ML19345B502

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LER 80-039/03L-0:on 801025,valves V16-20-20 & LRW-83 Found to Have Seat Leakage in Excess of Tech Specs.Cause Not Stated.Valves Repaired
ML19345B502
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 11/24/1980
From: Murphy W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19345B485 List:
References
LER-80-039-03L, LER-80-39-3L, NUDOCS 8012010403
Download: ML19345B502 (2)


Text

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AC FOJ.M 366 - U. S. NUCLEA3 REGULATORY COMMISSION v i7 771

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  • LICENSEE EVENT REPORT LER 80-39/3L CONTROL BLOCK: l 1

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' 8 4J 61 DOCK ET NUMBER 66 69 EV ENT QATI EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h

, le 6: i I While perf or=ing the Type C Leak Rate Testing, two valves (V16-20-20 and LRW-83) 1

o,3, jwere found to have seat leakage in excess of that permitted by Tech. Spec. Section [

lo iai 1 4.7.A.4. Since a second valve in each line provided containment isolation, there l t o , i r were no adverse consequences to the public health and safety. Similar events were I

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io 46 ; l reported as RO 79-28/3L, RO 77-16/3L, and RO 76-24/3L. f

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CAUSE OESCRIPT;ON AND CORRECTIVE ACTIONS 11 1 c i lThe valve- failures summarized in this report and their recairs and retests vill be i f

l1 i : ; treported in accordance with Appendix J, lb CFR '9. V.B'.3. I

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4 VTVYS1 i 05000271 LER 80-39/3L EVENT DESCRIPTION AND PROBABLE CONSEOUENCES During the performance of refuel related surveillance testing .

in accordance with Tech. Spec. Section 4.7.2.a. two primary -con-tainment isolation valves were found to have seat leakages in

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l excess of that permitted by Tech. Spec. Section 4.7.A.4. For each of those valves, a second valve in the applicable line provided the Proper containment isolation capability. .It is, therefore, con-cluded that there were no adverse consequences of this event to the health and safety of the public. Similar events were reported as RO 79-28/3L, RO 77-26/3L, and RO 77-24/3L. The two valves and j their as-found leakage rates are as follows:

Valve As-Found Description Leakage Rate Test Date V16-20-20 (Contain- Indeterminable 9/29/80 ment Purge Makeup Isolation Valve)

LRW-83 (Drywell Indeterminable 9/30/80 Floor Drain)

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

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