Generic Activity A-10 (Generic Letter 80-95)

GL80095 

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

                               NOV 13 1980 

Licensee: 

Attached for your implementation is the revised and final edition of 
NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle 
Cracking." The report provides the staff's resolution of the NRC's Generic 
Technical Activity A-10, which is an "Unresolved Safety Issue" pursuant to 
Section 210 of the Energy Reorganization Act of 1974. Public comments 
received in response to the "For Comment" edition of April 1980, have been 
incorporated where applicable. Appendix E of NUREG-0619 discusses the 
comments and the staff's disposition of these comments. 

The generic study resulted from the inservice discovery of cracking in 
feedwater nozzles and control rod drive return line nozzles. 

NUREG-0619 describes the technical issues, the technical studies and 
analyses performed by the General Electric Company and the NRC staff, the 
staff's technical positions based on these studies, and the staff's 
requirements for licensee and applicant implementation of the technical 
positions. 

It is expected that requirements contained in the NUREG will be met. 
Accordingly, pursuant to SS 50.54(f) operation reactor licensees are 
requested to furnish, within forty five (45) days of this letter, 
confirmation that the implementation dates indicated in NUREG-0619 will be 
met. For any date that cannot be met, furnish a proposed revised date, 
justification for the delay, and any planned compensating safety actions 
during the interim. After our evaluation of your response the NRC staff will
take action, as necessary to assure that such requirements and commitments 
are appropriately enforceable. This may include, as needed, issuance of a 
Confirmatory or Show-Cause Order. 

Because of the importance of resolving this issue, plants undergoing 
Systematic Evaluation Program (SEP) review will be required to implement 
changes in the same time frame as non-SEP plants. 

                                   Sincerely, 


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

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