Document: NRC Regulatory Guide
Document ID: c55ba6c5-aa2d-4ad6-aba2-2001e16524ab
Document Type: regulatory_guide
Title: Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1221/ML12216A015.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.150
CFR Part: 
CFR Title: 

Content:
oREG UNITED STATES 0~d NUCLEAR REGULATORY COMMISSION 0 oWASHINGTON, D. C. 20555 February 1, 1983. -Regulatory Guide 1.150 Revision I REGULATORY GUIDE DISTRIBUTION LIST (DIVISION 1) SUBJECT: REVISION 1 TO REGULATORY GUIDE,1.150 The original version of Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations," dated June 1981, was reviewed by the Ad Hoc Committee of the Electric Utility Industry. The Committee's review resulted in their recommending an alternative method, which was presented in "Final Report - Recommended Changes to Regulatory Guide 1.150," August 1982. The NRC staff has evaluated the recommended alternative method in the report and finds it an acceptable alternative. Therefore, this alternative method has been added to the regulatory positions in Regulatory Guide 1.150, and this Revision 1 is being issued as an active guide without prior issuance as a draft guide for comment. Of course, comments and suggestions for improvements in guides are encouraged at all times. Guides will be revised, as appropriate, to accommodate comments and to reflect new information or experience. Robert B. Minogue, D rector Office of Nuclear Regulatory Research U.S. NUCLEAR REGULATORY COMMISSION Revision 1 February 1983 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.150 ULTRASONIC TESTING OF REACTOR VESSEL WELDS DURING PRESERVICE AND INSERVICE EXAMINATIONS A. INTRODUCTION Criterion 1, "Quality Standards and Records," of Appen- dix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," requires, in part, that components important to safety be tested to quality standards commen- surate with the importance of the safety functions to be performed. Where generally recognized codes and standards are used, these codes and standards must be evaluated to determine their adequacy and sufficiency and must be sup-