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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.
Fissile Material—the radionuclides plutonium-239, plutonium-241, uranium-233, uranium-235, or any combination of these radionuclides. Fissile material means the fissile nuclides themselves, not material containing fissile nuclides. Unirradiated natural uranium and depleted uranium, and 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 LAC 33:XV.1505.C.
Graphitefor the purposes of LAC 33:XV.1505.C and 1511, graphite with a boron equivalent content less than 5 parts per million and density greater than 1.5 grams per cubic centimeter.
Licensed Materialbyproduct, source, or special nuclear material that is received, possessed, used, or transferred under a general or specific license issued by the department in accordance with this Chapter.
Low Specific Activity (LSA) Materialradioactive material with limited specific activity that is nonfissile or that is excepted under LAC 33:XV.1505.C, and that 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. LSA material must be in one of three groups:
i.uranium and thorium ores, concentrates of uranium and thorium ores, and other ores containing naturally occurring radioactive radionuclides that are not intended to be processed for the use of these radionuclides;
ii.solid unirradiated natural uranium, depleted uranium, natural thorium, or their solid or liquid compounds or mixtures;
iii.radioactive material for which the A2 value is unlimited; or
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 LAC 33:XV.1599.E.
i.water with tritium concentration up to 0.8 TBq/liter (20.0 Ci/liter); or
ii.other material in which the activity is distributed throughout, and the average specific activity does not exceed 10-4 A2/g for solids and gases, and 10-5 A2/g for liquids.
c.LSA-III. Solids (e.g., consolidated wastes, activated materials), excluding powders, that satisfy the requirements of 10 CFR 71.77, in which:
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 (e. g., concrete, bitumen, ceramic, etc.);
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
iii.the estimated average specific activity of the solid does not exceed 2 x 10-3 A2/g.
Low Toxicity Alpha Emittersnatural uranium, depleted uranium, and 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.
Maximum Normal Operating Pressurethe 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.
Natural Thoriumthorium with the naturally occurring distribution of thorium isotopes (essentially 100 weight percent thorium-232).
Normal Form Radioactive Materialradioactive material which has not been demonstrated to qualify as special form radioactive material.
Optimum Interspersed Hydrogenous Moderationthe presence of hydrogenous material between packages to such an extent that the maximum nuclear reactivity results.
Packagethe packaging together with its radioactive contents as presented for transport.
a.Fissile Material Package, Type AF Package, Type BF Package, Type B(U)F Package, or Type B(M)F Packagea fissile material packaging together with its fissile material contents.
b.Type A Packagea Type A packaging together with its radioactive contents. A Type A package is defined and must comply with the U.S. DOT regulations in 49 CFR Part 173.
c.Type B Packagea Type B packaging together with its radioactive contents. On approval, a Type B package design is designated by the 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 71.73 (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 U.S. 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 10 CFR 71.19.
Packagingthe assembly of components necessary to ensure compliance with the packaging requirements of this Chapter. It may consist of one or more receptacles, absorbent materials, spacing structures, thermal insulation, radiation shielding, and devices for cooling or absorbing

Louisiana Register   Vol. 34, No. 10   October 20, 2008

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