ML20107C859

Forwards Preliminary AO Rept 50-219/74/5

ML20107C859
Person / Time
Site:	Oyster Creek
Issue date:	01/17/1974
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
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References
FOIA-95-258 NUDOCS 9604180040
Download: ML20107C859 (1)

Text

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-to:

James P. O'Reilly Directorate of Rogulatory operations Region I 631 Park Avenuo King of Prussia,' Pennsylvania 19406 Froint.

Jersey Central Power 6 Light Company.

Oyster Crock Xucient Generating Stetion Docket F50 219 Forked River, New Jersey 0873)

Abnormal 0' currence Report No, 50 219/74/ 5

Subject:

e The following is a preliminary report being subraitted in compliance with the Technical Specifications paragraph 6.6.2.

i Prelitninary Approval:

,M, d&M 1/17/74

[,, J. T. Carro)), 'J r, Date cet tir. A, Gl uhusso

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2 l9604180040 960213 5

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Oi R CREEF NUCLEAR GENERATING STA.

N FORKED RIVER, NEW JERSEY 08751 o

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Abnotwal occurronce Report No. 50-219/74/ 5 IDENTIFICATION Violation of the Technical Specifications, paragraph 4,S.P.1,d, i

0F OCCURRENCE:

failure of Main Steam Isolation Valve NSO4A to meet the allow-able leaknge. requirements.

Ei ;,

1his event is considered to be an nbnormal occurrence as de-fined in the Technical. Specifications, paragraph 1.15E CONDITTONS PRIOR 70 OCCURRENCE:

Steady State Power Routine Shutdown

~ ~ Hot Standby Operation ~

Cold Shutdown i,oad Changes Durant Refueling Shutdown Routine Power Operation Routine Startup

_ Other (Specify)

Operation

~

1 The plant was shutdown with the reactor coolant at <212*F, NESCRIPTION 1447 - Lenk rate test on Main Steam isolation Valve NSO4A began.

OP OCCURRENCF.:

1817. Leak rate test on Main Steam Isolution W1ve N504A ended.

Leakage rate was equivalent to 31.7 SCFH. The maximum a!!owable lenkage rate is 9.945 SCFH, as required by Technical Specifica-tion, paragraph 4.5.F.1.d.

@ c3

.APPAT@fr CAUSE hsign POdure or occuRRENCB:

Manufcetura Unususi Service Condition -

~ Insta11ation/

~ Inc. Environemental Construct. ion X

Composent Failure Operator

_ Other (Specify)

After checking the test. assenbly and the corsponents of the MSIV, it W48 determined that the p*cking around the valve shaft was the cause of the excessive leak rate.

1. FAX,YSIS OF The e,afety significance of the failure of NSO4A is dep6ndent OCCURRENCE on the condition of tho insido valvc NS03A. NS03A was con-sidered to have an acceptable leakage rate (2.0 SCFil) when tested on January 13, 1974, flowever, the validity of the test is questionable since the testing procedure assumes minimal leakago through NSO4A. The safety significance will be eval-usted fcIIcWing a retest of N$03A.

CORRECTIVE The valve shaft tiss repacked and the valve was retested sue-essfully. NS03A will be ratested to insure that it has an ACTION:

acceptable leak rate, FAILURB DATA:

the valve stem packing on NSO4A failed on Septetabor 27, 1973 This valve was repacked and passed its leak rate test.

Prepared by:

//d'W/dssf, Date:

1/17/74 o/

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