ML19254F766

LER 79-028/03L-0:on 791028,two Primary Containment Isolation Valves Had Seat Leakages in Excess of Tech Spec Requirement. Cause Undetermined.Valves Repaired & Retested.Detailed Rept Will Be Prepared

ML19254F766
Person / Time
Site:	Vermont Yankee
Issue date:	11/13/1979
From:	Conway W VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19254F759	List: ML19254F758 ML19254F766
References
LER-79-028-03L, LER-79-28-3L, NUDOCS 7911160547
Download: ML19254F766 (2)

Text

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VTVYS1 05000271 LER 79-28/3L EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During the performance of refuel outage related surveillance testing in accordance with Tech. Spec. Section 4. 7. A.2.b, two primary containment isolation valves were found to have seat lekages in excess of that per-mitted by Tech. Spec. Section 4.7.A.4. For each valve found to have seat leakage greater than that allowable, a second valve in the applicable line provided the proper containment isolation capability. It is therefore, concluded that there were no adverse consequences of this event to the health and safety of the public. Similar events were reported as RO 77-26/3L and R0 76-24/3L. The two valves and their as-found leakage rates are as follows:

Valve As-Found Description Leakage Rate Test Date V12-68 (Reactor 2.03 lbm/hr 10/17/79 Cleanup Return Line Isolation Valve)

V-16-20-20 Indeterminable 9/28/79 (Containment Purge Makeup Isolation Valve)

Both valves were repaired and satisfactorily retested prior to plant startup as required by Tech. Spec. Section 3.7.A.4.

CAUSE DESCRIPTION AND CORRECTION ACTIONS The valve failures summarized in this report and their repairs and retests will be reported in accordance with Appendix J,10 CFR 50, V.B.3.

7'6 305 w.