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:
d for NFPA codes referenced in NRC regulations such as NFPA 805 in 10 CFR 50.48(c). The NRC guidelines reference certain NFPA codes as providing guidance acceptable to the staff; therefore, such codes may be accorded the same status as RGs. More recent editions of the NFPA codes require submittal of technical documentation to the “authority having jurisdiction” (AHJ) to demonstrate equivalency of an alternative system, method, or device for AHJ approval. Whether or not the code of record includes this requirement, the NRC does not require review and approval of equivalency evaluations. However, the licensee should document these evaluations and make them available for NRC inspection. Since 2007, some NFPA codes require plans and calculations to be submitted to the AHJ before installation. The NRC monitors plant modifications in a variety of ways, such as periodic inspections, 10 CFR 50.59 evaluations, and updating and periodic submittal of the FSAR. Therefore, licensees need not submit informational transmittals, such as fire protection system plans and calculations, to the NRC, except as otherwise required. Since some NFPA codes require this transmittal, licensees should document these deviations from NFPA codes. When the applicant or licensee states that its design “meets the NFPA code(s)” or “meets the intent of the NFPA code(s)” and does not identify any deviations from such codes, the NRC understands that the design conforms to the codes and is subject to inspection against the NFPA code of record. The AHJ (as described in NFPA documents) refers to the Director of the Office of Nuclear Reactor Regulation, or designee, consistent with the authority specified in 10 CFR 1.43, “Office of Nuclear Reactor Regulation” (Ref. 50). 1.8.7 Fire Modeling When the evaluation of an FPP change is based on fire modeling, licensees should document the fact that its fire models and methods meet the NRC requirements. The licensee should also document that the