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:
plant-specific analyses to provide greater realism in the fire PRA model. Additionally, progress in fire PRA realism was made through a now-concluded fire PRA FAQ program and will continue to be made through ongoing research. Although a licensee may transition to an FPP based on NFPA 805 without a fire PRA model that encompasses all the areas in its facility, the licensee must develop a plant-specific fire PRA of sufficient scope and technical adequacy to demonstrate that the risk-informed requirements in the rule are met for all areas for which the licensee is using the risk-informed approach described in NFPA 805, Sections 2.4.3 and 4.2.4.2. If a licensee develops a fire PRA only for areas for which it uses the risk-informed approach, the licensee should develop, review, and maintain this limited-scope PRA in accordance with all applicable guidelines. The acceptance guidelines of RG 1.174 may require the total CDF or LERF (or both) to evaluate changes for which the risk impact exceeds specific guidelines. If no areas rely on the risk-informed approach, licensees may propose an alternative approach for making the transition to, and changing, an FPP based on 10 CFR 50.48(c). RG 1.205, Revision 2, Page 27 D. IMPLEMENTATION The NRC staff may use this regulatory guide as a reference in its regulatory processes, such as licensing, inspection, or enforcement. However, the NRC staff does not intend to use the guidance in this regulatory guide to support NRC staff actions in a manner that would constitute backfitting as that term is defined in 10 CFR 50.109, “Backfitting,” and as described in NRC Management Directive 8.4, “Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests” (Ref. 34), nor does the NRC staff intend to use the guidance to affect the issue finality of an approval under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” The staff also does not intend to use the guidance to support