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:
ence, if appropriately justified and consistent with applicable NRC requirements and current regulatory practice. DG-1335, Page 8 C. STAFF REGULATORY GUIDANCE This RG endorses IEEE Std. 497-2016 as an acceptable method for providing instrumentation to monitor variables for accident conditions, subject to the following regulatory guidance positions: 1. The applicability of IEEE Std. 497-2016 for licensees and applicants already committed to an earlier revision of RG 1.97 should be clarified: A licensee or applicant committed to an earlier revision of RG 1.97 may voluntarily convert the entire accident monitoring program using the criteria in this revision. To do so, the licensee or applicant needs to analyze the accident monitoring program in its entirety. Having carefully considered the applicability and usefulness of the new standard, the NRC staff recognizes that licensees or applicants may be interested in converting to the latest revision of RG 1.97, updating the plant’s entire accident monitoring program from the current licensing basis to a less prescriptive one. This conversion would entail conducting a new analysis of every type of variable, and may result in physical modifications to the plant and changes to its procedures and technical specifications. 2. Licensees and applicants that have committed to an earlier revision of RG 1.97 may voluntarily add Type F variables, that is, those variables to be monitored while managing a severe accident: A licensee or applicant committed to an earlier revision of RG 1.97 may use this revision to add Type F variables to their plant’s accident monitoring program. The licensee or applicant should first perform a comprehensive analysis of severe accidents to determine the variables to be selected. This revision of RG 1.97 may be used to select only Type F variables and determine their design, performance, qualification, and display criteria. For these modifications, the licensee should perform an analysis addressing