Document: NUREG-0800
Document ID: 71224475-ca63-4c09-acc1-c682d58112dd
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550082.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
lear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to DISTRIBUTION@nrc.gov. Electronic copies of this section are available through the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/, or in the NRC's Agencywide Documents Access and Management System (ADAMS), at http://www.nrc.gov/reading-rm/adams.html, under Accession # ML070550082. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 7-10 GUIDANCE ON APPLICATION OF REGULATORY GUIDE 1.97 REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None A. BACKGROUND This branch technical position (BTP) provides additional guidelines for reviewing an applicant/licensee's accident monitoring instrumentation. These guidelines are based on reviews of applicant/licensee design submittals that contained approved interpretations and alternatives for the guidance identified in Regulatory Guide 1.97. Revisions 2, 3, and 4 of Regulatory Guide 1.97 are currently in effect. Plants licensed prior to June 2006 committed to follow either Revision 2 or 3, both titled "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." Both revisions 2 and 3 of Regulatory Guide 1.97 prescribe a detailed list of variables to monitor and specify a comprehensive list of design and qualification criteria to be met by the instrumentation monitoring each variable. Revision 4, "Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants," endorses, with exceptions and clarifications, IEEE Std. 497-2002, "IEEE Standard Criteria for Accident Monitoring BTP 7-10-2 Revision 5 - March 2007 Instrumentation for Nuclear Power Generating Stations." IEEE Std. 497-2002 establishes flexible, performance-based criteria for the