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:
r completing PSIs for components initially selected for examination in accordance with the RIM program but lacks information related to the timing for completion of preservice examinations that may be needed due to activities such as repair and replacement, modifications that may add components, or changes that may add existing components into the scope of the RIM program that were not initially included. Paragraph RIM-2.7.3 specifies that preservice examinations shall be documented using encoded equipment and 3 Trial Use RG 1.247 had not been issued as of September 2021, but is expected to be issued by December 2021, prior to this regulatory guide being issued in final form. Plans to issue Trial Use RG 1.247 were discussed at the August 26, 2021, Advanced Reactor Stakeholders Public Meeting (see the meeting presentation at ADAMS Accession No. ML21237A463). This draft RG (DG-1383) does not take a position on the acceptability of ASME/ANS RA-S-1.4-2021 edition, it merely notes that it is the edition that the NRC staff has endorsed for use. Trial Use RG 1.247, endorses, with conditions, ASME/ANS RA-S-1.4-2021 edition; however, applicants and licensees should be aware that the trial use nature of the endorsement means that the NRC staff may depart from it in licensing, make changes to the endorsement in the future, or withdraw it altogether and that such actions would not constitute backfitting under 10 CFR 50.109, “Backfitting” or forward fitting as described in Management Directive 8.4, “Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests” (Ref. 16), or affect the issue finality of an approval under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” 4 Under 10 CFR 50.55a, systems and components of boiling and pressurized water-cooled nuclear power reactors meet ASME Code Section III. Section III provides standards for the design and construction of nuclear facility components and supports.