Document: NUREG-0800
Document ID: b10297dd-9822-4243-8665-c41d92699ea5
Document Type: srp
Title: RISK-INFORMED, PERFORMANCE-BASED FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0925/ML092590527.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1.2
CFR Part: 
CFR Title: 

Content:
UREG-0800 Section 9.5.1 license commitments are not covered in this SRP Section. In developing this SRP Section, the staff considered requirements of 10 CFR 50.48(c) and NFPA 805, 2001 Edition, to the extent it is incorporated into 10 CFR 50.48(c). The staff also considered the guidance provided by RG 1.205 which endorses with exceptions Nuclear Energy Institute (NEI) NEI 04-02, “Guidance for Implementing a Risk-Informed Performance-Based Fire Protection Program under 10 CFR 50.48(c),” Revision 2. At the time of drafting this SRP Section, some of the documents referenced herein are subject to revision, like RG 1.205 and NEI 04-02. For example, the referenced documents may be reorganized, which would affect the specific section references in this SRP. The staff should use the most current revision of RG 1.205 for accurate references. In addition, the staff incorporated interim guidance which was developed using experience from NFPA 805 pilot plant implementation. The staff has documented this interim staff guidance (ISG) via the NFPA 805 Frequently Asked Questions (FAQ) Process. [Regulatory Issue Summary (RIS) 2007-19, “Process for Communicating Clarifications of Staff Positions provided in RG 1.205 Concerning Issues Identified during the Pilot Application of National Fire Protection Association Standard 805”] Review Areas An FPP for a nuclear power plant (NPP) licensed to operate generally consists of the following elements (Ref. 35): • Delineation of organization, staffing, and responsibilities • Performance of a fire hazards analysis sufficient to ensure safe shutdown capability and minimize radioactive material releases in the event of a fire • Limitation of damage to structures, systems and components (SSCs) important to safety so that the capability to safely shut down the reactor is ensured • Evaluation of fire test reports and fire data to ensure they are appropriate and adequate for ensuring compliance with NRC regulatory requirements •