05000219/LER-1981-046, Forwards LER 81-046/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-046/03L-0.Detailed Event Analysis Encl
ML20011A894
Person / Time
Site: Oyster Creek
Issue date: 10/21/1981
From: Carroll J
JERSEY CENTRAL POWER & LIGHT CO.
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20011A895 List:
References
NUDOCS 8111030329
Download: ML20011A894 (3)


LER-1981-046, Forwards LER 81-046/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2191981046R00 - NRC Website

text

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//A' OYSTER CREEK i

NUCLEAR GENERATING STATION d

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(609)693-6000 P O BOX 388

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  • 08731 October 21, 1981 Mr. Ponald Haynes, Director Office of Inspection and Enforement negion I United States Nuclear Pegulatory Comnission 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

SUBJDCT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-46/3L This letter forwards three copies of a Licensee Event Report to report Report.21e Occurrence No. 50-219/81-46/3L in capliance with paragraph 6.9.2.r.2 of the 'Ibchnical Specifications.

Very truly yours,

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J. T. Carroll, Jr Acting Director ster Creek JIC:dh v

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Enclosures (h[N V cc: Director (40 copies) s Office of Inspection and Enforcement

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NOVO 2193jw 4 Washington, D.C.

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Director (3)

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< d' United States Nuclear Regulatory Coninission Washington, D. C. 20555 NRC Resident Inspector (1)

Oyster Cicek Nuclear Generating Station Forked River, N. J.

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OYSTEP CREEK NUCLEAR GENERATING STATICH Forked River, New Jersey 08731 Licensee Event Report.

Reportable Occurrence No. 50-219/81-46/3L U'

Report Date 4

October 21, 1981 i

Cecurrence Date Septenber 20, 1981 and Septenbo.r 25, 1981 s

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Identification of Occurrence N

During the functional testing of hydraulic snubbers, three'(3) cnubbers 'in the f

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Shutdown Cooling Systen were found with drag loads outside of acceptable limit.3,'.% s and one of the three also failed in the canpression mode. 'Ihis condition is '

N permitted per Technical Specifications section 3.5.A.8 as a limitincycondition -

for operati.on.

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s This event is considered to be a reportable occurrence as defined in the Tschnical.

Specifications, paragraph 6.9.2.b.2.

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Oonditions Prior to Occurrence

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The plant was in the cold shutdown condition.

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On Seputnbor 20 at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, hydraulic snubber #51/18 (serial #477253) locatal -

in Shuuown Cooling Systen Icop B, failed its functional test in the ccanpression mode and also could not obtain drag lmd within acceptable linits. Also, snubber

  1. 51/17 (cerial #487438) in Shutdown Cooling Systen Icop C failed to obtain drag load within acceptable limits. On Septanber 25 at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, snubber #51/19

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(serial #F93502) in Shutdown Cooling Systen Icop A could not. cbtain drag load within acceptable limits. All snubbers were disassenbled and inspected to determino failure mechanisms.

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g ent Cause of Occurrence An inspection of snubber 51/18 revealed rust on the piston head, dirty oil, ard -

a crack in a brass ring on the head cover. Snubber 51/17 was found with a faulty 0-ring, dirty oil, and a scored piston cylinder. Snubber 51/19 was foand to have oil lerJeage around the piston at the top seal assa;bly.

Analysis of Ocmrrence Hydraulic snubbers are installed to limit piping movetent durjng seismic events -

and during transient conditions. Another function is the ability of the piston to move freely during normal operation to ccurpensate for thermal expansion or contraction. All 3 snubbers are nounted in the same manner for each loop; all are perpendicular to the piping and are mounted frcun r.he floor to the piping r

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. ' p. 1 i.T alnost hcdsontally." Tnb.pihing lines are the liistarge lihes frm the Shutdown Jtich rxi horizontally for approximately 20 feet and Cooling heat exchaire.rs] )M!.pdO. feet to a carmon outlet header.

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saniter on each vert.ical lincEdvistreai of the failed snubtors and a pipe supgcrt upstream of the failed snubbers.

I Considering theffact that the plant was in onld shutdown and the Shutdown Cooling

. )n-Systs was ont of service'ior maintenance work, the safety significance of the C

Mont is censidept mininni.s If the plant, had beea shutdown with the Shutdown Cooling Syste'a in operatica), sthe safety significar.a would have been rdnimal

,. ' f' 4 because the piping novemmt, oue to thermal expansion /codtraction would have been in a direction widch would not be affected by the failure of the snnWrs.

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"D the event of "a sftatic event, the safety significance would be minimal because the snubbers would have acted as a rigid sap'jort and would properly restrict

'g,.' piping movment.

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1,', All' 3 anubbers uure replacud withl'.perti,14 sptr(s. !'fhe present' number of snubber V-t' "ailures require.1 1000 testing of snubbers in.adoccxiance with the Technical

' Specifications.- Present plans are tq ccmplete testing of the rernaining snubbers, or replace thm with ncVunits, by DeWr. 15; 1981^.',)\\

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