Document: NRC Regulatory Guide
Document ID: 30e6fa68-c7c1-4266-ba45-e06d1bbc07a0
Document Type: regulatory_guide
Title: Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1708/ML17083A134.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.97
CFR Part: 
CFR Title: 

Content:
(xix) requires applicants and licensees to provide instrumentation adequate for monitoring plant conditions following an accident that includes core damage. o 10 CFR 50.55a, “Codes and Standards,” describes consensus codes and standards that the NRC has incorporated into its regulations by reference. o 10 CFR Part 50, Appendix A, GDC 13, “Instrumentation and Control,” requires operating reactor licensees to provide instrumentation to monitor variables and systems over their anticipated ranges for accident conditions as appropriate to ensure adequate safety. o 10 CFR Part 50, Appendix A, GDC 19, “Control Room,” requires operating reactor licensees to provide a control room from which actions can be taken to maintain the nuclear power unit in a safe condition under accident conditions, including loss-of- coolant accidents. In addition, operating reactor licensees must provide equipment at appropriate locations outside the control room with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown. o 10 CFR Part 50, Appendix A, GDC 64, “Monitoring Radioactivity Releases,” requires operating reactor licensees to provide the means for monitoring the reactor containment atmosphere, spaces containing components to recirculate loss-of-coolant accident fluids, effluent discharge paths, and the plant environs for radioactivity that may be released as a result of postulated accidents. • 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. o 10 CFR 52.47(a)(23), requires a design certification application for light-water reactor (LWR) designs to present a description and analysis of design features for the prevention and mitigation of