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
CFR Part: 
CFR Title: 

Content:
monstrated to the NRC that it has met the applicable regulatory criteria for site release. The licensee must demonstrate that the facility has been radiologically decontaminated in accordance with the NRC-approved license termination plan. Before terminating the operating license, the NRC will determine if the plant has been dismantled according to the approved termination plan and will verify the licensee’s final radiation surveys by reviewing the surveys, conducting separate surveys, or both. 1.5 Changes to the Decommissioning Fire Protection Program Subject to the requirements of 10 CFR 50.48(f)(3), a licensee may make changes to the fire protection program without prior NRC approval provided the changes do not reduce the effectiveness of fire protection for facilities, systems, and equipment that could result in a radiological hazard, considering the plant conditions and activities during decommissioning. An engineering evaluation can be performed and conclude that the change has not affected the alternative functionally and its equivalent to the fire protection of SSCs described in Regulatory Positions C.2 through C.5 of this guide. For NFPA 805 plants, a licensee can change the fire protection program without prior NRC approval if an engineering evaluation demonstrates that the alternative is either functionally equivalent to the NFPA 805 Chapter 5 requirements, which are discussed in Regulatory Position C.6 of this guide, or provide an equivalent level of effectiveness to the current program for the decommissioning plant conditions and activities. NFPA 805 provides guidance on a performance-based approach that allows the use of risk insights or fire modeling to develop fire scenarios to evaluate and determine the fire protection for SSCs needed to meet the nuclear safety objectives. A licensee may use a low power/shutdown fire probabilistic risk assessment (PRA) model that has been reviewed and approved by the NRC to perform quantitative risk assessments to