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:
ANDE standard do not contain sufficient specificity for use as a qualification or certification program. Several important sections of ASME ANDE-1-2015 are not defined and are to be determined in the future by specific industry sector committees. It is not possible for the NRC to evaluate a certification and qualification program that has not been defined. For this reason, Code Case N-788-1 and the referenced ANDE-1-2015 are not sufficient on their own as a qualification and certification program able to be used as an alternative to ASME Code, Section XI, Division 1, Subarticle IWA-2300. The American National Standards Institute/American Society for Nondestructive Testing (ANSI/ASNT)-CP-189, “Standard for Qualification and Certification of Nondestructive Testing Personnel” (Ref. 13), may be used as provided in ASME Code, Section XI, Division 1. Basis for Regulatory Guidance Position 6 Section RIM-1.9 addresses standards and specifications referenced within ASME Code, Section XI, Division 2. Table RIM-1.9.1, column “Revision Date or Indicator,” specifies multiple editions or “latest edition” for some standards, methods, or specifications. For the NRC to find the ASME Code, Section XI, Division 2 to be acceptable for use, applicants should cite specific editions for use with the code. An edition of ASME NQA-1, “Quality Assurance Requirements for Nuclear Facility Applications” (Ref. 144), endorsed by the NRC in RG 1.28, should be used. With respect to PRA standard ASME/ANS RA-S-1.4, licensees or applicants should reference Trial Use RG 1.247, “Acceptability of Probabilistic DG-1383, Page 10 Risk Assessment Results for Advanced Non-Light Water Reactor Risk-Informed Activities,”3 which endorses, with conditions, ASME/ANS RA-S-1.4-2021 edition, “Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants.” (Ref. 15). Basis for Regulatory Guidance Position 7 The applicant or licensee should justify why the PRA