05000219/LER-1980-013-01, /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation

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/01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation
ML19309A913
Person / Time
Site: Oyster Creek
Issue date: 03/24/1980
From: Ross D
JERSEY CENTRAL POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19309A906 List:
References
LER-80-013-01T, LER-80-13-1T, NUDOCS 8004010509
Download: ML19309A913 (3)


LER-1980-013, /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation
Event date:
Report date:
2191980013R01 - NRC Website

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EV ENT DESCRtPTION AND F ROB ABLE CONSEQUENCES h b I :' l l On March 9, 1980, the Fire Suppression Water System was removed from l

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I gl Valve V-9-4 was removed and replaced with a new valve.

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>F Mornstown, New Jersey 07960 (201)455 8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-13/IT Report Date March 24, 1980 Occurrence Date

" arch 9, 1990 Identification of Occurrence Violation of the Technical Specifications, paragraphs 3.4.A.7.b. and 3.12.B.3.A, when the Fire Suppression Water System was removed from service to replace valve, V-9-4.

This event is considered to be a reportable occurrence as defined in the Techni-cal Specificat ions, paragraph 6.9.2.a. (9).

Conditions Prior to Occurrence The plant was shutdown for a refueling / maintenance outage.

The reactor was subcritical.

The reactor mode switch was locked in shutdown.

The cavity was flooded.

Description of Occurrence 1

On Sunday, March 9, 1980, the Fire Suppression Water System was removed f rom service to replace Fire Diesel Pump 1-1 discharge valve V-9-4 which was discovered during a surveillance test to have a crack in the volve body.

The NRC was notl-fled on Friday, March 7, 1980, of the plans to remove the Fire System from service to repair V-9-4.

The Fire Suppression Water System was planned to be out of service for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Actual time was only 5-1/2 hours.

The preplanning included the reactor mode switch to be locked in the shutdown position.

An administrative hold was placed on all work being performed on any reactor system that could inadvertantly lower the water level to below 4'8" above 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.

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R2portcblo Occurrcncs No. 50-219/80-13/IT Pagt 2 March 24,1980 were prohibited.

A fire truck pumper supplied by local fire department was used as a back-up supply of fire water.

The pumper would use sea water from the dis-l charge canal and enter the system via hydrant #2. The pumper was only to be used if the Group Shift Supervisor required the Water Suppression 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 Occurrence The cause of this occurrence is attributed to component failure.

The cause of the crack in the body of the valve is under investigation.

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 cther preccutions tcken throughout the plcnt, minimi ed the safety significance of this event.

Upon completion of the job and successful testing, the Fire Water Suppression System was returned to service.

Corrective Action

Valve V-9-4 was removed and replaced with a new valve.

Failure Data Size:

10" Type:

Gate Vendor:

Kennedy Valve 4

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