Document: NRC Regulatory Guide
Document ID: 666e1303-0170-4974-a7d6-af27eb586524
Document Type: regulatory_guide
Title: Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2104/ML21048A448.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.205
CFR Part: 
CFR Title: 

Content:
ition (Ref. 2), which is incorporated by reference in 10 CFR 50.48(c). Applicability This RG applies to reactor licensees subject to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” that voluntarily adopt a new fire protection licensing basis that complies with the requirements in 10 CFR 50.48(a) and 10 CFR 50.48(c). The RG could also apply to holders of combined licenses under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” However, because large sections of NFPA 805 would not be applicable to a 10 CFR Part 52 licensee, no combined license holder is expected to adopt 10 CFR 50.48(c) as its licensing basis. Therefore, the NRC is not expanding the RG’s applicability to combined license holders at this time. Applicable Regulations • 10 CFR Part 50 provides regulations for licensing production and utilization facilities, including the fire protection regulations listed below. o 10 CFR 50.48(a) requires applicants and licensees to have a fire protection plan that satisfies General Design Criterion (GDC) 3, “Fire protection,” in Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50. RG 1.205, Revision 2, Page 2 o 10 CFR 50.48(c) establishes the requirements for using NFPA 805 as an alternative to the requirements associated with 10 CFR 50.48(b) and Appendix R, “Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979,” or the fire protection license conditions for plants licensed after January 1, 1979. This regulation incorporates by reference NFPA 805, 2001 Edition, with certain exceptions. • 10 CFR Part 50, Appendix A, GDC 3, requires operating reactor licensees to design structures, systems, and components important to safety to minimize the probability and effect of fires and explosions. Related Guidance • RG 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific