ML19270F676

LER 79-003/03L-0 on 790120:feedwater Check Valve 1-220-62B Was Leaking.Caused by Dirty Valve Seat Preventing Proper Seating of Valve Disc.Valve Seat Was Cleaned & New Kalraz O Ring Installed

ML19270F676
Person / Time
Site:	Quad Cities
Issue date:	02/16/1979
From:	Schnitzmeyer 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-05, LER-79-3-3L-5, NUDOCS 7903070358
Download: ML19270F676 (2)

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'  ;; > 1 While performing the feedwater check valve local leak rate test. the leakaae rate  !

,3 r j through feedwater check valve 1-220-628 was found to be 2558 SCFH. This is in 1

-,t excess of the 18.36 SCFH allowable limit as specified by Technical Specification j

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. 4 fact that the inboard feedwater check valve, 1-220-588, way tested and found to be rm; within acceptable limits. Thus, any back leakage through the B feedwater line would _

have been stopped by check valve 1-220-58B.  ;

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[Y 41 l@ lYl@ l Nl@ lC l6 l6 l5 IQ 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h The valve seat was found to be dirty preventing the proper seating of the valve l1l0l l l

, , disc. The "0" ring was found to be in acceptable condition. The valve seat was l l

, , y cleaned and a new Kairaz "0" ring was installed. Af ter th'c valve was reassembled [

a second local leak rate test was performed. The corrected leak rate was found to l be 4.4 SCFH.  ;

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1. LER NUMBER: 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 20, 1979, local leak rate testing was being performed in accordance with procedure QTS 100-25, Feedwater Check Valve Local Leak Rate Test. The leak rate through feedwater check valve 1-220-62B was found to be 2558 SCFH, which exceeds the 18.36 SCFH limit specified in the Technical Specifications.

Work request 365-79 was written to investigate and repair the leakage.

VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The consequences of this event are minimized by the fact that the inboard feedwater check valve, 1-220-58B, was tested and found to be within acceptable limits. Thus, any back leakage through the B feedwater line would have been stopped by check valve 1-220-58B. Feedwater check valves in the "A" feedwater line 1-220-58A and 1-220-62A each had acceptable leak rate values.

Vll. CAUSE:

Check valve 1-220-62B was disassembled under work request 365-79 The valve seat was found to be dirty preventing the proper seating of the valve disc. The "0"-ring was found to be in acceptabic condition. The last failure of valve 1-220-62B was on March 22, 1977 during the last Unit One refueling outage. The check valve is an 18 inch swing type check valve manufactured by Crane Company.

Vill. CORRECTIVE ACTION:

The valve seat was cleaned and a new Kairaz "0" ring was installed. The valve was reassembled and successfully bench tested. After reinstalling the valve, a local leak rate test was performed on the valve. The corrected leak rate was found to be 4.4 SCFH.