ML20064J216

/03L-0 on 781108:during Performance of Type C Containment Penetration Leak Test,12 Valves Were Found to Be Leaking at a Rate Greater than Maximum Measurable on Leak Rate Monitor Caused by Excessive Valve Leakage

ML20064J216
Person / Time
Site:	Beaver Valley
Issue date:	12/22/1978
From:	Werling J DUQUESNE LIGHT CO.
To:
Shared Package
ML20064J198	List: ML20064J194 ML20064J216 ML20064J226 ML20064J229
References
LER-78-059-03L, LER-78-59-3L, NUDOCS 7812290223
Download: ML20064J216 (3)

Text

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7 8 60 el DOCKET NUMuf M be 69 EVENT DATE 74 75 REPORT CATE 80 EVENT OESCRIPTION ANC PROB A8LE CONSEQUENCES h O 2 l Durinn the performance of Type C Containment Penetration Lenk Testine_ evelvo I g l valves were found to be leaking at a rate greater than the maximum measurable l 0 A l on the leak rate monitor (300 SCF per day). The leaking valves presented minimal l

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33 34 31 40 4 g CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS The valves were repaired and g l The incident resulted from excessive valve leakage.  ;

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Attechment To LER 78-59/03L Beaver Valley Power Station DUQUESNE LIGHT COMPANY Docket No. 50-334 During the performance of Type C containment penetration leak testing, the following valves were found to be leaking at a rate greater than the maximum measurable on the leak rate monitor (300 SCF/ day):

1. TV-CC-105El - RCP 1A component cooling water outlet containment inside isolation valve

2. HY-119 - Recombiner lA return line inside containment check valve

3. CH-181 - RCP 1A seal supply check valve

4. CH-183 - RCP 1C seal supply check valve

5. Personnel air lock inner door equalizing valves

( 6. SI BIT check valve to RCS cold leg injection

7. SI SI Pump 1A check valve to hot leg injection

8. SI SI Pump 1B check valve to hot leg injection

9. MOV-SI-890A - SI Pump 1A discharge valve to RCS hot legs

10. MOV-SI-890B - SI Pump 1B discharge valve to RCS hot legs

11. SI-451 - MOV-SI-890A valve disc vent

12. SI-452 - MOV-SI-890B valve disc vent The safety significance of each of the leaks is discussed below.

1. Reactor Coolant Pump 1A component cooling water outlet containment inside isolation valve (TV-CC-105E1]. The redundant isolation valve outside containment [TV-CC-105E2] was available and exhibited leakage within the allowable limits. During accident conditions, leakage from this line would present no unreviewed safety problem.

2. Recombiner 1A Return Line inside containment check valve [HY-119]. The

(. redundant isolation valve outside containment [HY-110] was available and exhibited leakage within the allowable limits. During accident conditions, leakage from this line would present no unreviewed safety problem.

3. Reactor Coolant Pump 1A and 1C seal supply check valves [CH-181] and

& 4. [CH-183]. The redundant isolation valves outside containment [MOV-CH-308A]

and [MOV-CH-308C] were available and exhibited leakage within the allowable limits. During accident conditions, leakage from this line would present no-unreviewed safety problem.

5. Air Lock Inner Door Equalizing Valves. Although the inner door equalizing valves leaked, the outer door equalizing valves exhibited leakage within allowable limits. During accident conditiens, leakage from this pathway would present no unreviewed safety problem.

1

.LER 78-59/03L Duquesne Light Company i Docket No. 50-334 Attachment - Page 2 4D r

6. Boron Injection Tank check valve to Reactor Coelant Cold leg injection paths [SI-94]. Redundant valves [SI-91], [MOV-SI-867C] and [MOV-SI-867D]

in this pathway exhibited leakage within the allowable limits. During accident conditions this line serves as a primary injection pathway for highly borated water which would preclude the possibility of any leakage from the containment atmosphere to the oatside envi.onment.

7. Low Head Safety Injection Pumps lA ar.d 1B hot leg discharge valves, check 8,9,10, valves and valve disc vents [MOV-SI-890A], [MOV-SI-890B], [SI-13], [SI-14],

11,12. [SI-451] and (SI-452]. Although these valves failed the leak rate test, this is not considered to be significant since under accident conditions the Low Head Safety Injection pumps would be operating and these lines I would be pressurized to a pressure much higher than the peak containment pressure during the initial phase of safety injection and will be in injection service during the long term phase.

The valves were repaired and the tests were repeated. The valve leakage was acceptable in the retest.

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