Document: NUREG-0800
Document ID: 05a851a6-07ff-41b4-8528-a032ba433e04
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0327/ML032740044.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1
CFR Part: 
CFR Title: 

Content:
evision 4 - October 2003 4 review. The appendices to this BTP provide additional review guidance for specific, unique, or expanded fire protection program criteria. Section D, Glossary, contains terms and definitions used in this BTP. This BTP has been developed to provide comprehensive review guidance for nuclear power plant fire protection programs. This guidance identifies the scope and depth of fire protection that the Commission considers acceptable for nuclear power plants. This guidance may be used for review of existing fire protection programs and program elements, proposed changes to existing programs that are subject to NRC review, new applications, fire vulnerability analyses [e.g., fire probabilistic risk assessments (PRA)], and programs for plant shutdown and decommissioning. Risk-informed and performance-based alternatives to the guidance presented in this regulatory guide may be acceptable and are evaluated on a case-by-case basis. B. BACKGROUND 1. Fire Protection Regulatory History During the initial implementation of the U.S. nuclear reactor program, regulatory acceptance of fire protection programs at nuclear power plants was based on the broad performance objectives of General Design Criterion 3 (GDC 3) in Appendix A to 10 CFR Part 50. Appendix A establishes the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety. GDC 3 addresses fire protection requirements and specifies, in part, that (1) structures, systems, and components important to safety must be designed and located to minimize the probability and effects of fires and explosions, (2) noncombustible and heat-resistant materials be used wherever practical, and (3) fire detection and suppression systems be provided to minimize the adverse effects of fires on structures, systems, and components important to safety. However, during this early stage of nuclear power regulation, given the lack of detailed