§ 54.4. Scope.
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/us/cfr/t10/s§ 54.4·A research copy — for the controlling text, always check the official state or federal source. Not legal advice.
(a)Plant systems, structures, and components within the scope of this part are—
(1)Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following functions—
(i)The integrity of the reactor coolant pressure boundary;
(ii)The capability to shut down the reactor and maintain it in a safe shutdown condition; or
(iii)The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in § 50.34(a)(1), § 50.67(b)(2), or § 100.11 of this chapter, as applicable.
(2)All nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of any of the functions identified in paragraphs (a)(1) (i), (ii), or
(iii)of this section.
(3)All systems, structures, and components relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48), environmental qualification (10 CFR 50.49), pressurized thermal shock (10 CFR 50.61), anticipated transients without scram (10 CFR 50.62), and station blackout (10 CFR 50.63).
(b)The intended functions that these systems, structures, and components must be shown to fulfill in § 54.21 are those functions that are the bases for including them within the scope of license renewal as specified in paragraphs
(a)(1)-(3) of this section. [60 FR 22491, May 8, 1995, as amended at 61 FR 65175, Dec. 11, 1996; 64 FR 72002, Dec. 23, 1999]
Connections21 cite this · traces to 5
Cited by 21 sections · top 7
Traces to 5 documents
CFR
- Environmental qualification of electric equipment important to safety for nuclear power plants.§ 50.49
- Fire protection.§ 50.48
- Fracture toughness requirements for protection against pressurized thermal shock events.§ 50.61
- Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants.§ 50.62
- Loss of all alternating current power.§ 50.63
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