ML20117C603
| ML20117C603 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Browns Ferry |
| Issue date: | 10/07/1983 |
| From: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Olshinkski J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20114F930 | List:
|
| References | |
| FOIA-84-616 NUDOCS 8505090470 | |
| Download: ML20117C603 (1) | |
Text
UNITED ST ATES pm EE CO NUCLEAR REGULATORY COMMisslON p
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- E 101 M ARIETT A STREET.N.W.
ATLANTA, CEORGIA 30303
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November 8, 1983 i
NMEMORANDUM FOR Richard C. Lewis, Director Division of Project and Resident Programs FROM:
John A. 01shinski, Director Division of Engineering and Operational Programs
SUBJECT:
BROWNS FERRY MAIN STEAM RELIEF VALVE TAILPIPE 10-INCH VACUUM BREAKERS Reference your memo of October 7,1983, regarding concerns on redesign of the vacuum breakers.
On November 3 a conference call was held between the plant manager of Browns Ferry and members of NRC staff to address the question of safety of Unit 2 continued operation. The plant manager stated that the valves installed in Unit 2 had displayed sticking open during testing but that only a small force was required to close it.
Also, the valves are intended to be replaced at the end of this cycle. The staff (including the senior resident) agreed that the indicated problem was resolved. This should answer Item "d".
Item a asks the safety concern of the valve not reseating. This case is bounded by the Design Basis Accident LOCA. However, for normal operating transients, the design basis should be as stated in the FSAR, Section 4.4.4 " Nuclear Steam Pressure Relief System Design Basis (1) The nuclear system relief valves shall not discharge to the primary containment drywell." This requires that the vacuum relief valves be tested and qualified such that operation within the design basis is assured.
Items b and c address specific areas which will be inspected during the next routine inspection, but before January 31, 1984.
[ N($Y' John A. Olshinski l
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8505090470 e41002 FI
-616 PDR
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