Document: NRC Regulatory Guide
Document ID: 3b4c5897-7060-42e3-83a9-cf0790b7dc60
Document Type: regulatory_guide
Title: Acceptability of ASME Code, Section XI, Division 2, Requirements for RIM Programs for NPPs, for Non-LWRs
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2112/ML21120A185.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.246
CFR Part: 
CFR Title: 

Content:
lity of the heat-affected zone. Reliability Target A performance goal established for the probability that an SSC will complete its specified function to achieve plant-level and reliability goals. RIM Program A program that defines, evaluates, and implements strategies to ensure that reliability targets for SSCs are defined, achieved, and maintained throughout the plant lifetime. The RIM program is outlined in Article RIM-2 of ASME Code, Section XI, Division 2. A RIM program would be similar to a conventional ISI program but may be extensive, including activities such as ISI; testing; MANDE; and maintenance, repair, and replacement practices. RIM Strategy Methods of ensuring a component meets its reliability target. The methods may include, but are not limited to, design strategies; material selection; fabrication procedures; operating practices; PSI; ISI; testing; MANDE; and maintenance, repair, and replacement practices. Sodium Fast Reactor A nuclear reactor that is essentially unmoderated and is cooled by liquid sodium. DG-1383, Page 20 REFERENCES 5 1. American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Division 2, “Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,” 2019 Edition, New York, NY, July 1, 2019.6 2. U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy.” 3. CFR, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter 1, Title 10, “Energy.” 4. ASME, Boiler and Pressure Vessel Code, Section III, “Rules for Construction of Nuclear Facility Components,” Division 1, New York, NY, 2019. 5. ASME, Code for Operation and Maintenance of Nuclear Power Plant, New York, NY, 2020. 6. U.S. Nuclear Regulatory Commission (NRC), Regulatory Guide (RG) 1.28, “Quality