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:
ire Brigade Practice The licensee should hold practice sessions for each shift fire brigade on the proper method of fighting the various types of fires that could occur in a nuclear power plant. These sessions should provide brigade members with experience in actual fire extinguishment and the use of self-contained breathing apparatuses under the strenuous conditions encountered in firefighting. The licensee should provide these practice sessions at least once a year for each fire brigade member. 1.6.4.4 Fire Brigade Training Records The licensee should maintain individual records of training provided to each fire brigade member, including drill critiques, for at least 3 years to ensure that each member receives training in all parts of the training program. These training records should be available for NRC inspection. 1.7 Quality Assurance The overall plant QA plan should include the QA program for fire protection. The licensee should maintain a QA program that provides assurance that the fire protection systems are designed, fabricated, erected, tested, maintained, and operated so that they will function as intended. Fire protection systems are not “safety related” and, therefore, are not within the scope of Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50, unless the licensee has committed to including these systems under the plant’s Appendix B program. The NRC staff has generally used guidance for an acceptable QA program for fire protection systems, previously given in Section C.4 of BTP CMEB 9.5-1, “Guidelines for Fire Protection for Nuclear Power Plants,” Revision 2, issued July 1981 (Ref. 45), in the review and acceptance of approved FPPs for plants licensed after January 1, 1979. This RG incorporates that guidance, and the NRC staff will continue to use it in the review and acceptance of approved FPPs for new reactors. For plants licensed before January 1, 1979, BTP APCSB 9.5-1,