ML19270F659

LER 79-003/03L-0 on 790130:1-2001-4 Valve Leak Rate Was 26.0 Std Cubic Feet Per Hour.Caused by Worn Valve Stem Packing.Valve Packing Replaced

ML19270F659
Person / Time
Site:	Quad Cities
Issue date:	02/16/1979
From:	Tielz G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17296A304	List: ML17296A303 ML19270F656 ML19270F659 ML19270F662 ML19270F668 ML19270F673 ML19270F676 ML19270F679 ML19270F682 ML19270F683 ML19270F684
References
LER-79-003-03L-01, LER-79-3-3L-1, NUDOCS 7903070338
Download: ML19270F659 (2)

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.[ While performing the local leak rate test on the drywell floor drain sump isolation  !

- - - ,. valves, A0 1-2001-3 and 4, it was determined that the 1-2001-4 valve leak rate l

{ was 26.0 SCFH. The safety implications of this occurrence are minimal due to the fact j

, - - that the redundant Isolation valve in the drywell sump line, A0 1-2001-3, had a  ;

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{iloll The cause of the excessive Icakage was due to a worn valve stem packinq on the 1-2001-4 I g,gi;l valve. '.e valve packing was replaced and the volume between valves A01-2001-3 and I

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,,,,,; 4 was retestcd. The corrected combined leak rate is 1.85 SCFH. [

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1. LER NUMBER: LER/R0 79-03/03L-0

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

On January 30, 1979 while performing a local leak rate test on the drywell floor drain sump isolation valves, A0 1-2001-3 and 4, it was determined that the 1-2001-4 valve leak rate was 26 SCFH. This is in excess of the 18.36 SCFH allowable limit as specified by Technical Specification 4.7.A.2.i.2.b. The test was done in accordance with procedure QTS 100-16. While the volume between the two valves was pressurized, application of a soap bubble solution indicated leakage through the stem packing of the 1-2001-4 valve.

VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The safety implications of this occurrence are minimal due to the fact that the redundant isolation valve in the drywell sump line, A0 1-2001-3, had a leak rate of only 1.85 SCFH.

Therefore, had a Group Two isolation occurred, the drywell sump line would have been isolated.

Vii. CAUSE:

The cause of this occurrence is attributed to component failure.

Worn valve stem packing caused the leakage. The packing was manufactured by Crane Packing Company, style number 1871, size one inch by one and a half Inch.

Vill. CORRECTIVE ACTION:

The immediate corrective action was to write a work request to replace the valve packing. Af ter the packing was replaced, the valve was local leak rate tested again. The corrected combined leak rate of the volume between both valves is 1.85 SCFH.