Document: NRC Regulatory Guide
Document ID: edb75cf4-27e1-4166-989c-25781bd48b98
Document Type: regulatory_guide
Title: Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2007/ML20078K920.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.191
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CFR Title: 

Content:
ction, which could be adopted by license amendment. Under the standard condition, a licensee may make changes to the approved fire protection program, without prior NRC approval, if the changes do not adversely affect the plant’s ability to achieve and maintain safe shutdown in the event of a fire. Most licenses have been amended to include the standard condition on fire protection. In 2004, the NRC amended its fire protection rule in 10 CFR 50.48 to incorporates by reference the 2001 Edition of NFPA 805 with exceptions, modifications, and supplementation. 10 CFR 50.48(c) allows nuclear power plant licensees to submit a license amendment request to adopt a fire protection program that meets the requirements of NFPA 805 as an alternative to meeting the requirements of 10 CFR 50.48(b) or any plant-specific fire protection license conditions (Ref. 15). Licensees that have an approved NFPA 805 program under 10 CFR 50.48(c) can use Chapter 5 of NFPA 805 to comply with 10 CFR 50.48(f). A licensee that does not have an approved NFPA 805 program under 10 CFR 50.48(c) can request approval to implement NFPA 805 or other performance- based standards to meet the requirements of 10 CFR 50.48(f). The glossary includes terms used in this guide. These definitions have been obtained from existing regulatory documents, industry fire protection standards, or defined by the NRC staff. Appendix A to this guide provides guidance on the level of fire protection that is acceptable to the NRC staff for spent fuel areas, radioactive waste storage areas, and other plant areas where a fire could potentially affect structures, systems, and components (SSCs) required to maintain spent fuel integrity. DG-1370, Page 5 Criterion 3, 10 CFR 50.48, and Appendix R to 10 CFR Part 50 provide the fire protection requirements for operating reactors. Before the decommissioning rule was published on July 29, 1996 (Ref. 16), the NRC’s fire protection regulations did not address nuclear power plants that