ML20085E561

LER ER-76-011:on 760328,test on Penetration 46 Indicated Leakage Above Acceptable Limits.Caused by Worn Valve Seats

ML20085E561
Person / Time
Site:	Palisades
Issue date:	05/06/1976
From:	Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20085E564	List: ML20085E561 ML20085E569
References
LER-ER-76-011, LER-ER-76-11, NUDOCS 8308150358
Download: ML20085E561 (2)

Text

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UCENSEE EVENT REPORT CONTROt 8LOCx:l_ l l I I I I pts nr att a usiso minnassarion) 1 8

[ UCENsE NUMBER T . T E I sir lPl Al Ll1l l 6 l 0l-l0 l 0 l 0 l 0l 0l-l 0 l 0 l l hl 1l 1l1 l1l l0l1l 7 89 14 15 25 28 30 31 32 DOCKET NUM8ER EVENT DATE REPORT DATE O COwr l l l @ souRC[LJ l 01 si 01-10121 si sl 10 I a l 2181716 I I 01 s101617 I 61 7 8 57 58 59 80 81 88 89 74 75 80 EVENT DESCRIPTION Q lDuring the Palisades local leak rate testing, the test on penetration #h6 showed l 7 89 80

@ lleakage above acceptable limits (about 111 liters / min). The leakage was associated I 7 89 80 Q lwith one of two in series valves. The second valve performed satisfactorily. l 7 R9 80

@ lAffected parts replaced. (ER-76-011) I 7 8 80

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CEDE NE CCMPONENT CODE VELATEN 7

'M 89 10 lSl DI W 11 12 lVI Al LIVI El X]

17 W43 44 l M I 1 l 21 0l 47 48 CAUSE OESCRIPTION HG l The valve (CV-1101) is a h" globe valve with Teflon soft seats. Inspection dis- l 7 89 80 32 l closed that the seats were vorn from use (normal wear). The valve is a 150 psi ASA l 7 89 80 3 I rated valve made of carbon steel, Model 38-20571, and is air operated. I s  % POWER OTHER STATUS O Ovt OaSCOVERY OESCRIPTON 1

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9 l0 l010 l l 10 12 13 NA I 44 d45 l 48 NA l 80 RELE O O E AMOUNT OF ACTMTV LOCATON OF RELEASE E LZ_J 9

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7 8 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTON DE 10101 d Lzj l NA J'

7 89 11 12 13 a0 PERSONNEL INJURIES NUMBER DESCRIPTON 3[ l 0l 010 l l NA l

7 89 11 12 80 PROBABLE CONSEQUENCES i 3E INone. Redundant valve operated properly. l  !

7 89 80 LOSS OR OAMAGE TO FACIUTY TYPE DESCRIPTON 7 89 32 [Z_} 10l NA l 80 PUBUCITY 30 I NA l 7 89 80 AOOITIONAL FACTORS .

, 89 El NA l 8308150358 760506 80 ,

PDR ADOCK 05000255 l 19 l S PDR I 7 89 80 l

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Mr James G. Keppler  ;~ g[13 jogy -

Office of Inspection Enforcement , (. , , f~g Region III \~- cem:ssum US Nuclear Regulatory Co= mission

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799 Roosevelt Road Glen Ellyn, IL 60137

\l ];s 4, t ; La f DOCKET 50-255, LICENSE DPR PALISADES PLANT, ER-76-011 CONTAINMENT ISOLATION VALVE  !

l Attached is a Licensee Event Report which relates to the Palisades Plant. I This event was originally thought to be nonreportable since containment l integrity was not required at the time the problem was observed and a i second isolation valve performed satisfactorily. Later review disclosed i that it may be reportable as " abnormal degradation discovered in the pri- '

mary containment." Such an interpretation must conclude that degradation of one of two in series valves designed to isolate containment is intended ~

to be reported under the prompt notification requirements. '

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1 David A. Bixel ,

Assistant Nuclear Licensing Administrator CC: R. A. Purple, USNRC i

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