ML19305C058

Forwards LER 80-006/03L-0

ML19305C058
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/19/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19305C059	List: ML19305C058 ML19305C061
References
P-80057, NUDOCS 8003250535
Download: ML19305C058 (4)

Text

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,; puhue service company ce ceaende y .

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

.farch 19,1980 Fort St. Vrain Unic No. 1 P-80057 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 coiy of Reportable Occurrence Report No. 50-267/

80-06, Final, submitted per the requirements of Technical Specification AC 7. 5. 2 (b) 3.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/80-06.

Very truly yours, Do ar

• Manager, Nuclear Production DW/cla Enclosure cc: Director, MIPC d)g' 9 q 8 0 0 3 P_50 53 s

REPORT DATE: March 19,1980 REPORTABLE OCCURRENCE 80-06 ISSUE O OCCURRENCE DATE: Februarv 18, 1980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE C0ffANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/ 80-06/03-L-0 FINAL IDENTIFICATION OF OCCURRENCE:

On February 18, 1980, with the reactor plant critical at less than 2% power, it was determined that a hydraulic snubber required by Fort St. Vrain Technical Specification LCO 4.3.10 was inoperable.

This is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)3.

EVENT DESCRIPTION:

During the early part of February while the reactor was in a shutdown con-dicion, vent stack snubber, VSS-117, was removed for repair. The snubber was out of service during the subsequent reactor start up on February 17, 1980, and resulted in a degraded mode of LCO 4.3.10. The plant operating personnel were informed of the impaired snubber on February 18, 1980, at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> and took the reactor suberitical at that time. The replacement snubber was installed, and the reactor was taken critical again for oper-ator training at 1450 that day.

CAUSE DESCRIPTION:

The approved procedure for removal of hydraulic snubbers requires that the Shif t Supervisor be notified when a snubber is being removed for repairs.

This information is recorded in an igairment log that is checked regularly by the Shift Supervisor.

There is no record of the maintenance personnel informing the Shif t Supervisor that this anubb9i' w s being removed from service; therefore, when the impair-t ent Iog was crackcd prior to the startup on February 17, 1980, there was no record of vent stack snubber, VSS-ll7, being out of service. The re-actor was started up, putting the plant in a degraded mode of LCO 4.3.10.

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REPORTABLE OCCURRENCE 80-06 ISSUE O Page 2 of 3 CORRECTIVE ACTION:

Replacement snubber was installed.

Maintenance personnel involved with the snubber repair were reprimanded and the igortance of following approved procedures emphasized.

A change request has been submitted to the commission which would modify LCO 4.3.10 and its basis to require snubber operability only during power operation of the reactor, which is consistent with other Technical Speci-fications. This was proposed on May 9,1978, in P-letter P-78062, and af ter almost two years we still have not received relief from this Techni-cal Specification.

There was no affect on public health or safety. No further corrective action is anticipated or required.

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REPORTABLE OCCURRENCE 80-06 ISSUE O Page 3 of 3 l

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i Prepared By: ,dd, /

Asa B. Reed Technical Service Technician Reviewed By: .

. V Gahm echnical Services Supervisor Reviewed By:

Frank M. Mathie Operations Manager Approved By: 2b ff m* h_

Don Warembourg Manager, Nuclear Production l

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