05000272/LER-1982-054, Forwards LER 82-054/03L-0.Detailed Event Analysis Encl

Forwards LER 82-054/03L-0.Detailed Event Analysis Encl

ML20063J626
Person / Time
Site:	Salem
Issue date:	08/18/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20063J628	List: 05000272/LER-1982-054, Forwards LER 82-054/03L-0.Detailed Event Analysis Encl 05000272/LER-1982-054-03, /03L-0:on 820731,unidentified RCS Leakage Found to Be Greater than Tech Spec Limit.Caused by Failed Packing on Valve 1CV75.Valve Repacked & Will Be Permanently Repaired During Next Refueling Outage
References
NUDOCS 8209020487
Download: ML20063J626 (3)

LER-1982-054, Forwards LER 82-054/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2721982054R00 - NRC Website

text

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O PSEG i

~

l Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 18, 1982 i

t i

l Mr.

R. C.

Ilaynes i

Regional Administrator USNRC Region 1 631 Park Avenue 1

King of Prussia, Pennsylvania 19406

Dear Mr. Ilaynes:

LICENSE NO. DPR-70 DOCKET NO. 50-272

' REPORTABLE OCCURRENCE 82-054/03L Pursuant to the requirements of Salem Generating Station j

Unit No.

1, Technical Specifications, Section 6.9.1.9.b,

)

we are submitting Licensee Event Report for Reportable Occurrence 82-054/03L.

This report is required within thirty (30) days of the occurrence.

Sincerely yours, f. D I

i H.

J.

Midura General Manager -

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Salem Operations RF:ks /J[

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Distribution i

3 8209020487 820818 PDR ADOCK 05000272 S

PDR j

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Report Number:

82-054/03L Report Date:

08-18-82 Occurrence Date:

07-31-82 Facility:

Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Reactor Coolant System Unidentified Leakage - Out-of-Specification.

This report was initiated by Incident Reports82-204 and 82-208.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 98% - Unit Load 1040 MWe.

DESCRIPTION OF OCCURRENCE:

At 0811 hours0.00939 days <br />0.225 hours <br />0.00134 weeks <br />3.085855e-4 months <br />, July 31, 1982, during performance of Surveillance Procedure SP (O) 4. 4. 6. 2, Reactor Coolant System (RCS) unidentified leakage was found to be 1.8 GPM.

This is greater than the 1.0 GPM allowed by the Technical Specifications, and Action Statement 3.4.6.2.b was entered.

An operator was immediately sent into containment to determine the source of the additional leakage.

At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the operator reported that 1 GPM was leaking from the packing of Pressurizer Auxiliary Spray Isolation Valve 1CV75.

The surveillance was satisfactorily completed and indicated a new unidentified leak rate of 0.4 GPM.

This is below the 1 GPM limit, and Action Statement 3.4.6.2.b was terminated.

i At 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br />, August 2, 1982, the Control Operator noticed an l

increasing indication on the containment air particulate monitor.

l The leak rate, as determined by the Containment Sump Monitoring System, was found to have increased from 0.55 GPM to 2.9 GPM, and at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, Action Statement 3.4.6.2.b was re-entered.

The 3eakage was again identified as being from Valve 1CV75, and unidentified leakage was calculated to be 0.5 GPM.

With leakage in specification, at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br />, August 2, 1982, Action Statement 3.4.6.2.b was terminated.

In both cases, identified leakage was less than the Technical Specification limit of 10 GPM and no l

Reactor Coolant Pressure boundary leakage was observed.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The additional RCS leakage in both instances was due to the failure of the packing on Valve 1CV75.

l l

l

i LER 82-054/03L.

ANALYSIS OF OCCURRENCE:

The RCS leakage limits are based on insuring the ability of detecting. leakt ge from the Reactor Coolant Pressure boundary.

The boundary is one of several design features which prevent the release of radioactive fission products to the environment (the others are the fuel cladding and primary containment).

Since the redundant barriers were maintained, and leakage was subsequently identified as not being from the pressure boundary, no risk to the public or environment was involved.

As such, the occurrence constituted operation in a degraded mode permitted by a limiting condition for operation and is reportable in accordance with Technical Specification 6.9.1.9.b.

Action Statement 3.4.6.2.b requires:

With any pressure boundary leakage, be in at least hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; with any RCS leakage greater than any one of the Technical Specification limits, excluding pressure boundary leakage, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

CORRECTIVE ACTION

As noted, no Reactor Coolant Pressure boundary leakage was observed.

In both instances, unidentified leakage was brought within the 1 GPM limit, and the action statement was terminated.

Due to the increase in leakage past the packing of Valve 1CV75, on August 2, 1982, the packing gland was injected with Furmanite and leakage was stopped.

Permanent repair of the valve will be performed during the next refueling outage.

FAILURE DATA:

Copes-Vulcan Inc.

2" Control Valve Type D-100-100 Prepared By R.

Frahm I

S MkI%

Genefal Ma' nager -

Salem Operations SORC Meeting No.

82-77