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:
June 26, 1990. (ML003707885) 28. IN 2002-27, “Recent Fires at Commercial Nuclear Power Plants in the United States.” 29. NEI 95-10, Revision 6, “Industry Guide for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule.” 30. NFPA 804, “Standard for Fire Protection for Advanced Light Water Reactor Electric Generating Plants.” 9.5.1-14 Revision 5 - March 2007 31. NFPA 805, “Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants.” PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. 9.5.1-15 Revision 5 - March 2007 APPENDIX A Supplemental Fire Protection Review Criteria for New Reactors Unless specifically noted otherwise, the review guidance in this SRP section is applicable to the FPP for new reactor plants. This appendix provides additional guidance applicable to new reactor FPPs. Many of the current fire protection requirements and guidelines for operating reactors were issued after the construction permits and/or operating licenses were approved by the Commission. The backfit of these requirements and guidelines to existing plant designs created the need for considerable flexibility in the application of the regulations on a plant-by- plant basis. For new reactor designs, fire protection requirements, including the protection of safe-shutdown capability and the prevention of radiological release, can be readily integrated in the planning and design phase for the plant. For applications submitted in accordance with 10 CFR