Document: NUREG-0800
Document ID: 43123a17-321c-4751-b3ba-9ba5e9b0b364
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A726.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
uidance identified in RG 1.97. Revisions 2, 3, and 4 of RG 1.97 are currently in effect. Plants licensed before 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 RG 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, Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 497, “IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations.” IEEE Std 497 establishes flexible, performance-based criteria for the selection, performance, design, qualification, display, and quality assurance of accident monitoring variables. 1. Regulatory Basis Title 10 of the Code of Federal Regulations (10 CFR) 50.34(f)(2)(xvii) requires in part that instrumentation be provided to measure, record, and read out in the control room: containment pressure, containment water level, containment hydrogen concentration, containment radiation intensity (high-level), and noble gas effluents. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 13, “Instrumentation and Control,” requires in part that instrumentation be provided to monitor variables and systems over their anticipated ranges for accident conditions, as appropriate, to ensure adequate safety. GDC 19, “Control Room,” requires in part that a control room be provided from which actions can be taken to maintain the nuclear power unit in a safe condition under accident conditions, including