Staff Evaluation Of Interim Multiple-Consecutive Safety-Relief Valve Actuations (Generic Letter 79-09)

GL79009 

                               UNITED STATES 
                            NUCLEAR REGULATORY 
                          WASHINGTON, D. C. 20555 

                            February 27, 1979 

All BWR Licensees   (Except Humboldt Bay, Big Rock Point, Dresden 1 and La 
                    Crosse)  

RE:  STAFF EVALUATION OF INTERIM MULTIPLE-CONSECUTIVE SAFETY-RELIEF VALVE 
     ACTUATIONS  

Gentlemen: 

In letters dated March 20, 1978, the staff requested that all licensees of 
BWR facilities with the Mark I containment design perform an interim 
assessment of the consequences of a multiple-consecutive safety-relief valve
discharge event. The enclosed staff evaluation concludes our review of the 
interim assessments. Your submittals and actions for this activity are 
identified in the enclosure.  

Based on our review, we conclude that continued operation of the Mark I BWR 
facilities is acceptable, subject to the corrective actions identified in 
the evaluation, until this issue is ultimately resolved as part of the Mark 
I Long-Term Program. 

                                        Sincerely, 


                                        B. K. Grimes, Assistant Director for
                                             Engineering and Projects 
                                        Division of Operating Reactors 


                                        R. H. Vollmer, Assistant Director 
                                           for Systems and Projects 
                                        Division of Operating Reactors 

Enclosure:  
Safety Evaluation Report  

cc: Service List 

7903230001