Document: NUREG-0800
Document ID: 69433f0d-1a24-4cf6-b8b9-31109f9f51c5
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190014.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1
CFR Part: 
CFR Title: 

Content:
ned to be acceptable to manage aging effects of SSCs in the scope of the license renewal as required by 10 CFR 54. For example, the intended function of fire suppression piping or the fire pump casing is to provide a pressure boundary. Programs to manage the aging effects of the pressure boundary can be existing plant programs, modified (or enhanced) programs, or new programs specifically created to address aging concerns. The development of modified or newly created programs is dependent upon (1) the aging effect that needs to be managed, and (2) the ability of the current program to manage the aging effect throughout the period of extended operation. Plants that have installed Halon 1301 extinguishing systems that will be credited during the extended life of the plant should have either a plan for continued access to an adequate supply of replacement Halon or a plan to replace the system. Due to the uniqueness of each existing nuclear power plant and to the variations in plant licensing bases, the staff should consider that requirements imposed on one plant are not necessarily applicable 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. 9.5.1-24 Revision 5 - March 2007 APPENDIX C Supplemental Fire Protection Review Criteria for Fire Probabilistic Risk Assessments (PRA) 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