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:
bability of occurrence and the consequences of fire. To meet these objectives, the fire protection programs are designed to provide reasonable assurance, through defense-in-depth, that a fire will not prevent the performance of necessary safe shutdown functions and that radioactive releases to the environment in the event of a fire will be minimized. The NRC’s regulatory framework for nuclear plant fire protection programs is a number of regulations and supporting guidelines, including, but not limited to, 10 CFR Part 50, §50.48, 10 CFR Part 50, Appendix A, General Design Criterion 3 (GDC 3), 10 CFR Part 50, Appendix R, various regulatory guides, generic communications (e.g., Generic Letters, Bulletins, and Information Notices), NUREG reports, and industry standards. This BTP and the associated Standard Review Plan (SRP) Section 9.5.1, provide guidelines for staff review of applicant and licensee fire protection programs and related submittals. Since all the fire protection regulations promulgated by the NRC are not applicable to all plants, the review guidelines contained within this BTP are characterized as recommended practices and not as strict regulations or requirements. Reviews of fire protection programs for operating reactors, including those for license renewal, should be conducted in the context of the current licensing basis for the plant. Reviews for new plant applications, including standard design certifications should be reviewed to the guidelines in this BTP. For those reactors that are permanently shutdown and are subject to the requirements of 10 CFR Part 50, §50.82, “License Termination,” the plants are assumed to be operating to an approved fire protection program at the time operations are ceased. The fire protection objectives for these plants are modified from protection of structures, systems and components important to safety and necessary for safe shutdown, to minimizing the potential for fire induced release of radioactive