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:
ng stations. It should be used in conjunction with the he most recent version of IEEE Std. 603, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations” (Ref. 12), that is incorporated by reference in 10 CFR 50.55a. to ensure completeness of the post-accident monitoring system design when a computer is to be used as a component of a post-accident monitoring system to enable the ability of plant operators to take preplanned manual safety actions for which there are no provisions for automatic safety actions. DG-1335, Page 4 Paperwork Reduction Act This RG provides guidance for implementing the mandatory information collections in 10 CFR Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et. seq.). These information collections were approved by the Office of Management and Budget (OMB), under control numbers 3150-0011 and 3150-0151. Send comments regarding this information collection to the Information Services Branch, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs NEOB-10202, (3150-0011, 3150-0151), Office of Management and Budget, Washington, DC 20503. Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number. DG-1335, Page 5 B. DISCUSSION Reason for Revision The staff is issuing Revision 5 of RG 1.97 to endorse IEEE Std. 497-2016 “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants,” with exceptions and clarifications. Revision 5 also makes further clarifying revisions by expressly expanding the applicability of RG 1.97 to holders of, or applicants for, power reactor design certifications or combined licenses under 10 CFR Part 52, and by adding references to the