ML19270F662

LER 79-003/03L-0 on 790124:reactor bldg-to-suppression Chamber Vacuum Breaker 1.1601-31B Had Leak Rate of 142.7 Std Cubic Feet Per Hour.Caused by Component Failure.Valve Packing Replaced & Second Leak Test Performed

ML19270F662
Person / Time
Site:	Quad Cities
Issue date:	02/16/1979
From:	Swales J 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-02, LER-79-3-3L-2, NUDOCS 7903070340
Download: ML19270F662 (2)

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44 47 34 M 36 3/ 40 4l 42 CAUSE DESCRIPTION AfJD CORRECTIVE ACTIONS li j ol l The cause of this occurrence was component failure. The leakage was coming through j l,l,yl the teflon packing around the valve shaft. The valve packing was replaced and a i g,j7; l second leak raty test was performed on the volume between valves 1-1601-31B and [

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1. LER NUMBER: LER/R0 78-03/03L-0 ll. 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 24, 1979, a local leak rate test of reactor building-to-suppression chamber vacuum breakers, 1-1601-31B and A0 1-1601-20B, revealed an excessive leak rate of 147.7 SCFH. The test was performed in accordance with procedure QTS 100-29, and the accep-tance criteria is 18.36 SCFH according to Technical Specification 4.7 2.i.2.b. Valves A0 1-1601-20B and 1-1601-31B were leak rate tested by pressuring the volume between them to 48 psig and measuring the pressure decay. During the leak test, it was found that virtually all of the leakage was coming through the stem packing on the 1-1601-31B valve. Work request number 448-79 was written to repair the valve.

The last failure of a reactor building to suppression chamber vacuum breaker to pass its leak test occurred on Unit Two, January 18, 1978, and is reported in LER/R0 78-03/03L.

VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The consequences of this occurrence were minimal because the A0 1-1601-208 valve, which is in-line with the 1-1601-31B valve, would have provided the necessary isolation. In addition, the redundant suppression chamber to reactor building vacuum breakers, A0 1-1601-20A and 1-1601-31A, were fully operable and passed their locak leak rate test.

V. CAUSE:

The cause of this occurrence was component failure. During the local leak rate test, it was determined that most of the leakage was coming through the teflon packing around the valve shaft.

The 1-1601-31B valve is a 20 inch, 150 pound vacuum breaker check valve, manufactured by the Atwood and Morril Company.

Vill. CORRECTIVE ACTION:

The teflon packing was replaced on both sides of the valve shaft.

The volume was again local leak rate tested and the total leak rate was found to be 0.67 SCFH.