ML20010H925

Forwards LER 81-049/03L-0.Detailed Event Analysis Encl

ML20010H925
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/01/1981
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20010H926	List: ML20010H925 ML20010H930
References
P-81216, NUDOCS 8109290418
Download: ML20010H925 (7)

Text

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., .t Public Servlee Company & CcHendo September 1, 1981 Fort St. Vrain Unit No. 1 P-81216 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission

> Region IV

! Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 i

Reference:

Facility Operating License No. OPR-34

! Docket No. 50-267

Dear Mr. Seyfrit:

Enclosed please find a copy of keportable Occurrence Report No. 50-267/81-049, Final, submitted per the requirements of Technical i Specification AC 7.5.2(b)2.

1 Ai ,, please find enclosed one copy of the Licensee Event Report for i Reportable Occurrence Report No. 50-267/81-049.

Very truly yours, i

/w WM Don Warembcurg 3 Manager, Nuclear Droduction DW/cis f r \j F t i + %

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Enclosure cc: Director, MIPC 8Eg b)h Sd[%g[g'$[k rpa

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5 8109290418 810901 PDR ADOCK 05000267 r S PDR: } 5 c2 N

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OCCURRENCE REPORT DISTRIBUTION Nutnber of Copies 1 (P Letter)

Department of Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - -

San Francisco Operations Office Atta: California Patent Group 1333 Broadway .

Oakland, California 94612

--- - ---------- 1 (P Letter)

Departmen t o f Ene rgY - - - - - - - - - - -

Ifr. Glen A. Newby, Chief HTR Branch Division of Nuclear Power Development

? tail Station B-107 Washington, D.C. 20545 1 (P Letter)

De par tment o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Atta: Project Manager 110 West A Street, Suite 460 San Diego, California 92101

---

----------- ----- h (Original of P I.etter Mr. Karl V. Seyfrit. Director and Copy of LER)

Region IV -

Of fice of Inspection and Enforcement Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 1 (P Letter, LER)

Director - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Of fice of Management Inforr.ation and Program Control U. S. Nuclear Regulatory Cotmnission Washington, D.C. 20555 10 (Original of [PiU LetteI Mr . R i ch a rd Phe lp s - 4 '- - - - - - - - - - - - - - - - - - - - - - - - -

plus Two Copies, One FSV, GA, Site Copy of P Letter One Representative Copy of LER)

General Atomic Company P. O. Box 426 Platteville, Colorado 80651 1 (P Letter, LER)

Mr . B ill Lava lee - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Nuclear Safety Analysis Center 3412 Hillview Avenue P. O. Box 10412 Palo Alto, California 94303 (P Letter, LER)

NRC Resident Site Inspector -- - ------- ----------- - 1

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REPORT DATE: Seotember 1.1981 REPORTABLE OCCURRENCE 81-049 ISSUE O OCCURRENCE DATE: Auoust 2, 1981 Page 1 of 5 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/81-049/03-L-0 Final 4

IDENTIFICATION OF OCCURRENCE:

During the period from August 2, 1981, to August 7, 1981, the plant was operated in a degraded mode of' LCO 4.2.10 on three occasions.

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

EVENT DESCRIPTION:

Event 1 See Figure 1. At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on August 2, 1981, with the average core outlet temoerature greater than 1200 degrees fahrenheit, the total prir ilant oxidants (the sum of carbon monoxide, carbon dioxide, and increased above 10 ppm. Operation continued under these This event cono.t ions until 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on August 2, 1981.

ccnstitutes operation in a degraded mode of LCO 4.2.10.

Event 2 See Figure 1. At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on August 2, 1981, with average core outlet temperature greater than 1200 degrees fahrenheit, the total primary coolant oxidants increased above 10 ppm. Operation continued This under these conditions until 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on August 7, 1981.

event constitutes operation in a cegraded mode of LCO 4.2.10.

Event 3 See Figure 1. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on August 7, 1981, with average core outlet temperature greater than 1200 degrees fahrenheit, the total primary coolant oxidants increased above 10 ppm. Operation continued under these conditions' until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on August 7, 1981. This event constitutes operation in a degraded mode of LCO 4.2.10.

REFORTABLE OCCURRENCE 81-049 ISSUE O Page 2 of 5 CAUSE DESCRIPTION:

Event 1 See Figure 1. At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on August 2,1981, reactor power was -

increased from 32.9% power to 41% power with a corresponding increase in core outlet temperature from 1105 degrees fahrenheit to 1203 degrees fahrenheit. This was the first time core outlet .

temperature had been increased above 1200 degrees f0hrenheit since the refueling shutdown. Total primi.ry coolant oxidants increased to 10.1 ppm at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> then decreased to less than 10 ppm by 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

Event 2 ,

See Figure 1. At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on August 2,1981, reactor power had slowly been increased to 46% with core cutlet temperature increasing to 1215 degrees fahrenheit. Primary coolant oxidants increased to 11.5 opm due to the residual moisture in the core from tne refueling shutdown. Power was increased to 53% by August 5, 1981, with several spikes in total oxidants' levels as the core continuad to out gas.

Power was reduced at 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> to approximately 46% due to turbine vibrations, then subsequently raised to 70%. Primary coolant axidants increased as power was increased t; a maximum of 19.5 ppm, then began a downward trend, and at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on August 7, 1981, decreased to less than 10 ppm.

Event 3 See Figure 1. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on August 7, 1981, a small increase in carbon dioxide and carbon monoxide levels due to out gassing caused total primary coolant oxidants to increase to 10.4 ppm. By 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, pr'eary coolant oxidant levels had decreased to less than 10 ppm.

CORRECTIVE ACTION:

Corrective actions to the degraded mode operations outlined in this occurrence are as follows:

Egent 1 Total primary coolant oxidant levels promptly decreased below 10 ppm, thus ro cc rective action was necessary. l Event 2 The primary coolant purification system was utilized to remeve the primary coolant oxidants and thereby bringing them below tae LCO limit of 10 ppm.

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REPORTABLE OCCURRENCE 81-049 ISSUE O Page 3 of 5 Event 3 Total primary coolant oxidant tevels promptly dropped below 10 ppm, thus no corrective action was necessary. .

No further corrective action is anticipated or required.

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REPORTABLE OCCURRENCE 81-049 ISSUE O Page' 5 of 5 e

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Prepared By:

Fauf Moore Mh  %/

Technical Services Technician i

Reviewed Sy: WN Me,4 *Ja Milt McBride' Technical Services Manager f.

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