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:
lity to achieve and maintain safe shutdown in the event of a fire. In 10 CFR 50.48(c), the NRC requires licensees choosing to adopt NFPA 805 to identify license conditions to be revised or superseded. Licensees should request a new fire protection license condition that will define the revised bases for making changes to the approved NFPA 805 FPP without prior NRC approval. Regulatory Position 3.1 in Section C provides an example license condition. Appendices to NFPA 805 As discussed in the Statement of Considerations (titled “Approval of Incorporation by Reference” in the Federal Register notice for the final 10 CFR 50.48(c) rulemaking), the appendices to NFPA 805 are not considered part of the rule. Fire Probabilistic Risk Assessment Although a licensee may transition to an FPP based on NFPA 805 without a fire probabilistic risk assessment (PRA)1 model, licensees should develop a plant-specific fire PRA to fully realize the safety and cost benefits of making the transition to NFPA 805. This is because a fire PRA forms the basis for risk-informed changes to the FPP that can be made without prior NRC review and approval under a revised plant license condition, as described in Regulatory Position 3.1 in Section C. Consideration of International Standards The International Atomic Energy Agency (IAEA) works with member states and other partners to promote the safe, secure, and peaceful use of nuclear technologies. The IAEA develops Safety Standards and Safety Guides for protecting people and the environment from harmful effects of ionizing radiation. This system of safety fundamentals, safety requirements, safety guides, and other relevant reports reflects an international perspective on what constitutes a high level of safety. To inform its development of this 1 The NRC considers probabilistic safety analysis and PRA to be synonymous. This RG will use PRA. The term “fire PRA,” as used in this RG, encompasses all levels and types of PRAs, including fire PRAs