United States Nuclear Regulatory Commission - Protecting People and the Environment

Implementation of Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations, Revision 1 (Generic Letter No. 83-15)


                               UNITED STATES 
                       NUCLEAR REGULATORY COMMISSION 
                          WASHINGTON, D. C. 20555 

                               March 23, 1983 

TO ALL LICENSEES OF OPERATING POWER REACTORS AND APPLICANTS FOR OPERATING 
LICENSES (GENERIC LETTER 83-15) 

SUBJECT:  IMPLEMENTATION OF REGULATORY GUIDE 1.150, "ULTRASONIC TESTING OF 
          REACTOR VESSEL WELDS DURING PRESERVICE AND INSERVICE EXAMINATIONS,
          REVISION 1 

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. 

Except in those cases in which an applicant or licensee proposes an 
acceptable alternative method for complying with specified portions of the 
Commission's regulations, the method described in Revision 1 of the subject 
Guide will be used in the evaluation of (1) the results of inservice 
examination programs of all operating reactors after July 15, 1981, and (2) 
the results of preservice examination program of all reactors under 
construction performed after January 15, 1982. The recommendations of this 
guide are not intended to apply to preservice examinations that have already
been completed. We recommend that all licensees modify their technical 
specifications if appropriate, to make them consistent with the 
recommendations in the subject Guide. 

Any guidance in the subject Guide related to information collection 
activities has been cleared under OMB Clearance No. 3150-0011, which expires
April 30, 1985. 

                                   Sincerely, 


                                   Darrell G. Eisenhut, Director 
                                   Division of Licensing 
                                   Office of Nuclear Reactor Regulation 


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