Document: NRC Regulatory Guide
Document ID: e1a28538-35cc-4fc2-ab12-2e1d95830205
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:
ames, ducts, and piping, to assure the integrity and capability of the systems. • ARDC-45 indicates that the structural and equipment cooling systems shall be designed to permit appropriate periodic inspection of important components, such as heat exchangers and piping, to ensure the integrity and capability of the systems. • ARDC-53 states that the containment structure shall be designed to permit appropriate periodic inspection of all important areas, such as penetrations. The above ARDC indicate the need for inspection activities, and as mentioned above, the NRC requires applicants for operating and combined licenses to include plans for maintenance, surveillance, and periodic testing of SSCs, which boiling and pressurized water-cooled nuclear power reactors satisfy by implementing ASME Code, Section XI, Division 1 as incorporated in 10 CFR 50.55a. However, neither the ARDC nor the regulations of 10 CFR Part 50 or 52 indicate the appropriate standards to which a PSI/ISI program is to be developed and implemented for non-LWRs. ASME Code, Section XI, Division 2, provides a process for developing a RIM program similar to a traditional PSI and ISI program under ASME Code, Section XI, Division 1, for all types of nuclear power plants. The RIM program contains provisions beyond a traditional program, such as significant use of probabilistic risk assessment (PRA) to develop reliability targets for SSCs within the scope of the program. It also relies on establishing such practices as monitoring, nondestructive examination and repair and replacement to maintain the reliability of components based on the degradation mechanisms that may exist throughout the life of the plant. ASME Code, Section XI, Division 2, also provides a process for the identification of the scope, degradation mechanisms, and reliability targets for the in-scope SSCs; identification and evaluation of RIM strategies and uncertainties; program implementation; performance monitoring; and program