ML19338D644

Forwards LER 80-045/03L-0

ML19338D644
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/15/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19338D645	List: ML19338D644 ML19338D649
References
P-80316, NUDOCS 8009230598
Download: ML19338D644 (4)

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\' i PLATTEVILLE, COLOR ADO 80651 September 15, 1980 Fort St. Vrain Unit No. 1 i P-80316 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/

80-45, 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. 50-267/80-45.

Very truly yours, hw Don Warembourg Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC 8009280 Sff 3

REPORT DATE: September 15, 1980 REPORTABLE OCCURRENCE 80-45 ISSUE O OCCURRENCE DATE: August 16, 1930 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLOPJJ)0 16805 UELD CCUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-45/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

A hydraulic oil line on a reheat steam bypass valve failed requiring the iso-lation of Loop 2 group 2 hydraulic valves, which necessitated the shutdown of Loop 2 secondary coolant system.

This is reportable as a degraded mode of LCO 4.3.7 per Fort St. Vrain Techni-cal Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

At approxinately.0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on August 16, 1980, while reducing reactor pcuer, a hydraulic oil line on PV-2244, Loop 2 reheat steam bvpass valve, failed. This resulted in hydraulic oil being sprayed around level 3 (elevation 4771') of the Reactor Building. The hot steam pipes in the area, along with the hy-draulic oli produced thick, heavy smoke, but no flames were detected. Loop 2 group 2 hydraulic valves were isolated, Loop 2 was shutdown as required by LCO 4.3.7, and as a conservative measure, reactor power was decreased to 2%,

and a canual scram was inserted at approximately 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />.

The local fire department was called in to assees possible fire danger and help with fire control if necessary. Plant cleanup was begun as soon as temperatures in the area permitted.

CAUSE DESCRIPTION: -

The failure occurred in a threaded fitting on the valve. The fitting ruptured at the threads. Failure was due to vibration and normal service.

REPORTABLE OCCURRENCE 80-45 ISSUE O Page 2 of 3 CORRECTIVE ACTION:

1 Loop 2 group 2 valves were isolated to terminate the oil leak.

Loop 2 of the secondary coolant system was shut down in compliance with LCO 4.3.7.

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! - A firewatch was stationed and plant cleanup begun.

The ruptured fitting was replaced and system returned to normal.

No further corrective action is anticipated or required.

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d REPORTABLE OCCURRNCE 80-45 ISSUE O Page 3 of 3 4

Prepared By: dd, .

Asa B. Reed Technical Services Technician

Reviewed By

. K Gahn Technical Services Supervisor Y

Reviewed By: \,

Frank '!. Mathie Operations Manager i

i Approved By: tote -~[b; Don Warembourg (/

Manager, Nuclear Production 1

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