05000311/LER-1982-112, Forwards LER 82-112/01T-0.Detailed Event Analysis Encl

Forwards LER 82-112/01T-0.Detailed Event Analysis Encl

ML20027C996
Person / Time
Site:	Salem
Issue date:	10/15/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20027C997	List: 05000311/LER-1982-112, Forwards LER 82-112/01T-0.Detailed Event Analysis Encl
References
NUDOCS 8210280152
Download: ML20027C996 (3)

LER-1982-112, Forwards LER 82-112/01T-0.Detailed Event Analysis Encl

Event date:
Report date:
3111982112R00 - NRC Website

text

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" O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 15, 1982 Mr.

R. C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DP R-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-ll2/OlT Pursuant to the requirements of Salem Generating Station Unit No.

2, Technical Specifications, Section 6.9.~1.8.c, we are submitting Licensee Event Report for Reportable Occurrence 82-ll2/0lT.

This report is required within fourteen (14) days of the occurrence.

Sincerely yours, f, SlcEs wJ H.

J. Midora General Manager -

Salem Operations RF:ks CC:

Distribution i

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l Report Number:

82-112/OlT i

Report Date:

10-15-82 Occurrence Date:

10-05-82 Facility :

Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 1

IDENTIFICATION OF OCCURRENCE:

I.

Containment Service Water Leak - No. 21 Containment Fan Coil Unit.

This report was initiated by Incident-Report 82-317.

CONDITIONS PRIOR TO OCCURRENCE:

1 Mode 1 - Rx Power 82% - Unit Load 900 MWe.

DESCRIPTION OF OCCURRENCE:

At 1303 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.957915e-4 months <br />, October 5, 1982, while performing a containment surveillance, an operator discovered a small service water leak of approximately 1.0 GPM on No. 21 Containment Fan Coil Unit (CFCU).

No. 21_CFCU was declared inoperable and the leak was i

isolated.

Prompt notification was made to the NRC by telephone at 1312 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.99216e-4 months <br />, in accordance with NRC IE Bulletin 80-24, with written' confirmation transmitted on October 6, 1982.

Technical Specification Action Statement 3.6.2.3a was already in force as of 1653 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.289665e-4 months <br />, October 4, 1982, when the CFCU had been taken out of service for maintenance.

Both containment spray systems were operable throughout the occurrence.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Investigation of the problem revealed that the leakage was from a flange in the service water piping; a blank had been removed from the flange on October 5, 1982 following Belzona repair of a previous leak on the cooler.

Adverse working conditions in the vicinity of the CFCU make alignment and torquing of the flange difficult.

ANALYSIS OF OCCURRENCE:

Primary containment is a design feature which ensures that the release of radioactive materials in the event of accident con-ditions will be restricted such that site boundary radiation doses will be within the limits of 10CFR100.

r (LER 82-ll2/0lT.

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ANALYSIS OF OCCURRENCE:NRC IE.Bulletin 80-24 requires that any service. water leak inside the containment be' considered as a degradation of the' containment boundary.

If containment pressure increased to'the design pressure of.47 psig during an accident, therefis a possibility of the.re-lease of radioactivity through the service water discharge.

The-occurrence, therefore, constituted an abnormal degradation ~of the primary containment and is reportable in accordance with Technical.

Specification 6.9.1.8.c.

The CFCU's operate in conjunction with the containment spray.

systems to remove heat and radioactive contamination from the containment atmosphere in the event of a. design basis accident.

Operability of either all fan coil groups or of.both containment spray systems is necessary to ensure offsite radiation dose is maintained within the limits of 10CFR100.

Action Statement 3.6.2.3a requires:

With one group of CFCU's inoperable and both contain-ment spray systems operable, restore the inoperable group of cooling fans to operable status within 7 days, 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 />.

Because.the leakage was immediately isolated, containment integrity-was maintained.

Containment cooling capability was provided by the

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containment spray systems.

The occurrence,:therefore, involved no risk to the health or safety of the public.

Due to the loss of redundancy in design and engineered safety features, the^ event constituted operation in a degraded mode permitted by the limiting conditions for operation.

CORRECTIVE ACTION

As noted, the leakage was immediately isolated and prompt notifi-cation of the NRC was performed in accordance with Technical l

Specification 6.9.1.8.

The leaking flange was retorqued, the leakage was stopped, and No. 21 CFCU was satisfactorily tested.

No. 21 CFCU was declared operable, and at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />, October.7, 1982, Action Statement 3.6.2.3a was terminated.

FAILURE DATA:

Not Applicable.

l Prepared By R.

Frahm Generdl Manager -

l Salem Operations SORC Meeting No.

82-92 l

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