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:
Operating Prior to January 1, 1979," to 10 CFR Part 50, which specified detailed regulatory requirements for resolving the disputed issues. As originally proposed (Federal Register, Vol. 45, No. 1&5, May 22, 1980), Appendix R would have applied to all plants licensed prior to January 1, 1979, including those for which the staff had previously accepted the fire protection features as meeting the provisions of Appendix A to APCSB 9.5-1. After analyzing comments on the proposed rule, the Commission determined that only three of the fifteen items in Appendix R were of such safety significance that they should apply to all plants (licensed prior to January 1, 1979), including those for which alternative fire protection actions had been approved previously by the staff. These items are fire protection of safe shutdown capability (including alternative, dedicated, or backup shutdown systems), emergency lighting, and the reactor coolant pump oil system. Accordingly, the final rule required all reactors licensed to operate before January 1, 1979, to comply with these three items even if the NRC had previously approved alternative fire protection features in these areas (Federal Register, Vol. 45, Nov. 19, 1980)1. The remaining provisions of Appendix R did not apply provided that the fire protection features proposed or implemented by the licensee for those provisions had been accepted by the NRC staff in a safety evaluation. In addition, the rule provided for an exemption process that could be used by a licensee provided that a required fire protection feature to be exempted would not enhance fire protection safety in the facility or that such modifications may be detrimental to overall safety (10 CFR Part 50.48(c)(6)). Under this process, if the Director, Office of Nuclear Reactor Regulation, determined that a licensee has made a prima facie showing of a sound technical basis for such an assertion, then the Revision 4 - October 2003 7 implementation dates of the rule were