Document: NUREG-0800
Document ID: 949ca18d-b0e4-4b54-9ca9-fdb657988111
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660170.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
idance applies equally to IEEE Std. 603-1991, Clauses 5.6 and 5.11. The I&C evaluation is limited to the review of components and electrical wiring inside racks, panels, and control boards for systems important to safety. The evaluation of the physical separation of electrical cables is addressed in the review of Chapter 8 of the SAR. (f) Regulatory Guide 1.97, Revisions 2 and 3, “Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident” (endorses ANSI/ANS 4.5-1980, “Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors"), and Regulatory Guide 1.97, Revision 4, Appendix 7.1-A-27 Revision 5 - March 2007 “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants” (endorses IEEE Std. 497-2002, “IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations”) Applicability - Information systems important to safety. Review Methods - Regulatory Guide 1.97 provides a basis for evaluating conformance to GDC 13. Existing plants currently reference Revision 2 or 3 of Regulatory Guide 1.97. Revision 4 of Regulatory Guide 1.97 is intended primarily for new plants. Revision 4 may be used by the current operating reactor licensees for modification or conversion in accordance with Regulatory Position 1 of Regulatory Guide 1.97. Revision 4 to Regulatory Guide 1.97 represents a significantly different approach to the topic from the previous revisions. Revision 4 is based on IEEE Std. 497-2002, which establishes flexible, performance-based criteria for the selection, performance, design, qualification, display, and quality assurance of accident monitoring variables. There is no prescriptive list of accident monitoring parameters or associated functional requirements on a parameter-by-parameter basis. The evaluation of instrumentation for monitoring environs conditions and radiation monitoring systems is addressed in the