05000219/LER-1980-025-01, /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow

/01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow

ML19329F938
Person / Time
Site:	Oyster Creek
Issue date:	07/01/1980
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19329F932	List: 05000219/LER-1980-025, Forwards LER 80-025/01T-0 05000219/LER-1980-025-01, /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow
References
LER-80-025-01T, LER-80-25-1T, NUDOCS 8007110383
Download: ML19329F938 (3)

LER-1980-025, /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow

Event date:
Report date:
2191980025R01 - NRC Website

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sit 2si V-9-8 and V-9-12 were removed and replaced with new valves. The removed l

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Momstown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-25/IT Report Date July 1, 1980 Date of Occurrence June 18, 1980 ldentification of Occurrence The Fire Suppression Water System was removed from service to replace valve

• V-9-8 and V-9-12.

This event is considered reportable in accordance with paragraph 3.I2.b.3 of the Technical Specifications.

Conditions Prior to Occurrence Reactor Pressure, Atmospheric Reactor Temperature, <212*F Description of Occurrence On Wednesday, June 18, 1980, the Fira Suppression Water System was removeg

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from service to replace Circulating Water Pump and Dilution Pump seal water post indicating valve V-9-12 and loop post indicating valve V-9-8.

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V-9-12 was found, during a surveillance test, to have a non-functioning operator. Valve V-9-8 was observed leaking when isolated for other main-tenance-The NRC was notified on the morning of June 18, 1980, of plans to remove the Fire System from service for repair.

The Fire Suppression Water System was planned to be out of service for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Actual time was only 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The prerequisites included the reactor mode switch to be locked in the shutdown position. An admini-strative hold was placed on all work being performed on any reactor system that could inadvertantly lower the water level to below 4'8" abov'e the top of the core. A roving fire watch patrolled and documented inspections at 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> intervals in all areas required by the Technical Specification. All welding, burning and grinding operations were pro-hibited. A fire truck pumper supplied by the local fire department was used as a back-up supply of fire water. The pumper uculd use sea v.ater Jersey Central Power & Ught Company is a Member of the General Public Utsties System

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3: port ble Occurrsnca No. 50-219/80-25/IT raga 2 July 1, 1980-from the discharge canal and enter the system via hydrant #3 The pumper was only to be used ef the Group Shift Supervisor required the Fire Sup-pression Water System to handle an emergency condition. Startup banks SIA and SIB were in service and electrical buses A, B, C and D were all energized.

Apparent Cause of 9ccurrence The cause of this event is attributed to component failure. Valve V-9-12 was found te have the valve stem disconnected from its disc.

Analysis of_ Occurrence This job was preplanned to prevent unexpected failure of the fire system.

The temporary Fire Water Suppression System, in addition to the fire watches and other precautions taken throughout the plant, minimized the safety significance of this event. Upon completion of the job a,9d successful testing, the Fire Water Suppression System was returned to service.

Corrective Action

Valves V-9-8 and V-9-12 were removed and replaced with new valves. The removed valves will be inspected to determine the cause of the failures.

A revision to this Reportable Occurrence will be submitted upon the com-pletion of the Investigation.

Failure Data V-9-8 Size, 12" Type, Gate Vendor, Kennedy Valve V-9-12 Size, 4" Type, Gate Vendor, Kennedy Valve 1

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