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:
ty so that a fire that is not promptly extinguished by the fire suppression activities will not prevent the safe shutdown of the plant or result in release of radioactive materials to the environment. 3. Fire Protection Program Performance Goals 3.1 Safety-Related Structures, Systems, and Components The loss of function of systems used to mitigate the consequences of design basis accidents under post-fire conditions does not per se impact public safety. The need to limit fire damage to systems required to achieve and maintain safe shutdown conditions is greater than the need to limit fire damage to those systems required to mitigate the consequences of design basis accidents. 3.2 Post-Fire Safe Shutdown The performance objectives of the fire protection program relative to post-fire safe shutdown are to ensure that one success path of structures, systems, and components necessary for hot shutdown is free of fire damage, and to limit fire damage such that one success path of structures, systems, and components necessary to achieve and maintain cold shutdown can be repaired or made operable within a specified time period using onsite capabilities. For advanced reactor designs, safe shutdown must be achieved assuming all equipment in any one fire area will be rendered inoperable by fire and post-fire re-entry for repairs or operator actions is not possible. For passive light water reactor designs that rely on natural circulation and heat transfer to remove reactor decay heat, safe shutdown is defined in SECY 94-084 and Appendix B of this BTP. 3.3 Prevention of Radiological Release The fire protection program, including the fire hazards analysis, should demonstrate that the plant will maintain the ability to minimize the potential for radioactive releases to the environment in the event of a fire. Fires are expected to occur over the life of a nuclear power plant and thus should be treated as anticipated operational occurrences as defined in Appendix A to 10 CFR Part 50.