Definitions.

CFR · 2024-01-01 · US · Title 10

(a) The following definitions apply to this part: (1) The relative importance to safety, safeguards, and security; (2) The magnitude of any hazard involved; (3) The life cycle stage of a facility; (4) The programmatic mission of a facility; (5) The particular characteristics of a facility; (6) The relative importance of radiological and nonradiological hazards; and (7) Any other relevant factor. (1) Physical, design, structural, and engineering features; (2) Safety structures, systems, and components; (3) Safety management programs; (4) Technical safety requirements; and (5) Other controls necessary to provide adequate protection from hazards. (1) The nuclear safety design criteria to be satisfied; (2) A safety analysis that derives aspects of design that are necessary to satisfy the nuclear safety design criteria; and (3) An initial listing of the safety management programs that must be (1) The sufficiency of the documented safety analysis for a Hazard Category 1, 2, or 3 DOE nuclear facility; (2) The extent to which a contractor has satisfied the requirements of Subpart B of this part; and (3) The basis for approval by DOE of the safety basis for the facility, including any conditions for approval. (1) The probability of the occurrence or the consequences of an accident or the malfunction of equipment important to safety previously evaluated in the documented safety analysis could be increased; (2) The possibility of an accident or malfunction of a different type than any e

official document · source cfr-2024 · id 10:§ 830.3