Document: NUREG-0800
Document ID: 757f66f9-1dd5-4125-9970-089087134ad9
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0905/ML090510170.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1.1
CFR Part: 
CFR Title: 

Content:
able to another plant and, similarly, exceptions approved for one plant may not apply to another plant. Each plant should be evaluated based on the site-specific design and licensing basis. 9.5.1.1-24 Revision 0 – February 2009 APPENDIX C Supplemental Fire Protection Review Criteria for Fire Probabilistic Risk Assessments The purpose of this appendix is to provide guidance for the review of the fire protection information to be provided in an application for PRA. An existing plant that has not adopted a risk-informed, performance-based FPP in accordance with 10 CFR 50.48(c) may apply risk- informed methodologies, including fire PRA, to the evaluation of a FPP change. However, the proposed methodologies, including the acceptance criteria, should be reviewed and approved by the NRC prior to the implementation of the plant change. 10 CFR Part 52.47(a)(v) requires that new reactor applications submitted under Part 52 include a design specific probabilistic risk assessment. A detailed fire PRA is not necessarily required for a new reactor FPP. However, if a COL applicant references a DC and if that certified design developed a fire PRA, then the COL applicant, per proposed 10 CFR 52.80(a), is to use that PRA and update it to reflect site and plant-specific information that may not have been available at the design stage. In addition, a licensee that has a risk-informed, performance-based FPP (similar to an NFPA 805 program) or that plans to evaluate plant changes using a risk-informed approach should have a detailed fire PRA. The term Afire PRA@ encompasses all levels and types of PRAs, ranging from a simplified bounding analysis to a detailed analysis in accordance with NUREG/CR-6850 and the draft American Nuclear Society Fire PRA Standard. NUREG/CR-6850 should provide the basis for the review of the proposed methodologies. Refer to SRP Chapter 19, AProbabilistic Risk Assessment,@ for additional guidance on the review of nuclear power plant PRAs. A fire PRA should be