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
CFR Part: 
CFR Title: 

Content:
endent Storage of Spent Nuclear Fuel, High Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste,” Part 72, Chapter 1, Title 10, “Energy.” DG-1359, Page 121 119. Electric Power Research Institute (EPRI), EPRI NP-5283-SR-A, “Guidelines for Permanent BWR Hydrogen Water Chemistry Installations,” Palo Alto, CA, 1987.10 120. NRC, RG 1.206, “Applications for Nuclear Power Plants,” Washington, DC. 121. NFPA, NFPA 804, “Standard for Fire Protection for Advanced Light Water Reactor Electric Generating Plants,” Quincy, MA. 122. NRC, SECY-05-0197, “Review of Operational Programs in a Combined License Application and Generic Emergency Planning Inspections, Tests, Analyses, and Acceptance Criteria,” Washington, DC, October 28, 2005. 123. NRC, Management Directive 8.4, “Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests,” Washington, DC, September 20, 2019. (ADAMS Accession No. ML18093B087) 10 Copies of Electric Power Research Institute (EPRI) standards and reports may be purchased from EPRI, 3420 Hillview Ave., Palo Alto, CA 94304; telephone (800) 313-3774; fax (925) 609-1310. DG-1359, Appendix A, Page A-1 APPENDIX A FIRE PROBABILISTIC RISK ASSESSMENTS In addition to existing plants that have not adopted a risk-informed, performance-based fire protection program (FPP) in accordance with Title 10 of the Code of Federal Regulations (10 CFR) section 50.48(c), licensees that have not adopted 10 CFR 50.48(c) and licensees preparing new reactor FPPs may apply risk-informed methodologies, including fire probabilistic risk assessment (PRA), to the evaluation of an FPP change. However, the U.S. Nuclear Regulatory Commission (NRC) should review and approve the proposed methodologies, including the acceptance criteria, before implementation of the plant change. According to 10 CFR 52.47(a)(v), new reactor applications submitted under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power