05000267/LER-1981-065, Forwards LER 81-065/03L-0.Detailed Event Analysis Encl

Forwards LER 81-065/03L-0.Detailed Event Analysis Encl

ML20033A577
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/16/1981
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20033A578	List: 05000267/LER-1981-065, Forwards LER 81-065/03L-0.Detailed Event Analysis Encl 05000267/LER-1981-065-03, /03L-0:on 811017,hot Reheat Header Activity Monitors Temporarily Out of Svc for Completion of Radiography.Caused by Exccessive Leakage in Feedwater Heater 5.Radiography Required to Verify Welds
References
P-81294, NUDOCS 8111250591
Download: ML20033A577 (4)

LER-1981-065, Forwards LER 81-065/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671981065R00 - NRC Website

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16805 Road 19 1/2, Platteville, Colorado -80651-9298 November 16, 1981 Fort St. Vrain Unit No. 1 P-81294

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Mr. Karl V. Seyfrit, Director

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A} NOV2 41931* 7 Nuclear Regulatory Commission IJ Region IV

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Office of Inspection and Enforcement

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Reference:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/81-065, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/81-065.

Very truly yours,

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Don Warembourg l

Manager, Nuclear Production i

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REPORT DATE:

November 16, 1981

. REPORTABLE OCCURRENCE 81-065 ISSUE O OCCURRENCE DATE:

October 17, 1981 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2.

PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/81-065/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During the period between October 17, 1981, through October 19, 1981, the hot reheat header activity monitors were taken out of service.on several occasions This is a degraded mode of LCO 4.4-1, Table 4.4-2, and is repo. table per Fort St.

Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

At the beginning of October, a leak across the #5 feedwater heater

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tube sheet was discovered. The leak was large enough to preclude operation above 70% power.

The heater isolation valves were also found to be leaking-excessively which prevented isolation of the heater during operation of the plant to effect neccessary repairs of the heater.

To enable the testing (RT-500K) to be completed before the scheduled maintenance period, it was decided to remove #5 feedwater heater from the normal feedwater header and cap the heater isolation piping.

Operation of the plant could continue on the emergency feedwater header.

On October 5,

1981, the transfer to the emergency feedwater header was made, and the repair modification to the normal feedwater header began On October 17, 1981, the welding was started on the #5 heater piping Radiography was required at various points in the procedure to verify the quality of the welds. The hot reheat header. activity monitors were in close proximity to the work area. To prevent loop shutdowns on high header activity from being initiated by the radiogr1phy source, the reheat activity monitors were removed from service. This was done using approved procedures which were reviewed and approved by the Plant Operations Review Committee. The activity monitors were only taken out of service during the actual radiography and were returned to service immediately after the exposure was

,. completed.

In all cases, the activity monitors were returned to service within the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limit required by LC0 4.4.1.

The welding and radiography were completed on October 19, 1981, and the normal feedwater header was returned to service at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br />.

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REPORTABLE 0CCURRENCE 81-065 ISSUE O Page 2 of 3

CAUSE

DESCRIPTION:

Radiography required per Quality Assurance Procedures necessitated removing these instruments from service to prevent undesired loop shutdowns.

CORRECTIVE ACTION:

' The instruments were returned to service following the required radiography.

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REPORTABLE. OCCURRENCE 81-065-ISSUE O Page 3 of 3 Prepared By:

Paul Moore Technical Services Technician 4

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Reviewed By:

L Charles Fuller Technical Services Engineering Supervisor Reviewed 'By:

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Edwin D. Hill l

Station Manager 7VM_

Approved By: _ Don Warembourgg Manager, Nuclear Production l

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