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:
at was more flexible. Instead of prescribing the instrument variables to be monitored (as was the case in Revision 3 of RG 1.97), the industry developed performance-based criteria for use in selecting variables. These efforts resulted in the development of IEEE Std. 497-2002, which established flexible, performance-based criteria for the selection, performance, design, qualification, display, and quality assurance of accident monitoring variables, which are the operators’ primary sources of accident monitoring information. This standard was endorsed by Revision 4 of RG 1.97, subject to eight regulatory positions. IEEE Std. 497-2010 (Ref. 15) was developed to incorporate some of those regulatory positions and revised some definitions and terminology. Based on insights from the Fukushima Dai-ichi accident in March 2011, the nuclear industry in the United States has recognized the need for instrumentation to monitor plant conditions after fuel damage has occurred. In addition, the NRC has determined that all power reactor licensees must have a reliable means of remotely monitoring wide-range spent fuel pool levels. As a result, the NRC issued an order (NRC Order EA-12-051) to all licensees requiring spent fuel pool level instrumentation. Accordingly, IEE broadened the scope of the standard to include severe accidents. IEEE Std. 497-2016 reflects a more technology-neutral approach and an effort to bring the standard in line with related international standards. DG-1335, Page 6 In addition, IEEE Std. 497-2016 adds a new kind of variable, Type F, which provides primary information to indicate fuel damage and the effects of fuel damage. The regulatory requirement for Type F variables derives from specific appendices of 10 CFR Part 52. At least one of the design certification rules incorporates, by reference, a design certification document that requires combined license applicants to implement SAMGs. Because the SAMGs cannot be implemented without instrumentation to