ML20090D834
| 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) | |
Text
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To:
James P. O'Reilly
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_i Directorate of Resulatory Operations I
Region I
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King of Prussia, Pennsylvania 19406
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s From:
Jersey Central Power G Light Company
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Oyster Creek Nuclear Generating Station
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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, b
paragraph 6.6.2.
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Preliminary Approval:
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o /t'c(M 1/9/75 J.T. Carroll,JrgN Date
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- g.- 1 Mr. A. Giambusso./
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8303030032 750109 PDR ADOCK 05000219 400 S
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O Initial. Telephone p/1/8/75 Date of Repsrt Date:.
Occurrence:
1/8/75
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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.
f CONDITIONS PRIOR x
Steady State Power Routine Shutdown
'lV OCCURRENCE:
Hot Standby Operation Cold Shutdown Load Changes During Refueling Shutdown Routine Power Operation Routine Startup Other (Specify)
Operation i
- Ihe major plant parameters at the time of the event were as a
follows:
t Power:
Core, 1916 MWt ii Electric, 674 Mh'e b
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Finw:
Recirc., 15.5 X 104 gpm Feed., 7.6 X 106 lb/hr h
Stack Gas: 27,575 pCi/sec h
DESCRIPTION On Wednesday, January 8, 1975, at approximately 1240, while
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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
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R; port No.. 50-219/75/1 L
Paga 2 E
APPARENT CAUSE Design Procedure j
^OF OCCURRENCE:
Manufacturer Unusual Service Condition Installation /
Inc. Environmental lI Construction Component Failure Other (Specify)
J Operator x
i This failure is attributed to improper valve linkage adjustment I.ll' which resulted in valve overtravel in the previous closin'g I
motion. This overtravel caused the valve disc to jam against the seat.
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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.
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l CORRECTIVE Corrective action involved valve linkage adjustment to climinate l
ACTION:
l the overtravel and subsequent retesting to demonstrate valve y
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operability.
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FAILURE DATA:
N/A 6
Date:
1/9/75 Prepared by:
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