Document: NUREG-0800
Document ID: 69433f0d-1a24-4cf6-b8b9-31109f9f51c5
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190014.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1
CFR Part: 
CFR Title: 

Content:
ion 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 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, spent fuel pool cooling) or result in the release of radioactive materials, under the unusual conditions that may be present during these operations. 9.5.1-20 Revision 5 - March 2007 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 of the plant that are not in accordance with the acceptance criteria in RG 1.189. In addition, some of the acceptance criteria in RG 1.189 may not be applicable to some reactor designs. The following are examples of alternative designs that have been accepted by the NRC and plant design features for which the acceptance criteria do not apply. These are examples and may not include all cases. The reviewer should determine the applicability of the acceptance criteria and the acceptability of any deviations for plant-specific conditions. 8.1 Alternative Designs a. At least one new reactor design has been certified by the NRC without meeting the guidance in RG 1.189, Regulatory Position 6.1.2.2, to provide detection in control room cabinets and consoles. The acceptance of this approach was based on the