ML19309E757

Forwards LER 80-015/03L-0

ML19309E757
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/18/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19309E759	List: ML19309E757 ML19309E760
References
P-80082, NUDOCS 8004240323
Download: ML19309E757 (4)

Text

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7"' pubuc servlee company of Ceno m de

,; 16805 Weld County Road 191/2, Platteville, Colorado 80651

_s April 18, 1980 Fort St. Vrain Unit No. 1 P-80082 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:

Enc 1csed please find a copy of Reportable Occurrence Report No. 50-267/

80-15, 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. 50-267/80-15.

Very truly yours, h Ww Don Warembourg Manager, Nuclear Production DW/cls Enclosure cc: Director, MIPC Roa s

Iff 8004240 D23

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REPORT DATE: April 18, 1980 REPORTABLE OCCURRENCE 80-15 ISSUE O OCCURRENCE DATE: March 20, 1980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 tiELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-15/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

From 1115 to 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on March 20, 1980, with the plant operating at approximately 60% thermal power and 216 MRe, the emergency feedwater header supply to Loop 2 helium circulator water turbine drives was isolated to repair a leaking pressure control valve.

This resulted in operation in a degraded mode of LCO 4.2.2(a) and is re-portable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

On March 6,1980, a Plant Trouble Report was initiated indicating that PV-21244 (pressure control valve on emergency feedwater header supply to Loop 2 circulator water turbine drives) was leaking. This problem in it-self did not render the valve or the emergency feedwater supply to the Loop 2 circulators inoperable.

The affected pressure control valve is designed to control the feedwater supply to the water turbine drives under flow conditions. Under the no-flow conditions which existed at the time, a second pressure control valve (PV-21244-1) is provided to bleed off any valve leakage from PV-21244 to the turbine water drain tank. Because the leakage through PV-21244 was suf-ficient that PV-21244-1 could barely accomodate the flow, a decision was made to isolate the emergency feedwater supply to Loop 2 circulators in order to repair PV-21244.

The emergency feedwater supply to Loop 2 helium circulator pelton drives was isolated from 1115 to 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on March 20, 1980. The Loop 2 emergency feedwater header supply was returned to service within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period allowable per LCO 4.2.2(a); thus, all helium circulatorc were oper-able during this time period.

Had it been necessary, the Loop 2 circulators could have been operated on water turbine drive at reduced speed utilizing a water supply from the emergency condensate or firewater systems.

H REPORTABLE OCCURRENCE 80-15 ISSUE O Page 2 of 3 CAUSE  !

DESCRIPTION:

Cause of this valve leaking through was a loose bolt on the block which locks the operator stem to the valve stem. This did not allow proper valve stroking, which resulted in leakage past the valve seat.

CORRECTIVE ACTION:

The block which locks the operator to the valve stem was cleaned and re-assembled. Valve stroke was calibrated, and the valve and system were returned to service.

No further corrective action is anticipated or required.

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s REPORTABLE OCCURRENCE 80-15 ISSUE O Page 3 of 3 Prepared By: d/s /

Cathy C. Hirsch v

[A l Technical Services Technician Reviewed By: ,

V J. V.4 Gahm f Technical Services Supervisor i

Reviewed By: K /v7 %7b [A. /6 W Frank M. Mathie /

Operations Manager l

f Approved By: Whwb Don Warembourg g Manager, Nuclear Productfon i

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