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:
s are “in the course of preparation” or otherwise under development, applicants may need to develop that information. Such information should be submitted to the NRC for review and approval in the application. Basis for Regulatory Guidance Position 11 Mandatory Appendix V includes tables for examination categories. These tables mimic comparable tables in ASME Code, Section XI, Division 1, which were written for plants that use pressurized components. Several of the tables include pressure-retaining in the title of the table. Although non-LWRs may operate at atmospheric or near atmospheric pressure, these ASME Code, Section XI, Division 1, tables should be considered in the development of RIM strategies and MANDE requirements regardless of the design pressure of the components. This is because some pertinent inspections may be gleaned from considering these examinations. If the operating and accident pressures are very low and will not challenge the integrity of the component, this should be considered in the process for establishing RIM strategies and MANDE requirements. Basis for Regulatory Guidance Position 12 Mandatory Appendix IV, “Monitoring and NDE Qualification,” Article IV-5, “Records,” instructs the user that the MANDEEP shall establish record retention requirements. Records generated under a PSI/ISI program are quality records that come under the record retention requirements of the quality assurance program established under 10 CFR 50 Appendix B for the facility and should be retained in accordance with requirements established in the quality assurance program. Basis for Regulatory Guidance Position 13 Mandatory Appendix VII contains tables of degradation mechanism attributes and attribute criteria in the supplements for various reactor types. The NRC staff noted that the tables did not identify stress relaxation cracking (sometimes referred to as reheat cracking) as a degradation mechanism. Stress relaxation cracking should be considered in