LSA material
Low Specific Activity (LSA) material means Class 7 material with limited specific activity which is not fissile material or is excepted under 173.453, and which satisfies the descriptions and limits set forth below. Shielding material surrounding the LSA material may not be considered in determining the estimated average specific activity of the LSA material. LSA material must be in one of three groups:
(1) LSA–I:
(i) Uranium and thorium ores, concentrates of uranium and thorium ores, and other ores containing naturally occurring radionuclides which are intended to be processed for the use of these radionuclides; or
(ii) Natural uranium, depleted uranium, natural thorium or their compounds or mixtures, provided they are unirradiated and in solid or liquid form; or
(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 values for activity concentration specified in § 173.436 or calculated in accordance with § 173.433, or 30 times the default values listed in Table 8 of § 173.433.
(2) LSA–II:
(i) Water with tritium concentration up to 0.8 TBq/L (20.0 Ci/L); or
(ii) Other radioactive 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.
(3) LSA–III. Solids (e.g., consolidated wastes, activated materials), excluding powders, that meet the requirements of § 173.468 and 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 (such as 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 Class 7 (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, excluding any shielding material, does not exceed 2 × 10−3 A2/g.