ML20084C651

AO 50-219/74-47:on 740912,two Bergen-Paterson Hydraulic Shock & Sway Arrestors on South Core Spray Sys Found Inoperable.Caused by Component Failure.Two Snubbers Replaced W/Units Rebuilt W/Ethylene Propylene Seals

ML20084C651
Person / Time
Site:	Oyster Creek
Issue date:	09/23/1974
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084C654	List: ML20084C651 ML20084C712
References
AO-50-219-74-47, NUDOCS 8304080142
Download: ML20084C651 (3)

Text

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.ersey Central Power & Light Company !(i!

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September 23, 1974 /h

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Deputy Director for Reactor Projects Directorate of Licensing United States Atomic Energy Commission Washington, D. C. 20545

Subject:

Oyster Creek Station Docket No. 50-219

~ Abnormal Occurrence Report No. 50-219/74-47 The purpose of this letter is to forward to you the attached Abnormal Occurrence Report in compliance with paragraph 6.6.2.a of the Technical Specifications.

Enclosed are forty copics of this submittal.

Very truly yours, M!

Donald A. Ross Manager, Nuclear Generating Stations

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es Enclosures cc: Mr. J. P. O'Reiily, Director Directorate of Regulatory Operations, Region 1 .

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PDR ADOCK 05000219 S PDR WPY SENT REGION l -

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Jersey Central Power & Light Company -

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• MORRISTOWN, N.J. 07900

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OYSTER CREEK NUCI. EAR GENERATING STATION ' .

FORKED RIVER, NEW JERSEY 08731 , ~'

Abnormal Occurrence ,

Report No. 50-219/74-47 i

Report Date i

September 23, 1974 i .

i Occurrence Date j September 12, 1974

.J-Identification of Occurrence f-Inoperability of two Bergen-Paterson hydraulic shock and sway arrestors located on the south core spray system. This event is considered to be an abnormal -

4 q occurrence as defined in the Technical Specifications, paragraph 1.15D. ./

a Conditions Prior to Occurrence '

r The plant was at steady state power with majer parameters as follows: _.

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Power: Reactor, 1907 MWt '/

Electric, 646 MWe 7, , 7 Flow: Recirculation, 59.5 x 106 lb/hr ,

Feedwater, 7.13 x 106 lb/hr Reactor Pressure: 1020 psig  ; ,

Stack Gas: 14,300 pCi/sec Description of Occurrence Two snubbers positioned in a pipe chase on the southwest corner of the reactor building were located during a pipe tracing project. Since neither of the units had previously been inspected or counted during previous inspections, their operability was questionabic. Both units were replaced and subsequently tested.

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o o Abnortal Occurrence Report No. 50-219/74-47 Page 2 9

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. There was no oil in the accumulators on either unit. The piston rod on one unit was essentially frozen in position. Although the second unit was stroked I'

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and would " lock up", its motion was not smooth.

Apparent Cause of Occurrence

Component failure is the apparent cause of this occurrence.

, Analysis of Occurrence .

The safety significance of this occurrence was a partial loss of the seismic restraining ability for the affected system. Ilad the plant suffered a design

, basis earthquake, the probability that the system would have suffered structural damage was increased.

Corrective Action The two snubbers were replaced with units rebuilt with ethylene propylene seals.

These snubbers were found during the trace-out of the system by an operator.

This instituted a retrace of all engineered safeguard systems to locate any additional snubbers which may have been overlooked previously. During this subsequent trace-out, four additional snubbers were located -- two on the south core spray system in the clean up filter sludge tank room, which is a high radiation area cnd normally inaccessibic, and two on the north core spray system in the north core spray pump room in areas which were difficult to observe.

These four snubbers were determined to be operabic. All of these snubbers have been added to the snubber surveillance inspection program.

Failure Data Manufacturer: Bergen-Paterson Type: ilSSA-10 J

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