ML19323A512

Forwards LER 80-017/03L-0

ML19323A512
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/09/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19323A513	List: ML19323A512 ML19323A516
References
P-80076, NUDOCS 8004210294
Download: ML19323A512 (3)

Text

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t# public Service Company 2 Cellensflo 16805 Weld County Road 191/2, Platteville, Colorado 80651 April 9,1980 Fort St. Vrain Unit No. 1 P-80076 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Conunission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive .

i 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/

80-17, 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. 50-267/80-17.

Very truly yours, Don Waretiourg Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC i

Doo)

S lll 3004210$99

REPORT DATE: April 9,1980 REPORTABLE OCCURRENCE 80-17 ISSUE O OCCURRENCE DATE: March 11, 1980 Page 1 of 2  ;

FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-17/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On March 11, 1980, with the plant shutdown, a sample required by SR NR 1.1 was not taken. This is being reported as a degraded mode of SR NR 1.1 per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

On March :.1,1980, with the plant at approximately 36% thermal power and 90 Mi electric power, a plant upset occurred due to a rupture of a main cooling water return line to the main cooling water tower. This upset resulted in a main turbine generator trip, a manual reactor scram, and the loss of the main condenser. The decay heat exchanger was used for decay heat removal, and primary and secondary coolant flows were maintained throughout the upset.

During this upset and the plant recovery that followed, one of the plant effluent samples required by SR NR 1.1 was not taken. The samples before and after the missed sample were normal, and during the plant upset, the cooling tower blowdown was shut off.

CAUSE DESCRIPTION:

The sample was not taken because abnormal plant conditions preempted the operators time.

CORRECTIVE ACTION:

The sample was taken the next shift as required, and the surveillance form was marked to indicate why the missing sample was not taken.

There was no affect on public health or safety.

Jo further corrective action is anticipated or required.

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REPORTABLE OCCURRENCE 80-17 ISSUE O Page 2 of 2 1 4 Prepared By: itA f /, /

• Asa B. Reed t Technical Services Technician Reviewed By: [ .,,, "  ;

J .' W. Cahm

'Tlechnical Services Supervisor t/  ;

Reviewed By:

Frank M. Mathie Operations Manager Approved By: A M ,f _

Don Waren6ourg g Manager, Nuclear Production l