05000267/LER-1981-020, Forwards LER 81-020/03L-0.Detailed Event Analysis Encl

Forwards LER 81-020/03L-0.Detailed Event Analysis Encl

ML20008F679
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/27/1981
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20008F680	List: 05000267/LER-1981-020, Forwards LER 81-020/03L-0.Detailed Event Analysis Encl 05000267/LER-1981-020-03, /03L-0:on 810226,primary Coolant Moisture & Oxidants Exceeded Limits.Caused by Circulator Buffer Sys Upset & Helium Circulator Trip Due to 810223 Reactor Scram. Reactor Power Reduced Until Moisture Level Decreased
References
P-81103, NUDOCS 8104210494
Download: ML20008F679 (5)

LER-1981-020, Forwards LER 81-020/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671981020R00 - NRC Website

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PLATTEV1LLE, COLORADO 80651 March 27, 1981 Fort St. Vrain Unit No. 1

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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/

81-020, 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 i

Reportable Occurrence Report No. 50-267/81-020.

Very truly yours, t -,a fi f Don Warefnbourg

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REPORT DATE:

March 27, 1981 REPORTA3LE OCCURRENCE 81-020 ISSUE O OCCURRENCE DATE:

February 26, 1981 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY RCAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/81-020/03-L-0 Final ICENTIFICATION OF OCCURRENCE:

On February 26,1981, from 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> to 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, the plant was operated in a degraded mode of LCO 4.2.10 and LCO 4.2.11.

These events are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

See Figure 1.

On February 25, 1981, reactor power was increased to 60:

thermal with core average outlet temperature greater than 1200*F. See Area A of Figure 1.

Following the increase in power, total prinary coolant oxidants, the conbination of CO, C0, and moisture, started to increase and 3

exceeded the LCO 4.2.10 limit of 10'ppn. Reactor power was reduced, lowering the core average outlet ce=perature to less than 1200*F and restoring con-pliance with LCO 4.2.10.

See Figure 1, Area 3.

Due to the moisture present in the primary coolant, the reduction of core average outlet temperature below 1200*F resulced in exceeding the dewpoint limit of LCO 4.2.11, Figure 4.2.11-1.

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CAUSE

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DESCRIPTION

Cause of the increased moisture is being attributed to a reactor seras on February 23, 1981, and the resultant circulator buffer system upset which caused moisture ingress.

CORRECTIVE ACTION:

The reactor pewer level was reduced to about *0T thermal and remained thera encil primary coolant moisture and oxidants had decreased to acceptable limits.

No further corrective action is anticipated or required for the events de-scribed in this report.

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REPORTABLE OCCUFJtENCE 81-020 ISSUE O Page 3 of 3 Prepared By:

8 Asa B. Reed Technical Services Technician Reviewed By:

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