05000311/LER-1982-127, Forwards LER 82-127/03L-0.Detailed Event Analysis Encl

Forwards LER 82-127/03L-0.Detailed Event Analysis Encl

ML20066K587
Person / Time
Site:	Salem
Issue date:	11/10/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20066K592	List: 05000311/LER-1982-127, Forwards LER 82-127/03L-0.Detailed Event Analysis Encl
References
NUDOCS 8211290590
Download: ML20066K587 (4)

LER-2082-127, Forwards LER 82-127/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3112082127R00 - NRC Website

text

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O PSEG Public Service Electric and Gas Comoany P.O. Box E Hancocks Bridge, New Jersay 08038 Salem Generating Station November 10, 1982 Mr. R. C. Ilaynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Ilaynes :

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-127/03L Pursuant to the requirements of Salem Generating Station Unit No. 2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-127/03L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, H. J. Midura General Manager -

Salem Operations RF:ks d[

CC: Distribution 8211290590 821110 PDR ADOCK 05000311 PDR g

The Energy People ggth

'F,2 i G f;!?.b 116 I

L Report Number: 82-127/03L Report Date: 11-10-82 Occurrence Date: 10-20-82 Facility: Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Missed Surveillances - Reactor Coolant System Water Inventory.

l This report was initiated by Incident Reports82-376 and 82-399.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 80% - Unit Load 880 MWe.

DESCRIPTIO!1 OF OCCURRENCE:

At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, October 20, 1982, during routine operation, the Control Room Operator observed that Surveillance Pro-cedure SP (O) 4.4.7. 2.d, Reactor Coolant System (RCS) Water Inventory, had not been performed within the time interval required by the Technical Specifications. The previous RCS water inventory had been performed at 0410 hours0.00475 days <br />0.114 hours <br />6.779101e-4 weeks <br />1.56005e-4 months <br />, October 16, 1982; at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br />, October 19, 1982, the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> surveillance interval plus 25% allowance elapsed, and Action Statement 3.4.7.2.a applied.

An RCS inventory was immediately commenced; surveillance of the containment sump pump and containment radioactivity monitor demonstrated RCS leakage was within limits. Before the RCS inventory could be completed, a small forced load reduction occurred. The Joad reduction was due to a decrease in condenser vacuum resulting from a loss of power to the house heating boiler.

Duc to the load change, steady state RCS conditions could not be maintained. These conditions are required for satisfactory per-formance of the surveillance procedure. The surveillance was subsequently performed when conditions stabilized, and the RCS leak rate was determined to be satisfactory. At 0753 hours0.00872 days <br />0.209 hours <br />0.00125 weeks <br />2.865165e-4 months <br />, October 20, 1982, Action Statement 3.4.7.2.a was terminated.

At 0446 hours0.00516 days <br />0.124 hours <br />7.374339e-4 weeks <br />1.69703e-4 months <br />, October 26, 1982, the Control Room Operator noted that 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> had elapsed since the previous performance of the RCS inventory. The surveillance could not be performed at that time, however, due to a load reduction resulting from planned maintenance on the circulators. Further investigation revealed that the RCS inventory was, in fact, overdue.

I LER 82-127/03L I DESCRIPTION OF OCCURRENCE: (continued)

Technical Specification 4.0.2.b requires that the combined time for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval. The inventory nad been performed, as noted, at 0410 hours0.00475 days <br />0.114 hours <br />6.779101e-4 weeks <br />1.56005e-4 months <br />, October 16, 1982; the third consecutive surveillance was, therefore, due at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br />, October 25, 1982, not on the following day as assumed.

Since the surveillance requirements were not met, Action State-ment 3.4.7.2.a came into effect. The leak rate was again verified to be in specification using the containment sump and radioactivity monitor systems.

When operating conditions stabilized, the RCS inventory was performed. With satisfactory completion of the test, at 1152 hours0.0133 days <br />0.32 hours <br />0.0019 weeks <br />4.38336e-4 months <br />, October 26, 1982, compliance with Limiting Condition for Operation 3.4.7.2 was regained.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

In both instances, timely performance of the test was inadvertently overlooked. The situation was aggravated by the failure of the surveillance requirement to make aliowance for routine, unavoidable transients which preclude performance of the surveillance.

ANALYSIS OF OCCURRENCE:

The reactor coolant leakage detection systems are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. The boundary is one of several design features (others include the fuel cladding and primary containment) which prevent the release of radioactive fission products to the environment in the event of core damage. As noted, RCS leakage was demonstrated to be within limits, indicating the integrity of the pressure boundary was maintained. Furthermore, no degradation of redundant design features occurred. Therefore, no risk to the health or safety of the public was involved. 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 3.4.7.2. 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 Technical Specification limits, isolate or reduce the leakage 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 />.

LER 82-127/03L <

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CORRECTIVE ACTION:

As noted, in both cases, RCS leakage was within specification, in compliance with the action statement. Operating conditions stabilized and the RCS water inventory was immediately performed.

License Change Request 82-14 has been submitted to eliminate the Technical Specification inventory requirement during non-steady state operation.

Operations personnel involved in the incidents were counseled concerning the Technical Specification surveillance requirements.

Finally, to insure completion within the surveillance interval, performance of the RCS water inventory was scheduled on a regular basis.

FAILURE DATA:

Not Applicable.

Prepared By R. Frahm //dN;Jso[u d Gener'al Msnager -

Salem Operations SORC Meeting No.82-101 l

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