ML19283B593
| ML19283B593 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Fermi, Oyster Creek, Hope Creek, Cooper, Pilgrim, Brunswick, Vermont Yankee, Duane Arnold, Quad Cities, FitzPatrick |
| Issue date: | 02/15/1979 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Ippolito T, Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19283B594 | List: |
| References | |
| NUDOCS 7903010061 | |
| Download: ML19283B593 (2) | |
Text
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UNITED STATES j
y" NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 e
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FEB 151979 MEMORANGUM FOR:
D. Ziemann, Chief, Operating Reactors Branch #2, D0R T. Ippolito, Chief, Operating Reactors Branch #3, DOR FROM:
D. G. Eisenhut, Deputy Director, Division of Operating Reactors
SUBJECT:
EVALUATION OF MARK I CONTAINMENT INTERIM ASSESSMENTS OF KULTIPLE-CONSECUTIVE SAFETY, RELIEF VALVE ACTUATIONS In letters dated March 20, 1978, the staff requested that each licensee of a Mark I BWR facility perform an interim assessment of the consequences of multiple-consecutive safety-relief valve actuations. Based on the review by the Plant Systems Branch and Engineering Branch (a subtask of Category A Task A-7) of the licensee responses to these letters, we find that all of the operating Mark I facilities have adequately demonstrated con-formance with the acceptance criteria for the Mark I Containment Short-Term Program. Therefore, continued operation of these plants is justified until this issue is ultimately resolved by the Mark I Containment Long Term-Program. A safety evaluation describing the bases for these conclusions is enclosed.
The enclosed sample letter should be mass-maili.C +.o all affected utilities within seven days of the date of this mer.orandum.
Please see C. Grimes (X27110) sho ld you have any questicns or concerns regarding this action.
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D. G. Eisenhut, eputy Director Division of Operating Reactors
Enclosure:
- 1. Sample letter to licensees
- 2. Safety evaluation
Contact:
C. Grimes, X27110 J. Fair, X28060 7 9 0 3 010 OCo (
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%,t UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 1,'*....a' s
All BWR Licensees (Except Humboldt Bay, Big Rock Point, 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,
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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