Document: NRC Regulatory Guide
Document ID: 8e45dce1-e1e7-4415-b1dd-7e2a610e545b
Document Type: regulatory_guide
Title: Fire Protection for Nuclear Power Plants (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2023/ML20231A835.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.189
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CFR Title: 

Content:
“Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976,” dated February 24, 1977 (Ref. 7), as reflected in NRC-issued safety evaluation reports (SERs). • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. The regulations in 10 CFR 52.47, 52.79, 52.137 and 52.157 for applications for standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities, respectively, state that the applicable 10 CFR Part 50 regulations cited above are also required for applicants for and holders of these 10 CFR Part 52 approvals. The staff notes that there are no similar requirements related to fire protection programs for applicants for and holders of early site permits. Related Guidance • Generic Letter (GL) 77-02, “Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and Quality Assurance,” dated August 29, 1977 (Ref. 8), provides criteria used by the staff to review specific elements of a licensee’s FPP, including organization, training, combustible and ignition source controls, firefighting procedures, and quality assurance (QA). • GL 81-12, “Fire Protection Rule (45 FR 76602; November 19, 1980),” dated February 20, 1981, and its associated clarification letter, dated March 22, 1982 (Ref. 9), provides information necessary to review licensee compliance with the alternative or dedicated shutdown requirements DG-1359, Page 4 of Section III.G.3 of Appendix R. Staff guidance in these letters defines safe-shutdown objectives, reactor performance goals, necessary safe-shutdown systems and components, and associated circuit identification and analysis methods. • GL 83-33, “NRC Positions on Certain Requirements of Appendix R to 10 CFR 50,” dated October 19, 1983 (Ref. 10), clarifies certain