ML19331B904

Forwards LER 80-037/03L-0

ML19331B904
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/08/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19331B905	List: ML19331B904 ML19331B908
References
P-80252, NUDOCS 8008130509
Download: ML19331B904 (5)

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pubMe Service Company & Collende

} 16805 ROAD 19%

__ i. / PLATTEV1LLE, COLOR ADO 80651 August 8, 1980 ,

Fort St. Vrain Unit No. 1 P-80252 1

Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012

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/

80-37, 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. 50-267/80-37.

Very truly yours, Y

Don Warembourg m,fwC Manager, Nuclear Production DW/cis Enclosure ec: Director, MIPC 003

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REPORT DATE: August 8, 1980 REPORTABLE OCCURRENCE 80-37 ISSUE O 0CCURRENCE DATE: July 11, 1980 ,

Page 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION ,

PUBLIC SERVICE COMPANY OF COLOPJLDO 16805 WELD COUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT No. 50-267/80-37/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On July 11, 1980, the reactor was operated at power with only one complete operating PCRV liner cooling water loop.

This constitutes operation in a degraded mode of LCO 4.2.13, and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

At 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> on July 11, 1980, with the reactor operating at approx 1=ately 1.8% thermal power, both pumps in one loop of the PCRV liner cooling system were shutdown in order to perform pipe welding in conjunction with a hanger installation.

Technical Specification LCO 4.2.13, PCRV Liner Cooling System, provides that the plant may be operated at power for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with only one complete operating liner cooling loop.

At the time the pu=ps were taken out of service, the reactor was not at power, and the intent was to remain at less than 2% until the system was returned to nor=al. However, due to changing plant conditions, the hourly average power level as recorded from the linear power channels exceeded 2%

for three readings with only one liner cooling loop in operation. Refer to the table on the next page for hourly average reactor power levels during the time period covered by this report.

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REPORTABLE OCCURRENCE 80-37 ISSUE O Page 2 of 4 EVEhT

• DESCRIPTION: (Cont'd)

Time Hourly Average Reactor Power Level 0600 1.8%

0700 1.8%

0800 1.8%

0900 1.8%

1000 1.9%

• 1100 2.2%

1200 1.4%

1300 1.6%

• 140C 2.9%

• 1500 2.3%

1600 1.1%

1700 1.3%

• Reactor at power Although the intent was to remain at less than 2% power, the three hourly average readings noted above were slightly greater than 2%. A literal inter-pretation of the definition of " power operation" indicates that the hourly periods ending at 1100, 1400, and 1500 constituted operation in a degraded mode permitted by LCO 4.2.13 a).

Following the 1500 hour0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> read.ag, no further degraded mode operation occurred.

By 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />, the construction work had been completed and the system re-stored to normal operation within the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> allowed by the LCO.

CAUSE DESCRIPTION:

Removal of one PCRV liner cooling loop from service, coupled with three brief periods of reactor power operation, resulted in operation in LC0 4.2.13 de-graded mode.

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e l REPORTABLE 6CCURRENCE 80-37 ISSIT 0 Page 3 of 4 CORRECTIVE .

ACTION:

Following the 1500 hour0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> reading, no further operation occurred with the re-actor at power.

By 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />, construction work had been completed and the system returned to service.

-No further corrective action is anticipated or required.

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REPORTABLE OCCURRENCE 80-37 ISSUE O Page 4 of 4

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Prepared By: (oMm s Cathy C. Hirsch Technical Services Technician Reviewed.By: Mhv , Zy J. W.' Gahn /

Technical Services Supervisor Reviewed By:

Frank M. Mathie Operations Manager Approved By: h bf M V'

Don Warembourg Manager, Nuclear Production i

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