ML19291C440

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LER 79-044/03L-0:on 791219,valve V-26-17 Was Blocked from Opening More than 50%.Caused by Placement of Scaffolding by Contractor Personnel.Blockage Cleared & Proper Valve Operation Verified
ML19291C440
Person / Time
Site: Oyster Creek
Issue date: 01/18/1980
From: Ross D
JERSEY CENTRAL POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19291C437 List:
References
LER-79-044-03L, LER-79-44-3L, NUDOCS 8001240433
Download: ML19291C440 (3)


Text

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Jersey Central Power & Light Company

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Mornstown. New Jerse/ 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-44/3L Report Date January 18, 1980 Occurrence Date December 19, 1979 Identification of Occurrence Reactor building to suppression chamber vacuum breaker valve V-26-17 was found to be prevented f rom fully opening more than approximately 50% by scaffolding.

This event is considered to be operation in a degraded mode as allowed by the Technical Specifications, paragraph 3.5. A.4.b, and to be a reportable occurrence as defined in paragraph 6.9.2.b. (2).

Conditions Prior to Occurrence The plant was operating at steady state power.

Power: Reactor, 1701 MWt Generator, 585 MWe b gpm Flow: Recirculation 16 x Feedwater6.33x10{0 lbm/hr Stack s: 2.71 x 100 uci/sec Description of Occurrence On December 19, 1979, the equipment operator assigned to conduct an operability test on the reactor building to suppression chamber vacuum breakers found V-26-17 blocked by scaffolding. He immediately cleared the blockage and con-ducted the test. The operability test was completed satisfactorily.

Apparent Cause of Occurrence This cause of the occurrence is attributed to contractor personnel who placed scaffolding in a position to block the valve from fully opening.

1794 15i C'> _. V PO /, ,s ' : Co~;;r U- J eGeners Pub! c Utit:es S/ stem

Reportable Occurrence Page 2 Report No. 50-219/79-44/3L Analysis of Occurrence The vacuum relief system from the reactor building to the pressure suppression chamber consists of two 100% vacuum relief breaker subsystems (2 parallel sets of 2 valves in series). The purpose of the vacuum relief valves is to equalize pressure so that containment external design pressure limits are not exceeded.

Operation of either subsystem will maintain the suppression chamber external pressure less than its design pressure of 1 psi.

The safety significance of this event is considered minimal because the valve would have opened approximately 50% and because the redundant subsystem is designed to perform the necessary venting function unassisted.

Corrective Action The blockage was immediately cleared and proper valve operation was verified.

Operations and contractor personnel were informed of the incident and reminded of the need to ensure that equipment is not damaged or prevented from performing its intended function.

Failure Data Not applicable

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