Document: NRC Regulatory Guide
Document ID: 47b09be1-4bf8-45f9-a099-7fed871c09bd
Document Type: regulatory_guide
Title: Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2114/ML21140A055.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.175
CFR Part: 
CFR Title: 

Content:
U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE RG 1.175, Revision 1 Issue Date: June 2021 Technical Lead: Michael Farnan Gary Wang Written suggestions regarding this guide or development of new guides may be submitted through the NRC’s public Web site in the NRC Library at https://nrcweb.nrc.gov/reading-rm/doc-collections/reg-guides/, under Document Collections, in Regulatory Guides, at https://nrcweb.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html. Electronic copies of this RG, previous versions of RGs, and other recently issued guides are also available through the NRC’s public Web site in the NRC Library at https://nrcweb.nrc.gov/reading-rm/doc-collections/reg-guides/, under Document Collections, in Regulatory Guides. This RG is also available through the NRC’s Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS under Accession Number (No.) ML21140A055. The associated draft guide DG-1286 may be found in ADAMS under Accession No. ML19240B371. The Regulatory Analysis for DG-1286 may be found in ADAMS under Accession No. ML19240B374. No public comments were received on DG-1286; therefore, the staff has not prepared responses to public comments. PLANT-SPECIFIC, RISK-INFORMED DECISIONMAKING: INSERVICE TESTING A. INTRODUCTION Purpose This regulatory guide (RG) describes an approach that is acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for developing risk-informed inservice testing (RI-IST) programs. It supplements the guidance provided in RG 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis” (Ref. 1). This guide describes acceptable methods for using information from a probabilistic risk assessment (PRA) with deterministic engineering information in the development of a RI-IST program to be submitted by a nuclear power plant licensee for review and authorization by the