ML20090D834

Preliminary AO-50-219/75-01:on 750108,during Surveillance Test,Vacuum Breaker V-26-16 Failed to Demonstrate Orerability.Caused by Improper Valve Linkage Adjustment. Valve Linkage Adjusted

ML20090D834
Person / Time
Site:	Oyster Creek
Issue date:	01/09/1975
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
AO-50-219-75-01, AO-50-219-75-1, NUDOCS 8303030032
Download: ML20090D834 (3)

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f 1 To: James P. O'Reilly ~:

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Directorate of Resulatory Operations .$y. I - ;

Region I y 3, ,gt:,v, y 631 Park Avenue King of Prussia, Pennsylvania 19406

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. From: Jersey Central Power G Light Company )

Oyster Creek Nuclear Generating Station Docket #50-219 }*

, Forked River, New Jersey 08731 A

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Subject:

Abnormal Occurrence Report No. 50-219/75/1 t

1hc following is a preliminary report being submitted  !

in compliance with the Technical Specifications, *

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paragraph 6.6.2. >

b Preliminary Approval:

E b o /t'c(M 1/9/75 J.T. Carroll,JrgN Date

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. T;: :g.- 1 7..ea t Mr. A. Giambusso ./

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8303030032 750109 PDR ADOCK 05000219 400 S PDR ,

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Initial. Telephone O

Date of Repsrt Date:. p/1/8/75

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Occurrence: 1/8/75 _

Initial Written Time of Report Date: 1/9/75 Occurrence: 1240 OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnomal Occurrence Report No. 50-219/75/ 1 IDENTIFICATION Failure of one reactor building to torus vacuum breaker valve OF OCCURRENCE:

to demonstrate operability during quarterly surveillance test-ing.

This event is considered to be an abnormal occurrence es de-fined in the Technical Specifications, paragraph 1.15D.

CONDITIONS PRIOR x Steady State Power Routine Shutdown

'lV OCCURRENCE: Hot Standby Operation f Cold Shutdown Load Changes During Refueling Shutdown Routine Power Operation Routine Startup Other (Specify)

Operation

• Ihe major plant parameters at the time of the event were as i a

follows: ,

t Power: Core, 1916 MWt ii Electric, 674 Mh'e b j Finw: Recirc., 15.5 X 104 gpm Feed., 7.6 X 106 lb/hr k Stack Gas: 27,575 pCi/sec h h

DESCRIPTION On Wednesday, January 8, 1975, at approximately 1240, while  ?

OF OCCURRENCE:

• If performing quarterly surveillance testing on the two air- g

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[ operated reactor building to torus vacuum breaker valves, it I l

was found that vacuum breaker V-26-16 failed to demonstrate 1 ik operability. V-26-16 failed to unseat as an increasing differ- 1 ential pressure was applied to differential pressure switch i 4

DPS66A. Testing was terminated when the maximum allowable i opening differential pressure-(0.5 psid) was reached.

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Abnormal Occurrence ( ') (L) [

R; port No.. 50-219/75/1 Paga 2  ;

E APPARENT CAUSE Design Procedure j

^OF OCCURRENCE: Manufacturer Unusual Service Condition ,

Installation / Inc. Environmental Component Failure lI Construction  !

Operator x Other (Specify) J

. i This failure is attributed to improper valve linkage adjustment I.l which resulted in valve overtravel in the previous closin'g l';

I motion. This overtravel caused the valve disc to jam against the seat. ]

s ANALYSIS OF Since the reactor building to torus vacuum relief system is a -

OCCURRENCE: i redundant system and full capacity is available through either ,

I air-operated valve (V-26-16 or V-26-18), the safety significance  ;

of this event is the los:: of redundancy. f f

l CORRECTIVE Corrective action involved valve linkage adjustment to climinate l ACTION: l the overtravel and subsequent retesting to demonstrate valve y i

I operability.

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FAILURE DATA: N/A ,

6 Prepared by: .

_m '_ Date: 1/9/75

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