05000267/LER-1981-023, Forwards LER 81-023/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-023/03L-0.Detailed Event Analysis Encl
ML20004C369
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 04/09/1981
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20004C370 List:
References
P-81120, NUDOCS 8106030266
Download: ML20004C369 (4)


LER-1981-023, Forwards LER 81-023/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2671981023R00 - NRC Website

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April 9,1981 Q'

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4s Mr. Karl V. Seyfrit, Director Nuclear Regulatory Comission 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/

81-023, 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. 50-267/81-023.

Very truly ycurs, WttA6 Don 14rembourg 9

Manager, Nuclear Production DW/cis Enclosure ec: Director, MIPC g) s l

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REPORT DATE:

April 9. 1981 REPORTABLE OCCURRENCE 81-023 ~

ISSUE O OCCURRENCE DATE:

~ March 10. 1981-Page 1 of 3 i

PURT ST. VRAIN NUCLEAR GENERATING-STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19.1/2' PLATTEVILLE, COLORADO-80651 REPORT No. 50-267/81-023/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During a greater than 10 spa release from the reactor building sug, it was discovered that,the proportional sampling system was inoperable. This is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2 as a de-graded mode of LCO 4.8.3.

EVENT i

DESCRIPTION

On March 10,1981, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, a tegorary pump was installed in the reactor building sump due to the ino.perability of the n9rmal sump pumps.

At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, af ter completing the pre-release conditions of LCO 4.8.3, a greater than 10 gpm release from the reactor building sump was begun.

LCO 4.8.3 allows for releases from the reactor building sump at greater than 10 gpm flow rates provided the following conditions are satisfied:

1.

Two grab samples are taken and analyzed for gamma activity prior to the release.

2.

Two activity monitors and recorder are operating and equipment is oper-able to automatically terminate the release on high specific activity or low circulating water blowdown.

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3.

During the release, the pump discharge must be proportionally sampled.

At 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br /> on March 10, 1981, it was discovered the proportional sampler was not sceiving a sample and the release was terminated.

The in-service activity monitors and recorder did not indicate any increase in activity during the release.

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REPORTABLE OCCURRENCE 81-023 ISSUE O Page 2 of 3

CAUSE

DESCRIPTION:

The cause for the proportional sampler not receiving a sample was that 'the.

solenoid valves on the reactor building sump. effluent discharge were not open. These valves are energized to open from the starting circuit of the reactor building sump pumps, allowing a sample of the affluent discharge to be continuously collected in a. sag le drum during a release.

When the temporary sump pump was installed, the need to provide.an ener-gizing signal to the solenoid valves was overlooked, resulting in propor-tional sampling isolation during the release.

. CORRECTIVE ACTION:

Upon' discovery of the inoperable proportional sampler, the release was' im-mediately terminated.

Instructions have been issued and status tags hung to insure the propor-tional sagler is operable when.using the ter/orary sump puty.

- Personnel issuing temporary changes will be instructed to insure all as-

. pects of the temporary change have been reviewed.

No further corrective action is anticipated or required.-

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REPORTABLE OCCURRENCE 81-023 l

ISSUE O Page 3 of 3 Prepared By:

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I Paul Moore Technical Services Technician Reviewed By:

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- W. Gahm ec.aical Services Supervisor Reviewed By:

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Frank M. Mathie 9

Operations Manager Approved By:

Mu Don Warembourg

,g Manager, Nuclear Production l

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