Document: NRC Regulatory Guide
Document ID: 2f74adca-9d44-43cf-ba12-0bb95b927199
Document Type: regulatory_guide
Title: Welder Qualification for Areas of Limited Accessibility + HISTORY - HISTORY 10/2016 – DG-1167 , Proposed Revision 1
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0628/ML062840416.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.71
CFR Part: 
CFR Title: 

Content:
eading-rm/adams.html, under Accession No. ML062840416. U.S. NUCLEAR REGULATORY COMMISSION October 2006 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 DRAFT REGULATORY GUIDE Contact: J.B. Hixon (301) 415-5205 DRAFT REGULATORY GUIDE DG-1167 (Proposed Revision 1 of Regulatory Guide 1.71, dated December 1973) WELDER QUALIFICATION FOR AREAS OF LIMITED ACCESSIBILITY A. INTRODUCTION This guide describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for implementing the agency’s requirements regarding the control of welding for nuclear components, as they relate to light-water-cooled and gas-cooled reactors. In particular, General Design Criterion 1, “Quality Standards and Records,” as specified in Appendix A, “General Design Criteria for Nuclear Power Plants,” to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), “Domestic Licensing of Production and Utilization Facilities,” requires that structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. To augment that requirement, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 requires the establishment of measures to ensure the control of materials and special processes such as welding, as well as proper welder qualification. Moreover, 10 CFR 50.55a, “Codes and Standards,” requires, in part, that components of the reactor coolant pressure boundary must be designed, fabricated, erected, and tested in accordance with the standards in Section III, “Nuclear Power Plant Components,” of the Boiler and Pressure Vessel Code promulgated by the American Society of Mechanical Engineers (ASME), or equivalent quality standards. 1 Copies of ASME standards discussed herein may be obtained from the American Society of Mechanical Engineers,