05000267/LER-1979-050, Forwards LER 79-050/03L-0

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Forwards LER 79-050/03L-0
ML19210C667
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 11/09/1979
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19210C669 List:
References
P-79270, NUDOCS 7911190410
Download: ML19210C667 (3)


LER-1979-050, Forwards LER 79-050/03L-0
Event date:
Report date:
2671979050R00 - NRC Website

text

.

I T public Service Company Cf CoHomde 16805 Weld County Road 191/2, Platteville, Colorado 80651 kJ.

e Novenber 9, 1979 Fort St. Vrain Unit No. 1 P-79270 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Com=ission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 REF:

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

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/79-50/03-L-0, Final, submitted per the requf.rements 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/ 79-50/03-L-0.

Very truly yours, T)v7 Don Warecbourg Manager, Nuclear Production DW/alk cc: Director, MIPC 1351 340 y

U s

7 911190 4-) C

REPORT DAIE:

November 9,1979 REPORTABLE OCCURRENCE 79-50 ISSUE O OCCURRENCE DATE:

Octob er 18, 1979 Page 1 of 2 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/ 79-50 /03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On two occasions during the period of October 18 and 19,1979, with the reac-tor operating at power, the motor driven fire pump was removed from service in order to repair an air release valve. These occasions constitute operation in a degraded mode of LCO 4.2.6 and are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DES CRIPTION:

On August 28, 1979, operations personnel performing routine rounds observed that an air vacuum release valve for the motor driven fire pu=p was leaking.

This leakage was not sufficient to render the motor driven fire pump or the fire water system inoperable.

At approximately 1140 hours0.0132 days <br />0.317 hours <br />0.00188 weeks <br />4.3377e-4 months <br /> on October 18, 1979, with the reactor operating at power, the motor driven fire pu=p was removed from service in order to re-pair the leaking air release valve.

The pump was returned to service at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, with the valve repair not yet complete. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on October 19, 1979, the pu=p was again removed from service to complete the required valve repair. The valve repair was completed and the pu=p returned to service at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on October 19, 1979.

Technical Specification LCO 4.2.6, Fire Water Pu=ps, requires that both the engine driven and the motor driven fire pump be operable with the reactor at power. However, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period with either pu=p inoperable is allowed per Section 4.0 of the Technical Specifications. Neither period of inoperiaility exceeded this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time limitation.

CAUSE

DESCRIPTION:

It was necessary to remove the motor driven fire pump from service in order to repair a water leak in an associated air vacuum release ve.1ve.

Cause of valve leakage was determined to be a damaged float and bent float ar=.

135i 341

REPORTABLE OCCURRENCE 79-50 ISSUE O Page 2 of 2 CORRECTIVE ACTION:

The valve was recoved from service and disassembled. The damaged float was replaced and the bent float arm repaired and adjusted. Valve repair was com-pleted and inspected, and the pu=p was returned to service.

No further corrective action is anticipated or required.

Prepared by:

d,r Cathy C. $1rsch Technical Services Technician Reviewed by:

W A ahm echnical Services Supervisor Reviewed by:

Frank M. Mathie Operations Manager Approved by:

M Don Ware = bourg Q'

Manager, Nuclear Production 1351 342