Document: NRC Regulatory Guide
Document ID: 8e45dce1-e1e7-4415-b1dd-7e2a610e545b
Document Type: regulatory_guide
Title: Fire Protection for Nuclear Power Plants (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2023/ML20231A835.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.189
CFR Part: 
CFR Title: 

Content:
h the use of suitable procedures. o 10 CFR Part 50, Appendix A, GDC 23, “Protection system failure modes,” requires that the protection system be designed to fail into a safe state or into a state demonstrated to be acceptable on some other defined basis, if the plant experiences conditions such as disconnection of the system, loss of energy (e.g., electric power, instrument air), or postulated adverse environments (e.g., extreme heat or cold, fire, pressure, steam, water, radiation). o 10 CFR Part 50, Appendix R, applies to licensed nuclear power electric generating stations that were operating before January 1, 1979, except as noted in 10 CFR 50.48(b). With respect to certain generic issues for such facilities, Appendix R identifies fire protection features required to satisfy GDC 3 of Appendix A. Two categories of Appendix R provisions apply to the fire protection features of these facilities: (1) The first category consists of those provisions that licensees were required to comply with in their entirety, regardless of whether the NRC had previously approved alternatives to the specific requirements. The requirements appear in Section III.G, “Fire protection of safe shutdown capability;” Section III.J, “Emergency lighting;” and Section III.O, “Oil collection system for reactor coolant pump.” Those plants subject to the requirements of Section III.G.3 must also meet the requirements of Section III.L, “Alternative and dedicated shutdown capability.” (2) The second category consists of requirements concerning the open items of previous NRC fire protection reviews. Open items are defined as fire protection features that the NRC staff had not previously approved as satisfying the provisions in Appendix A to Branch Technical Position (BTP) APCSB 9.5-1, “Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976,” dated February 24, 1977 (Ref. 7), as reflected in NRC-issued safety evaluation reports (SERs). • 10 CFR