Document: NUREG-0800
Document ID: 757f66f9-1dd5-4125-9970-089087134ad9
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0905/ML090510170.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1.1
CFR Part: 
CFR Title: 

Content:
-induced equipment failure. o. Use of polyvinyl chloride and other non-IEEE 1202 rated cable jacketing and insulation should be minimized. p. The Advanced Boiling Water Reactor (ABWR) and the Economic Simplified Boiling Water Reactor (ESBWR) design plants have no external reactor coolant pumps, eliminating a major fire hazard inside containment. In addition, the containment atmosphere during operation of the ABWR and ESBWR is inerted as with the existing BWR plants. 6.3 Additional Risk Consideration for New Reactor FPPs Turbine buildings remain potentially high-fire-risk areas in new reactor plants. Consideration should be given to the potential risk to adjacent safety related buildings and to ensuring control room or remote shutdown station habitability in the event of a major turbine fire. 7. Fire Protection for Non-Power Operation During shutdown operations, particularly during maintenance or refueling outages, fire conditions can change significantly as a result of work activities. Redundant systems important to safety 9.5.1.1-20 Revision 0 – February 2009 may not be available as described in plant technical specifications and plant procedures. Fire protection during shutdown or refueling conditions should minimize the potential for fire events to impact safety functions (e.g., reactivity control, reactor decay heat removal, SFP cooling) or result in the release of radioactive materials, under the unusual conditions that may be present during these operations. The guidance for fire prevention in Regulatory Position 2 of RG 1.189 is applicable to all modes of plant operation, including shutdown. License applications for new reactors should also address any special provisions to ensure that, in the event of a fire during a non-power mode of operation, the plant can be maintained in safe shutdown. 8. Alternative Designs and Non-Applicable Acceptance Criteria The new reactor designs that have been reviewed by the NRC have proposed FPP approaches for specific areas