Document: NRC Regulatory Guide
Document ID: 6f84e3bf-9ff3-49fb-a16a-0de3b89e6bc6
Document Type: regulatory_guide
Title: An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2103/ML21036A105.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.178
CFR Part: 
CFR Title: 

Content:
in RG 1.174, which provides specific considerations with respect to determining the acceptability of the PRA used in risk-informed decisionmaking, and (2) add the reference to ASME Code Case N-716-1, “Alternative Classification and Examination Requirements, Section XI, Division 1,” dated January 27, 2013 (Ref. 8), which describes an RI-ISI process as approved in RG 1.147. Background The NRC and the nuclear industry recognized that PRAs have evolved to be useful in supplementing deterministic engineering approaches in reactor regulation. On August 16, 1995, the NRC issued its policy statement on the increased use of PRA in nuclear regulatory activities, titled “Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement” (Ref. 9). After the publication of the policy statement, the Commission directed the NRC staff to develop a regulatory framework that incorporated risk insights. The NRC articulated this framework in SECY-95-280, “Framework for Applying Probabilistic Risk Analysis in Reactor Regulation,” dated November 27, 1995 (Ref. 10). This guide implements, in part, the Commission’s policy statement and the NRC staff’s framework for incorporating risk insights into the regulation of nuclear power plants, as further discussed below. In support of the use of risk-informed decisionmaking, the NRC developed RG 1.174, which provides guidance on an acceptable approach for developing risk-informed applications for a licensing-basis change, considers engineering issues, and applies risk insights. As companion guidance to RG 1.174, SRP Section 19.1, “Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,” describes the NRC staff’s review plan to evaluate the technical acceptability of PRA results for risk-informed license amendment requests. This guide supplements the guidance provided in RG 1.174. Specifically, this guide addresses the guidance for developing the