Document: NRC Regulatory Guide
Document ID: fe0fff83-b171-47c6-a3a7-46faf8de3252
Document Type: regulatory_guide
Title: Criteria for The Protection of Safety-Related
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2415/ML24158A041.pdf
Revision Date: 2024-08
Chapter: 
Section ID: RG-1.238
CFR Part: 
CFR Title: 

Content:
rate with the importance of the safety function to be performed. Furthermore, 10 CFR 50.55a(h) provides requirements for protection and safety systems and incorporates by reference IEEE Std. 279-1968, “Proposed IEEE Criteria for Nuclear Power Plant Protection Systems” (Ref. 4), IEEE Std. 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations” (Ref. 5), and IEEE Std. 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations” (including the correction sheet dated January 30, 1995) (Ref. 6). The applicability of each of these standards to a given nuclear power plant depends on the plant’s licensing date and other criteria. • Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50 establishes the minimum requirements for principal design criteria for water-cooled nuclear power plants,1 which include the following: o General Design Criterion (GDC) 1, “Quality standards and records,” requires, in part, that SSCs important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. o GDC 17, “Electric power systems,” requires, in part, that an onsite electric power system and an offsite electric power system be provided to permit functioning of SSCs important to safety. o GDC 18, “Inspection and testing of electric power systems,” requires, in part, that electric power systems important to safety be designed to permit appropriate periodic inspection and testing of important areas and features to assess the continuity of the systems and the condition of their components. o GDC 20, “Protection system functions,” requires, in part, that the protection system be designed to automatically initiate the operation of appropriate systems, including the reactivity control systems, to ensure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational