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:
babilistic 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 NRC. Applicability This RG applies to light-water reactor (LWR) licensees subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 2), and 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 3). This RG provides guidance for proposing a risk-informed approach to implement an RI-IST program in accordance with 10 CFR 50.55a(z)(1) in lieu of the IST requirements in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) (Ref. 4) as incorporated by reference in 10 CFR 50.55a. If a licensee has been authorized to implement 10 CFR 50.69, the risk-informed approach described in this RG is not applicable because the IST requirements in 10 CFR 50.55a for certain pumps, valves, and snubbers are replaced by the alternative treatment requirements in 10 CFR 50.69. Applicable Regulations • 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” provides RG 1.175, Page 2 regulations for licensing production and utilization facilities. o 10 CFR 50.55a, “Codes and Standards,” requires, in part, that systems and components must meet the IST requirements of the OM Code, as specified in 10 CFR 50.55a(b) and (f). This RG describes the information to be submitted by a licensee as part of an alternative request in accordance with 10 CFR 50.55a(z), “Alternatives to codes and standards requirements,” subparagraph (1), “Acceptable level of quality and safety,” to demonstrate that the proposed RI-IST program would provide an acceptable level of quality and safety. o 10 CFR Part 50, Appendix B, Criterion XVI, “Corrective Action,” which states, “Measures shall