05000219/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted

Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted

ML19350B981
Person / Time
Site:	Oyster Creek
Issue date:	03/16/1981
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19350B982	List: 05000219/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted 05000219/LER-1981-009-03, /03L-0:on 810213,snubber 23/3 Found W/Very Low Oil Level & Oil Discovered on Floor at Base Connection During NRC walk-around Insp.Caused by Failure of Inner Shaft Seal Due to Deterioration.Snubber Replaced W/Operable Spare
References
NUDOCS 8103240587
Download: ML19350B981 (3)

LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
2191981009R00 - NRC Website

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OYSTER CREEK NUCLEAR GENERATING STATION f@R:Jf[r L)1 CXJ "?.'f L"c'jb (609)693-6000 P.O. BOX 388

• FORKED RIVER

• NEW JERSEY

• 08731 c-.O.x uuo sm?i'm March 16, 1981

~

s Mr. Boyce H. Grier, Director h

I g'2,ggB Office of Inspection and Enforement c'

a Region I p

United States Nuclear Regulatory Camission 9 S' 631 Park Avenue King of Prussia, Pennsylvania 19406 [C' -

Dear Mr. Grier:

i SURTECT: Oyster Creek Nuclear Generating Station l

Docket No. 50-219 j

Licensee Event Report l

ReEcrtable Occurrence No. 50-219/81-09/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-09/3L in carpliance with paragraph 6.9.2.b.2 of the Technical Specifications.

l Very truly yours, l}?/

Ivan R. Finf

, yr.

Vice Presid t - JCP&L Director - Oyster Crc 1A IRF:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforcanent United States Nuclear Regulatory Cm mission Washington, D.C.

20555 Director (3)

Office of Managenent Infor:raticn

[

and Program Cbntrol e

United States Nuclear Regulatory Ca mission Washington, D. C. 20555 NRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station 180l 0824 05T5Y "

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OYSIER CREEK NUCLFAR GNEPATING STATICN Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-09/3L Report Date March 16, 1981 Occurrence Date February 13,.1981 Identification of Occurrence

- A hydraulic snubber _was found with its tell-tale indicator out of view and oil was disct.vered on the floor. 'Ihe snubber was removed and tested, and it sub-

%equently failed in the ccropression node.

This event.is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.

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- Conditions Prior to Occurrence i

T:.ie plant lwas' operating at steady state power.

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Major Plant Parameters Power:

. Reactor

- 1834 ~ bWt Generator 627 M4e 4

Flow:

Recirculation 15.1 x 10 p 6

Feedwater 6.75 x 10 ;1b/hr Description of Occurrence During a NBC walk-around inspection, snubber 23/3 -(serial number F93501 #7) was found with its tell-tale ' indicator out of view, and oil was disetwered on the

. floor.. 'Ihe' snubber was located on Conh'irment Spray System II, in the southeast corner of the 23' elevation. ' The snubber was 'retoved-and subsequently tested,_

and it' failed its test in the compression mcde.

Apparent Cause of Occurrence h cause of the occurrence was attributed to a broken down inner shaft seal.

-: h snubber was diusambled,' and the inner shaft seal was found partially deteriorated. Seal material apparently enteredLthe hydraulic fluid and pre-

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. vented the shaft fran noving properly in the conpression mode.

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Peportable Occurrence Page 2 o

Feport No. 50-219/81-09/3L Analysis of Occurrence Snubbers are installed to limit piping novatent during seismic events and during transient conditions.. The snubber pistons must also be free to move during normal operations and during a loss of coolant accident in order to compensate for thermal expansion and contraction of the piping system. Snubber 23/3 was located vertically on a 14 inch diameter pipe, and since it failed in the cmpression mode, it would not have performed its intended function for a down-ward piping movenent during a seismic event. At the present time, the significance cannot accurately be determined until a cmplete investigation has been etnpleted, including a stress analysis which nodels the piping syston with snubber 23/3 failed in the compression node. A revision to this reprt will be submitted when this analysis is ccrnplete. -

Corrective Action

The snubber was replaced with an operable spare. Future corrective action will be to rebuild the snubber and retest it before it is released for installation or before it can be declared an " operable spare". A prelinunary engineering evaluation, which r-nds the replacement of all hydraulic snubbers with mechanical snubbers, has been coupleted and sutmitted for corporate engineering review.

Failure Data Manufacturer - Bergen-Patterson Pipesupp rt Corp.

Model - HSSA-10 (max.10,000 lbs. force) l L

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