ML19318A581

LER 80-015/03L-0:on 800511,during Manual Operation of Relief Valves,Valve 1-203-3B Failed to Open.Hpci & Other Valves Operable.Caused by Dirty Contact on Valve Operator hold-in Coil Switch.Switch Replaced & Valve Returned to Svc 800512

ML19318A581
Person / Time
Site:	Quad Cities
Issue date:	06/09/1980
From:	Eagle J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19318A580	List: ML19318A579 ML19318A581
References
LER-80-015-03L-03, LER-80-15-3L-3, NUDOCS 8006230392
Download: ML19318A581 (2)

Text

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. NRC FORM 366 U. S. NUCLE AR R EGULATORY cOMMISSloN 47 779 LICENSEE EVENT REPORT C(/ CONTROL lBLOCK:

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> 3 60 68 69 EVENT DATg 74 75 DATE EVENT DESCRIPTION AND PROSABLE CONSECUENCES h lo :l l While performing the Manual Operation of Relief Valves orocedure 00S 201-1. r'elief 1 i; ,j l valve 1-203-3B failed to open (TS 3.5.D.2) . ,'a accordance with Technical l Io.Agl Specification 4.5.D.2, HPCI was demonstrated to be operable. All other electromatic l Ic ei i relief valves and the Target Rock-safety / relief valve were demonstrated to be j i 3 31 l ope rab le. l l c 71 l l 10 sii I 7 g 3 80 E CO E SLSCO E COMPON ENT CODE SUSCOD'E S' OE loi>l l5 lF l@ y@ l A l@ l Vl AlL IV l0 lP l@ W@ l Z l @ 19 20 a 9 to 11 12 13 18 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT Y E AR R EPORT NO. CODE TYPE N O.

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34 36 40 43 44 47 CJUSE DESCRIPTION AND CORRECTIVE ACTIONS h I :II The cause of this event was component failure due to a dirty contact on the valve l 1- ll operator hold-in coil switch. The hold-in coil switch was replaced and the valve I j i. ,ij was returned-to-service on May 12, 1980 and tested satisfactorily. l 1 '21 I l 11 tali l a 2 80

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l. 'LER NUMBER: LER R0 80-15/03L-0

11. LICENSEE NAME: Commonwealth Edison Company; quad-Cities Nuclear Power Station lit. FACILITY NAME: Unit One IV. DOCKET NUMBER: '050-254 V. EVENT DESCRIPTION:

On-Hay 11, 1980, load on Unit One was reduced to 25 percent power to per-form saml-annual surveillance testing. While performing the manual operation of the electromatic relief valves, surveillance procedure QOS 201-1, the 1-203-3B electromatic relief valve failed to operate from the Control Room switch. The test was performed to comply with the surveillance requirements of Technical Specification 4.5.D.l.b. As required by the LC0 for_ an inoperable relief valve, the HPCI system operability test was immediately performed and successfully completed.

VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The affect of one electromatic relief valve failing to open was minimized

.by the fact that the other relief valves were operable and at no time were any design limits exceeded. All other emergency core cooling systems were available during the time of this occurrence to supply water to the reactor vessel. Therefore, safe operation of the reactor was not affected as a result of this occurrence.

Vll. CAUSE:

1 The failure of the 1-203-38 electromatic relief valve is attributed to a dirty contact on the valve operator hold-in coil switch.

2 The electromatic relief valves are manufactured by the Consolidated Valve Division of Dresser Industries, type 1525-VX.

Vill. CORRECTIVE ACTION:

The hold-in coil switch was replaced and the valve was returned-to-service and test operated satisfactorily on May 11, 1980. On May 12, because of an uncertainty concerning the wiring that was done during the hold-in -

coil switch replacement, HPCI surveillance was initiated and the 1-203-33.

electromatic relief valve was taken out-of-service for wiring corrections.

Following these corrective actions the valve was returned-to-service and tested satisfactorily.

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