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HEHORANDUM FOR:
Richard DeYoung. Director, O!E Robert B. Hinogue, Director ONRR Carlyle Michelson, Director. 0AE00 Ronald Haynes, Regional Administrator, Region !
James P. O'Railly, Regional Administrator, Region II Janes Keppler, Req 1onal Adninistrator, Region !!!
Johr. Collins, Regional Administrator, Region IV
'Q, Rot,ert Engelken, Regional Administrator, Regio FROM:
Harold R. Denton, Director
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SUBJECT:
DEVELOPMENT OF GENERIC RF. COMMENDATIONS BASED Q a:
ON T11E REVIEW 0F THE JANUA U 25, 1982 STEAM 93 L.-
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GENERATOR TUBE RUPTURE AT GINNA
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A As a result of the Steam Generator Tube Rupture event at Ginna, a id @ @
Force was formed to develop the factual information and significant findings data base, associated with the event and, thereby, provide the required for the development of generic recomendations. The Task Force report (NUREG-0909, NRC Report on the January 25, 1982 Stean
_ Generator Tube Rupture at R. E. Ginna Nuclear Power Plant) was published on April 14, 1982 and a meeting on this report was held with the Comission on that date.
I request that each of your Offices review the Task' Force report, for the development of generic recomendations.
The plant specific aspects of the event are being addressed in the restart safety evaluation being conducted by NRR.
That review / evaluation is seneduled to be issued in a11d-May.
In addition, the Comission suggested that the Task Force members, which were drawn fron a number of Offices, be provided the opportunity to develop their recomendations drawing upon their insights gained in the NUREG-0909 Task Force review. Therefore, to the extent practical, I request that your review of this matter include input from the Task Force members in your Offices.
In order to facilitate the integration of various recomendations, I request that your recomendations for generic action be presented in a format consistent with the Task Force report; that is, recomandations should be identified with: Plant System Response; Human Factors Considerations; Radiological Consequences; Organizational Resoonse; and Post-Event Activities, s
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, MAY 3 1982 Your generic recommendations relative to the Ginna Steam Generator Tude l
Rupture event, as described in NUREG-0909, should be sent to G. Lainas, f
Assistant Director for Safety Assessment, Division of Licensing, Office of Nuclear Reactor Regulation who is coordinating this effort.
We request that you complete your efforts by May 17,1982.
If you have any questions relative to the coordination of this effort, please contact G. Lainas on FT5 492-7492.
@d seed H H. R. Denton Harolo R. Denton, Director Office of Nuclear Reactor Requlation cc:
W. Dircks D. Eisenhut S. Hanauer R. Vollmer R. Mattson H. Thonoson T. Martin, RE:I J. Wiggins, RE:I G. Holahan, NRR
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W. Lanning, AE00 I. V111alva. IE R. Nelson, RE:III S. Bryan, NRR R. Eckenrode, HRR J. Nehemias, NRR T. Chapman, NRR H.'M. Hawkins. IE H. P. Rhfilips, RE:III S. Reynolds, RE: I R. Simmennan. RE:I DISTRiatiTION:
Qentral Fileu ORTB Reading HRDenton Glainas Tippolito S'yy M
- SEE PREVIOUS CONCURRENCE
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