NRC Generic Letter 79-09, Staff Evaluation of Interim Multiple-Consecutive Safety-Relief Valve Actuations

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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