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:
ection. The staff will review the LAR to verify that the requirements for existing cables are met. If the staff approves use of these alternatives, this approval should be explicitly documented in the staff’s safety evaluation report (SER). 9.5.1.2-11 Rev. 0 – December 2009 Note that the flame spread testing requirements in Institute of Electrical and Electronic Engineers (IEEE) 383, “IEEE Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations,” are now provided in IEEE 1202, “IEEE Standard for Flame-Propagation Testing of Wire and Cable,” and have been removed from the current version of IEEE 383. Most existing plants reference earlier versions of IEEE 383 and have approved FPPs based on this standard. Plants that reference IEEE 383 are not required to meet IEEE 1202 when transitioning to a RI/PB FPP. Plants that have a licensing basis that does not reference IEEE 383 should demonstrate that the installed cables meet cable fire spread acceptance criteria at least as stringent as those in IEEE 383-1974. This equivalency should be documented in the SER. III.3 NUCLEAR SAFETY PERFORMANCE CRITERIA Chapter 2 of NFPA 805 provides the methodology to be used in implementing a PB FPP. Chapter 4 of NFPA 805 establishes the methodology to determine the fire protection systems and features required to achieve the performance criteria outlined in NFPA 805, Section 1.5. NEI 04-02, Section 4.3.2 sets out a systematic process for evaluating the existing post-fire safe shutdown analysis against the methodology requirements provided in Chapter 2 of NFPA 805 and the methods for achieving the nuclear safety performance criteria in Chapter 4 of NFPA 805. III.3.1 Nuclear Safety Compliance Assessment Methodology Transition 10 CFR 50.48(c)(3)(ii) states that Chapter 2 analyses shall be completed and the fire protection plan modified before changing the FPP and the plant as permitted by NFPA 805. The staff will