Document: NRC Regulatory Guide
Document ID: 0df18aa6-42a8-4990-aa7e-3df6d0907f3f
Document Type: regulatory_guide
Title: Criteria for Safety Systems (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2511/ML25114A021.pdf
Revision Date: 2025-11
Chapter: 
Section ID: RG-1.153
CFR Part: 
CFR Title: 

Content:
ortance 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), IEEE Std 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations” (Ref. 6) (including the correction sheet dated January 30, 1995 (Ref. 7)) and IEEE Std 603- 2018, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” The applicability of each of these standards to a given nuclear power plant depends on the plant’s licensing date and other criteria. o 10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants,” contains, in part, requirements for the design, reliability, qualification, and testability of safety systems. o 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants” establishes quality assurance requirements for the design, manufacture, construction and operation of SSCs that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses. Related Guidance • RG 1.28, “Quality Assurance Program Criteria (Design and Construction),” (Ref. 8) provides guidance for establishing and implementing a quality assurance program. • RG 1.32, “Criteria for Power Systems for Nuclear Power Plants,” (Ref. 9) provides guidance on the design, operation, and testing of electric power systems in nuclear power plants. • RG 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems,” (Ref. 10)