³ 1.1X10⁵ Sn-126 (a)    6.0X10^-1 1.6X10¹ 4.0X10^-1 1.1X10¹ 1.0X10^-3 2.8X10^-2 Sr-82 (a) Strontium (38) 2.0X10^-1 5.4 2.0X10^-1 5.4 2.3X10³ 6.2X10⁴ Sr-85    2.0 5.4X10¹ 2.0 5.4X10¹ 8.8X10² 2.4X10⁴ Sr-85m    5.0 1.4X10² 5.0 1.4X10² 1.2X10⁶ 3.3X10⁷ Sr-87m    3.0 8.1X10¹ 3.0 8.1X10¹ 4.8X10⁵ 1.3X10⁷ Sr-89    6.0X10^-1 1.6X10¹ 6.0X10^-1 1.6X10¹ 1.1X10³ 2.9X10⁴ Sr-90 (a)    3.0X10^-1 8.1 3.0X10^-1 8.1 5.1 1.4X10² Sr-91 (a)    3.0X10^-1 8.1 3.0X10^-1 8.1 1.3X10⁵ 3.6X10⁶ Sr-92 (a)    1.0 2.7X10¹ 3.0X10^-1 8.1 4.7X10⁵ 1.3X10⁷ T (H-3) Tritium (1) 4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 3.6X10² 9.7X10³ Ta-178 (long-lived) Tantalum (73) 1.0 2.7X10¹ 8.0X10^-1 2.2X10¹ 4.2X10⁶ 1.1X10⁸ Ta-179    3.0X10¹ 8.1X10² 3.0X10¹ 8.1X10² 4.1X10¹ 1.1X10³ Ta-182    9.0X10^-1 2.4X10¹ 5.0X10^-1 1.4X10¹ 2.3X10² 6.2X10³ Tb-157 Terbium (65) 4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 5.6X10^-1 1.5X10¹ Tb-158    1.0 2.7X10¹ 1.0 2.7X10¹ 5.6X10^-1 1.5X10¹ Tb-160    1.0 2.7X10¹ 6.0X10^-1 1.6X10¹ 4.2X10² 1.1X10⁴ Tc-95m (a) Technetium (43) 2.0 5.4X10¹ 2.0 5.4X10¹ 8.3X10² 2.2X10⁴ Tc-96    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 1.2X10⁴ 3.2X10⁵ Tc-96m (a)    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 1.4X10⁶ 3.8X10⁷ Tc-97    Unlimited Unlimited Unlimited Unlimited 5.2X10^-5 1.4X10^-3 Tc-97m    4.0X10¹ 1.1X10³ 1.0 2.7X10¹ 5.6X10² 1.5X10⁴ Tc-98    8.0X10^-1 2.2X10¹ 7.0X10^-1 1.9X10¹ 3.2X10^-5 8.7X10^-4 Tc-99    4.0X10¹ 1.1X10³ 9.0X10^-1 2.4X10¹ 6.3X10^-4 1.7X10^-2 Tc-99m    1.0X10¹ 2.7X10² 4.0 1.1X10² 1.9X10⁵ 5.3X10⁶ Te-121 Tellurium (52) 2.0 5.4X10¹ 2.0 5.4X10¹ 2.4X10³ 6.4X10⁴ Te-121m    5.0 1.4X10² 3.0 8.1X10¹ 2.6X10² 7.0X10³ Te-123m    8.0 2.2X10² 1.0 2.7X10¹ 3.3X10² 8.9X10³ Te-125m    2.0X10¹ 5.4X10² 9.0X10^-1 2.4X10¹ 6.7X10² 1.8X10⁴ Te-127    2.0X10¹ 5.4X10² 7.0X10^-1 1.9X10¹ 9.8X10⁴ 2.6X10⁶ Te-127m (a)    2.0X10¹ 5.4X10² 5.0X10^-1 1.4X10¹ 3.5X10² 9.4X10³ Te-129    7.0X10^-1 1.9X10¹ 6.0X10^-1 1.6X10¹ 7.7X10⁵ 2.1X10⁷ Te-129m (a)    8.0X10^-1 2.2X10¹ 4.0X10^-1 1.1X10¹ 1.1X10³ 3.0X10⁴ Te-131m (a)    7.0X10^-1 1.9X10¹ 5.0X10^-1 1.4X10¹ 3.0X10⁴ 8.0X10⁵ Te-132 (a)    5.0X10^-1 1.4X10¹ 4.0X10^-1 1.1X10¹ 1.1X10⁴ 3.0X10⁵ Th-227 Thorium (90) 1.0X10¹ 2.7X10² 5.0X10^-3 1.4X10^-1 1.1X10³ 3.1X10⁴ Th-228 (a)    5.0X10^-1 1.4X10¹ 1.0X10^-3 2.7X10^-2 3.0X10¹ 8.2X10² Th-229    5.0 1.4X10² 5.0X10^-4 1.4X10^-2 7.9X10^-3 2.1X10^-1 Th-230    1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 7.6X10^-4 2.1X10^-2 Th-231    4.0X10¹ 1.1X10³ 2.0X10^-2 5.4X10^-1 2.0X10⁴ 5.3X10⁵ Th-232    Unlimited Unlimited Unlimited Unlimited 4.0X10^-9 1.1X10^-7 Th-234 (a)    3.0X10^-1 8.1 3.0X10^-1 8.1 8.6X10² 2.3X10⁴ Th (natural)    Unlimited Unlimited Unlimited Unlimited 8.1X10^-9 2.2X10^-7 Ti-44 (a) Titanium (22) 5.0X10^-1 1.4X10¹ 4.0X10^-1 1.1X10¹ 6.4 1.7X10² Tl-200 Thallium (81) 9.0X10^-1 2.4X10¹ 9.0X10^-1 2.4X10¹ 2.2X10⁴ 6.0X10⁵ Tl-201    1.0X10¹ 2.7X10² 4.0 1.1X10² 7.9X10³ 2.1X10⁵ Tl-202    2.0 5.4X10¹ 2.0 5.4X10¹ 2.0X10³ 5.3X10⁴ Tl-204    1.0X10¹ 2.7X10² 7.0X10^-1 1.9X10¹ 1.7X10¹ 4.6X10² Tm-167 Thulium (69) 7.0 1.9X10² 8.0X10^-1 2.2X10¹ 3.1X10³ 8.5X10⁴ Tm-170    3.0 8.1X10¹ 6.0X10^-1 1.6X10¹ 2.2X10² 6.0X10³ Tm-171    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ U-230 (fast lung absorption) (a)(d) Uranium (92) 4.0X10¹ 1.1X10³ 1.0X10^-1 2.7 1.0X10³ 2.7X10⁴ U-230 (medium lung absorption) (a) (e)    4.0X10¹ 1.1X10³ 4.0X10^-3 1.1X10^-1 1.0X10³ 2.7X10⁴ U-230 (slow lung absorption) (a)(f)    3.0X10¹ 8.1X10² 3.0X10^-3 8.1X10^-2 1.0X10³ 2.7X10⁴ U-232 (fast lung absorption) (d)    4.0X10¹ 1.1X10³ 1.0X10^-2 2.7X10^-1 8.3X10^-1 2.2X10¹ U-232 (medium lung absorption) (e)    4.0X10¹ 1.1X10³ 7.0X10^-3 1.9X10^-1 8.3X10^-1 2.2X10¹ U-232 (slow lung absorption) (f)    1.0X10¹ 2.7X10² 1.0X10^-3 2.7X10^-2 8.3X10^-1 2.2X10¹ U-233 (fast lung absorption) (d)    4.0X10¹ 1.1X10³ 9.0X10^-2 2.4 3.6X10^-4 9.7X10^-3 U-233 (medium lung absorption) (e)    4.0X10¹ 1.1X10³ 2.0X10^-2 5.4X10^-1 3.6X10^-4 9.7X10^-3 U-233 (slow lung absorption) (f)    4.0X10¹ 1.1X10³ 6.0X10^-3 1.6X10^-1 3.6X10^-4 9.7X10^-3 U-234 (fast lung absorption) (d)    4.0X10¹ 1.1X10³ 9.0X10^-2 2.4 2.3X10^-4 6.2X10^-3 U-234 (medium lung absorption) (e)    4.0X10¹ 1.1X10³ 2.0X10^-2 5.4X10^-1 2.3X10^-4 6.2X10^-3 U-234 (slow lung absorption) (f)    4.0X10¹ 1.1X10³ 6.0X10^-3 1.6X10^-1 2.3X10^-4 6.2X10^-3 U-235 (all lung absorption types) (a), (d),(e),(f)    Unlimited Unlimited Unlimited Unlimited 8.0X10^-8 2.2X10^-6 U-236 (fast lung absorption) (d)    Unlimited Unlimited Unlimited Unlimited 2.4X10^-6 6.5X10^-5 U-236 (medium lung absorption) (e)    4.0X10¹ 1.1X10³ 2.0X10^-2 5.4X10^-1 2.4X10^-6 6.5X10^-5 U-236 (slow lung absorption) (f)    4.0X10¹ 1.1X10³ 6.0X10^-3 1.6X10^-1 2.4X10^-6 6.5X10^-5 U-238 (all lung absorption types) (d),(e),(f)    Unlimited Unlimited Unlimited Unlimited 1.2X10^-8 3.4X10^-7 U (natural)    Unlimited Unlimited Unlimited Unlimited 2.6X10^-8 7.1X10^-7 U (enriched to 20% or less) (g)    Unlimited Unlimited Unlimited Unlimited See Table 6 See Table 6 U (dep)    Unlimited Unlimited Unlimited Unlimited See Table See Table V-48 Vanadium (23) 4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10^{1 6}6.3X10^{3 5}1.7X10⁵ V-49    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 3.0X10² 8.1X10³ W-178 (a) Tungsten (74) 9.0 2.4X10² 5.0 1.4X10² 1.3X10³ 3.4X10⁴ W-181    3.0X10¹ 8.1X10² 3.0X10¹ 8.1X10² 2.2X10² 6.0X10³ W-185    4.0X10¹ 1.1X10³ 8.0X10^-1 2.2X10¹ 3.5X10² 9.4X10³ W-187    2.0 5.4X10¹ 6.0X10^-1 1.6X10¹ 2.6X10⁴ 7.0X10⁵ W-188 (a)    4.0X10^-1 1.1X10¹ 3.0X10^-1 8.1 3.7X10² 1.0X10⁴ Xe-122 (a) Xenon (54) 4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 4.8X10⁴ 1.3X10⁶ Xe-123    2.0 5.4X10¹ 7.0X10^-1 1.9X10¹ 4.4X10⁵ 1.2X10⁷ Xe-127    4.0 1.1X10² 2.0 5.4X10¹ 1.0X10³ 2.8X10⁴ Xe-131m    4.0X10¹ 1.1X10³ 4.0X10¹ 1.1X10³ 3.1X10³ 8.4X10⁴ Xe-133    2.0X10¹ 5.4X10² 1.0X10¹ 2.7X10² 6.9X10³ 1.9X10⁵ Xe-135    3.0 8.1X10¹ 2.0 5.4X10¹ 9.5X10⁴ 2.6X10⁶ Y-87 (a) Yttrium (39) 1.0 2.7X10¹ 1.0 2.7X10¹ 1.7X10⁴ 4.5X10⁵ Y-88    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 5.2X10² 1.4X10⁴ Y-90    3.0X10^-1 8.1 3.0X10^-1 8.1 2.0X10⁴ 5.4X10⁵ Y-91    6.0X10^-1 1.6X10¹ 6.0X10^-1 1.6X10¹ 9.1X10² 2.5X10⁴ Y-91m    2.0 5.4X10¹ 2.0 5.4X10¹ 1.5X10⁶ 4.2X10⁷ Y-92    2.0X10^-1 5.4 2.0X10^-1 5.4 3.6X10⁵ 9.6X10⁶ Y-93    3.0X10^-1 8.1 3.0X10^-1 8.1 1.2X10⁵ 3.3X10⁶ Yb-169 Ytterbium (70) 4.0 1.1X10² 1.0 2.7X10¹ 8.9X10² 2.4X10⁴ Yb-175    3.0X10¹ 8.1X10² 9.0X10^-1 2.4X10¹ 6.6X10³ 1.8X10⁵ Zn-65 Zinc (30) 2.0 5.4X10¹ 2.0 5.4X10¹ 3.0X10² 8.2X10³ Zn-69    3.0 8.1X10¹ 6.0X10^-1 1.6X10¹ 1.8X10⁶ 4.9X10⁷ Zn-69m (a)    3.0 8.1X10¹ 6.0X10^-1 1.6X10¹ 1.2X10⁵ 3.3X10⁶ Zr-88 Zirconium (40) 3.0 8.1X10¹ 3.0 8.1X10¹ 6.6X10² 1.8X10⁴ Zr-93    Unlimited Unlimited Unlimited Unlimited 9.3X10^-5 2.5X10^-3 Zr-95 (a)    2.0 5.4X10¹ 8.0X10^-1 2.2X10¹ 7.9X10² 2.1X10⁴ Zr-97 (a)    4.0X10^-1 1.1X10¹ 4.0X10^-1 1.1X10¹ 7.1X10⁴ 1.9X10^{6 a} A₁ and/or A₂ values include contributions from daughter nuclides with half-lives less than 10 days as listed in Table 4-A. ^bThe values of A₁ and A₂ in Curies (Ci) are approximate and for information only; the regulatory standard units are Terabecquerels (TBq). ^c The activity of Ir-192 in special form may be determined from a measurement of the rate of decay or a measurement of the radiation level at a prescribed distance from the source. ^d These values apply only to compounds of uranium that take the chemical form of UF₆, UO₂F₂ and UO₂(NO₃)₂ in both normal and accident conditions of transport. ^e These values apply only to compounds of uranium that take the chemical form of UO₃, UF₄, UCl₄ and hexavalent compounds in both normal and accident conditions of transport. ^f These values apply to all compounds of uranium other than those specified in notes (d) and (e) of this table. ^g These values apply to unirradiated uranium only. ^h A₂ = 0.74 TBq (20 Ci) for Mo-99 for domestic use. TABLE 4-A - DAUGHTER NUCLIDES WITH HALF-LIVES LESS THAN 10 DAYS Parent Nuclide Daughter Nuclide(s) Mg-28 Al-28                   Ca-47 Sc-47                   Ti-44 Sc-44                   Fe-52 Mn-52m                   Fe-60 Co-60m                   Zn-69m Zn-69                   Ge-68 Ga-68                   Rb-83 Kr-83m                   Sr-82 Rb-82                   Sr-90 Y-90                   Sr-91 Y-91m                   Sr-92 Y-92                   Y-87 Sr-87m                   Zr-95 Nb-95m                   Zr-97 Nb-97m, Nb-97                Mo-99 Tc-99m                   Tc-95m Tc-95                   Tc-96m Tc-96                   Ru-103 Rh-103m                   Ru-106 Rh-106                   Pd-103 Rh-103m                   Ag-108m Ag-108                   Ag-110m Ag-110                   Cd-115 In-115m                   In-114m In-114                   Sn-113 In-113m                   Sn-121m Sn-121                   Sn-126 Sb-126m                   Te-127m Te-127                   Te-129m Te-129                   Te-131m Te-131                   Te-132 I-132                   I-135 Xe-135m                   Xe-122 I-122                   Cs-137 Ba-137m                   Ba-131 Cs-131                   Ba-140 La-140                   Ce-144 Pr-144m, Pr-144                Pm-148m Pm-148                   Gd-146 Eu-146                   Dy-166 Ho-166                   Hf-172 Lu-172                   W-178 Ta-178                   W-188 Re-188                   Re-189 Os-189m                   Os-194 Ir-194                   Ir-189 Os-189m                   Pt-188 Ir-188                   Hg-194 Au-194                   Hg-195m Hg-195                   Pb-210 Bi-210                   Pb-212 Bi-212, Tl-208, Po-212             Bi-210m Tl-206                   Bi-212 Tl-208, Po-212                At-211 Po-211                   Rn-222 Po-218, Pb-214, At-218, Bi-214, Po-214       Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207    Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212    Ra-225 Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209 Ra-226 Rn-222, Po-218, Pb-214, At-218, Bi-214, Po-214    Ra-228 Ac-228                   Ac-225 Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209    Ac-227 Fr-223                   Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 Th-234 Pa-234m, Pa-234                Pa-230 Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214    U-230 Th-226, Ra-222, Rn-218, Po-214          U-235 Th-231                   Pu-241 U-237                   Pu-244 U-240, Np-240m                Am-242m Am-242, Np-238                Am-243 Np-239                   Cm-247 Pu-243                   Bk-249 Am-245                   TABLE 5 - GENERAL VALUES FOR A₁ AND A₂ Contents A₁ A₂ Activity concentration for exempt material (Bq/g) Activity concentration for exempt material (Ci/g) Activity limits for exempt consignments (Bq) Activity limits for exempt consignments (Ci) (TBq) (Ci) (TBq) (Ci) Only beta or gamma emitting radionuclides are known to be present 1 x 10^-1 2.7 x 10⁰ 2 x 10 ^-2 5.4 x 10^-1 1 x 10¹ 2.7 x10^-10 1 x 10⁴ 2.7 x10^-7 Alpha emitting nuclides, but no neutron emitters, are known to be present^a 2 x 10^-1 5.4 x 10⁰ 9 x 10^-5 2.4 x 10^-3 1 x 10^-1 2.7 x10^-12 1 x 10³ 2.7 x10^-8 Neutron emitting nuclides are known to be present or no relevant data are available 1 x 10^-3 2.7 x 10^-2 9 x 10^-5 2.4 x 10^-3 1 x 10^-1 2.7 x 10^-12 1 x 10³ 2.7 x 10^{-8 a} If beta or gamma emitting nuclides are known to be present, the A₁ value of 0.1 TBq (2.7 Ci) should be used. TABLE 6 - ACTIVITY-MASS RELATIONSHIPS FOR URANIUM Uranium Enrichment¹ wt % U-235 present Specific Activity TBq/g Ci/g 0.45 1.8 x 10^-8 5.0 x 10^-7 0.72 2.6 x 10^-8 7.1 x 10^-7 1 2.8 x 10^-8 7.6 x 10^-7 1.5 3.7 x 10^-8 1.0 x 10^-6 5 1.0 x 10^-7 2.7 x 10^-6 10 1.8 x 10^-7 4.8 x 10^-6 20 3.7 x 10^-7 1.0 x 10^-5 35 7.4 x 10^-7 2.0 x 10^-5 50 9.3 x 10^-7 2.5 x 10^-5 90 2.2 x 10^-6 5.8 x 10^-5 93 2.6 x 10^-6 7.0 x 10^-5 95 3.4 x 10^-6 9.1 x 10^{-5 1} The figures for uranium include representative values for the activity of the uranium-234 that is concentrated during the enrichment process. Table 7 - EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES Symbol of radionuclide Element and atomic number Activity concentration for exempt material (Bq/g) Activity concentration for exempt material (Ci/g) Activity limit for exempt consignment (Bq) Activity limit for exempt consignment (Ci) Ac-225 Actinium (89) 1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Ac-227    1.0X10^-1 2.7X10^-12 1.0X10³ 2.7X10^-8 Ac-228    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Ag-105 Silver (47) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ag-108m (b)    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Ag-110m    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Ag-111    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Al-26 Aluminum (13) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Am-241 Americium (95) 1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Am-242m (b)    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Am-243 (b)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Ar-37 Argon (18) 1.0X10⁶ 2.7X10^-5 1.0X10⁸ 2.7X10^-3 Ar-39    1.0X10⁷ 2.7X10^-4 1.0X10⁴ 2.7X10^-7 Ar-41    1.0X10² 2.7X10^-9 1.0X10⁹ 2.7X10^-2 As-72 Arsenic (33) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 As-73    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 As-74    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 As-76    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 As-77    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 At-211 Astatine (85) 1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Au-193 Gold (79) 1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Au-194    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Au-195    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Au-198    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Au-199    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ba-131 Barium (56) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ba-133    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ba-133m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ba-140 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Be-7 Beryllium (4) 1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Be-10    1.0X10⁴ 2.7X10^-7 1.0X10⁶ 2.7X10^-5 Bi-205 Bismuth (83) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Bi-206    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Bi-207    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Bi-210    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Bi-210m    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Bi-212 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Bk-247 Berkelium (97) 1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Bk-249    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Br-76 Bromine (35) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Br-77    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Br-82    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 C-11 Carbon (6) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 C-14    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Ca-41 Calcium (20) 1.0X10⁵ 2.7X10^-6 1.0X10⁷ 2.7X10^-4 Ca-45    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Ca-47    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Cd-109 Cadmium (48) 1.0X10⁴ 2.7X10^-7 1.0X10⁶ 2.7X10^-5 Cd-113m    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Cd-115    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Cd-115m    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Ce-139 Cerium (58) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ce-141    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Ce-143    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ce-144 (b)    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Cf-248 Californium (98) 1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Cf-249    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Cf-250    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Cf-251    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Cf-252    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Cf-253    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Cf-254    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Cl-36 Chlorine (17) 1.0X10⁴ 2.7X10^-7 1.0X10⁶ 2.7X10^-5 Cl-38    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Cm-240 Curium (96) 1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Cm-241    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Cm-242    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Cm-243    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Cm-244    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Cm-245    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Cm-246    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Cm-247    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Cm-248    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Co-55 Cobalt (27) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Co-56    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Co-57    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Co-58    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Co-58m    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Co-60    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Cr-51 Chromium (24) 1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Cs-129 Cesium (55) 1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Cs-131    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Cs-132    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Cs-134    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Cs-134m    1.0X10³ 2.7X10^-8 1.0X10⁵ 2.7X10^-6 Cs-135    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Cs-136    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Cs-137 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Cu-64 Copper (29) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Cu-67    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Dy-159 Dysprosium (66) 1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Dy-165    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Dy-166    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Er-169 Erbium (68) 1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Er-171    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Eu-147 Europium (63) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Eu-148    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Eu-149    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Eu-150 (short lived)    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Eu-150 (long lived)    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Eu-152    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Eu-152m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Eu-154    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Eu-155    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Eu-156    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 F-18 Fluorine (9) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Fe-52 Iron (26) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Fe-55    1.0X10⁴ 2.7X10^-7 1.0X10⁶ 2.7X10^-5 Fe-59    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Fe-60    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Ga-67 Gallium (31) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ga-68    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Ga-72    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Gd-146 Gadolinium (64) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Gd-148    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Gd-153    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Gd-159    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Ge-68 Germanium (32) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Ge-71    1.0X10⁴ 2.7X10^-7 1.0X10⁸ 2.7X10^-3 Ge-77    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Hf-172 Hafnium (72) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Hf-175    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Hf-181    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Hf-182    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Hg-194 Mercury (80) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Hg-195m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Hg-197    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Hg-197m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Hg-203    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Ho-166 Holmium (67) 1.0X10³ 2.7X10^-8 1.0X10⁵ 2.7X10^-6 Ho-166m    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 I-123 Iodine (53) 1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 I-124    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 I-125    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 I-126    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 I-129    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 I-131    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 I-132    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 I-133    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 I-134    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 I-135    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 In-111 Indium (49) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 In-113m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 In-114m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 In-115m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ir-189 Iridium (77) 1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Ir-190    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Ir-192    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Ir-194    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 K-40 Potassium (19) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 K-42    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 K-43    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Kr-79 Krypton (36) 1.0X10³ 2.7X10^-8 1.0X10⁵ 2.7X10^-6 Kr-81    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Kr-85    1.0X10⁵ 2.7X10^-6 1.0X10⁴ 2.7X10^-7 Kr-85m    1.0X10³ 2.7X10^-8 1.0X10¹⁰ 2.7X10^-1 Kr-87    1.0X10¹ 2.7X10^-9 1.0X10⁹ 2.7X10^-2 La-137 Lanthanum (57) 1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 La-140    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Lu-172 Lutetium (71) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Lu-173    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Lu-174    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Lu-174m    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Lu-177    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Mg-28 Magnesium (12) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Mn-52 Manganese (25) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Mn-53    1.0X10⁴ 2.7X10^-7 1.0X10⁹ 2.7X10^-2 Mn-54    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Mn-56    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Mo-93 Molybdenum (42) 1.0X10³ 2.7X10^-8 1.0X10⁸ 2.7X10^-3 Mo-99    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 N-13 Nitrogen (7) 1.0X10² 2.7X10^-9 1.0X10⁹ 2.7X10^-2 Na-22 Sodium (11) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Na-24    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Nb-93m Niobium (41) 1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Nb-94    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Nb-95    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Nb-97    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Nd-147 Neodymium (60) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Nd-149    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ni-59 Nickel (28) 1.0X10⁴ 2.7X10^-7 1.0X10⁸ 2.7X10^-3 Ni-63    1.0X10⁵ 2.7X10^-6 1.0X10⁸ 2.7X10^-3 Ni-65    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Np-235 Neptunium (93) 1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Np-236 (short-lived)    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Np-236 (long-lived)    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Np-237 (b)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Np-239    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Os-185 Osmium (76) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Os-191    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Os-191m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Os-193    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Os-194    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 P-32 Phosphorus (15) 1.0X10³ 2.7X10^-8 1.0X10⁵ 2.7X10^-6 P-33    1.0X10⁵ 2.7X10^-6 1.0X10⁸ 2.7X10^-3 Pa-230 Protactinium (91) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Pa-231    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Pa-233    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Pb-201 Lead (82) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Pb-202    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Pb-203    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Pb-205    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Pb-210 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Pb-212 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Pd-103 Palladium (46) 1.0X10³ 2.7X10^-8 1.0X10⁸ 2.7X10^-3 Pd-107    1.0X10⁵ 2.7X10^-6 1.0X10⁸ 2.7X10^-3 Pd-109    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Pm-143 Promethium (61) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Pm-144    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Pm-145    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Pm-147    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Pm-148m    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Pm-149    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Pm-151    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Po-210 Polonium (84) 1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Pr-142 Praseodymium (59) 1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Pr-143    1.0X10⁴ 2.7X10^-7 1.0X10⁶ 2.7X10^-5 Pt-188 Platinum (78) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Pt-191    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Pt-193    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Pt-193m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Pt-195m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Pt-197    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Pt-197m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Pu-236 Plutonium (94) 1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Pu-237    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Pu-238    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Pu-239    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Pu-240    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Pu-241    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Pu-242    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Pu-244    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Ra-223 (b) Radium (88) 1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Ra-224 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Ra-225    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Ra-226 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Ra-228 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Rb-81 Rubidium (37) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Rb-83    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Rb-84    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Rb-86    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Rb-87    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Rb(nat)    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Re-184 Rhenium (75) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Re-184m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Re-186    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Re-187    1.0X10⁶ 2.7X10^-5 1.0X10⁹ 2.7X10^-2 Re-188    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Re-189    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Re(nat)    1.0X10⁶ 2.7X10^-5 1.0X10⁹ 2.7X10^-2 Rh-99 Rhodium (45) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Rh-101    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Rh-102    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Rh-102m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Rh-103m    1.0X10⁴ 2.7X10^-7 1.0X10⁸ 2.7X10^-3 Rh-105    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Rn-222 (b) Radon (86) 1.0X10¹ 2.7X10^-10 1.0X10⁸ 2.7X10^-3 Ru-97 Ruthenium (44) 1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Ru-103    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Ru-105    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Ru-106 (b)    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 S-35 Sulphur (16) 1.0X10⁵ 2.7X10^-6 1.0X10⁸ 2.7X10^-3 Sb-122 Antimony (51) 1.0X10² 2.7X10^-9 1.0X10⁴ 2.7X10^-7 Sb-124    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Sb-125    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Sb-126    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Sc-44 Scandium (21) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Sc-46    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Sc-47    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Sc-48    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Se-75 Selenium (34) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Se-79    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Si-31 Silicon (14) 1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Si-32    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Sm-145 Samarium (62) 1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Sm-147    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Sm-151    1.0X10⁴ 2.7X10^-7 1.0X10⁸ 2.7X10^-3 Sm-153    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Sn-113 Tin (50) 1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Sn-117m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Sn-119m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Sn-121m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Sn-123    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Sn-125    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Sn-126    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Sr-82 Strontium (38) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Sr-85    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Sr-85m    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Sr-87m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Sr-89    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Sr-90 (b)    1.0X10² 2.7X10^-9 1.0X10⁴ 2.7X10^-7 Sr-91    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Sr-92    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 T (H-3) Tritium (1) 1.0X10⁶ 2.7X10^-5 1.0X10⁹ 2.7X10^-2 Ta-178 (long-lived) Tantalum (73) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Ta-179    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Ta-182    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Tb-157 Terbium (65) 1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Tb-158    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Tb-160    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Tc-95m Technetium (43) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Tc-96    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Tc-96m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Tc-97    1.0X10³ 2.7X10^-8 1.0X10⁸ 2.7X10^-3 Tc-97m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Tc-98    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Tc-99    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 Tc-99m    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Te-121 Tellurium (52) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Te-121m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Te-123m    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Te-125m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Te-127    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Te-127m    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Te-129    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Te-129m    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Te-131m    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Te-132    1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Th-227 Thorium (90) 1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Th-228 (b)    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Th-229 (b)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Th-230    1.0 2.7X10^-11 1.0X10⁴ 2.7X10^-7 Th-231    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Th-232    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 Th-234 (b)    1.0X10³ 2.7X10^-8 1.0X10⁵ 2.7X10^-6 Th (nat) (b)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 Ti-44 Titanium (22) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 Tl-200 Thallium (81) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Tl-201    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Tl-202    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Tl-204    1.0X10⁴ 2.7X10^-7 1.0X10⁴ 2.7X10^-7 Tm-167 Thulium (69) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Tm-170    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Tm-171    1.0X10⁴ 2.7X10^-7 1.0X10⁸ 2.7X10^-3 U-230 (fast lung absorption) (b),(d) Uranium (92) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 U-230 (medium lung absorption) (e)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-230 (slow lung absorption) (f)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-232 (fast lung absorption) (b),(d)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 U-232 (medium lung absorption) (e)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-232 (slow lung absorption) (f)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-233 (fast lung absorption) (d)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-233 (medium lung absorption) (e)    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 U-233 (slow lung absorption) (f)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 U-234 (fast lung absorption) (d)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-234 (medium lung absorption) (e)    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 U-234 (slow lung absorption) (f)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 U-235 (all lung absorption types) (b),(d),(e),(f)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-236 (fast lung absorption) (d)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-236 (medium lung absorption) (e)    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 U-236 (slow lung absorption) (f)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U-238 (all lung absorption types) (b),(d),(e),(f)    1.0X10¹ 2.7X10^-10 1.0X10⁴ 2.7X10^-7 U (natural) (b)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 U (enriched to 20% or less) (g)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 U (dep)    1.0 2.7X10^-11 1.0X10³ 2.7X10^-8 V-48 Vanadium (23) 1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^-6 V-49    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 W-178 Tungsten (74) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 W-181    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 W-185    1.0X10⁴ 2.7X10^-7 1.0X10⁷ 2.7X10^-4 W-187    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 W-188    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Xe-122 Xenon (54) 1.0X10² 2.7X10^-9 1.0X10⁹ 2.7X10^-2 Xe-123    1.0X10² 2.7X10^-9 1.0X10⁹ 2.7X10^-2 Xe-127    1.0X10³ 2.7X10^-8 1.0X10⁵ 2.7X10^-6 Xe-131m    1.0X10⁴ 2.7X10^-7 1.0X10⁴ 2.7X10^-7 Xe-133    1.0X10³ 2.7X10^-8 1.0X10⁴ 2.7X10^-7 Xe-135    1.0X10³ 2.7X10^-8 1.0X10¹⁰ 2.7X10^-1 Y-87 Yttrium (39) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Y-88    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Y-90    1.0X10³ 2.7X10^-8 1.0X10⁵ 2.7X10^-6 Y-91    1.0X10³ 2.7X10^-8 1.0X10⁶ 2.7X10^-5 Y-91m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Y-92    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Y-93    1.0X10² 2.7X10^-9 1.0X10⁵ 2.7X10^-6 Yb-169 Ytterbium (70) 1.0X10² 2.7X10^-9 1.0X10⁷ 2.7X10^-4 Yb-175    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Zn-65 Zinc (30) 1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Zn-69    1.0X10⁴ 2.7X10^-7 1.0X10⁶ 2.7X10^-5 Zn-69m    1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Zr-88 Zirconium (40) 1.0X10² 2.7X10^-9 1.0X10⁶ 2.7X10^-5 Zr-93 (b)    1.0X10³ 2.7X10^-8 1.0X10⁷ 2.7X10^-4 Zr-95    1.0X10¹ 2.7X10^-10 1.0X10⁶ 2.7X10^-5 Zr-97 (b)    1.0X10¹ 2.7X10^-10 1.0X10⁵ 2.7X10^{-6 a} [Reserved] ^b Parent nuclides and their progeny included in secular equilibrium are listed in the following: Sr-90 Y-90 Zr-93 Nb-93m Zr-97 Nb-97 Ru-106 Rh-106 Cs-137 Ba-137m Ce-144 Pr-144 Ba-140 La-140 Bi-212 Tl-208 (0.36), Po-212 (0.64) Pb-210 Bi-210, Po-210 Pb-212 Bi-212, Tl-208 (0.36), Po-212 (0.64) Rn-222 Po-218, Pb-214, Bi-214, Po-214 Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Tl-207 Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208(0.36), Po-212 (0.64) Ra-226 Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 Ra-228 Ac-228 Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64) Th-229 Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209 Th-nat Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64) Th-234 Pa-234m U-230 Th-226, Ra-222, Rn-218, Po-214 U-232 Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64) U-235 Th-231 U-238 Th-234, Pa-234m U-nat Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 Np-237 Pa-233 Am-242m Am-242 Am-243 Np-239 ^c [Reserved] ^d These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident conditions of transport. ^e These values apply only to compounds of uranium that take the chemical form of UO3, UF4, UCl4 and hexavalent compounds in both normal and accident conditions of transport. ^f These values apply to all compounds of uranium other than those specified in notes (d) and (e) of this table. ^g These values apply to unirradiated uranium only.

Authority: O.C.G.A. § 31-13-1et seq.

History. Original Rule entitled "Transportation of Radioactive Material" adopted. F. May 2, 1991; eff. May 22, 1991.

Amended: F. Feb. 24, 1994; eff. Mar. 16, 1994.

Amended: F. Oct. 4, 1994; eff. Oct. 24, 1994.

Amended: F. Apr. 16, 1997; eff. May 6, 1997.

Amended: F. Mar. 29, 2002; eff. Apr. 18, 2002.

Amended: F. Oct. 17, 2008; eff. Nov. 6, 2008.

Amended: F. Apr. 11, 2016; eff. May 1, 2016.

Amended: F. May 11, 2016; eff. May 31, 2016.

Amended: F. June 1, 2017; eff. June 21, 2017.

Amended: F. Dec. 14, 2017; eff. Jan. 3, 2018

Amended: F. Jan. 28, 2019; eff. Feb. 17, 2019.

Amended: F. Mar. 24, 2021; eff. Apr. 13, 2021.

Amended: F. Mar. 30, 2022; eff. Apr. 19, 2022.