05000267/LER-1982-046, Forwards LER 82-046/03L-0.Detailed Event Analysis Encl

Forwards LER 82-046/03L-0.Detailed Event Analysis Encl

ML20064J306
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/29/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20064J309	List: 05000267/LER-1982-046, Forwards LER 82-046/03L-0.Detailed Event Analysis Encl 05000267/LER-1982-046-03, /03L-0:on 821130,analytical Sys Moisture Monitors ME-9306 & ME-9307 Taken Out of Svc.Caused by High Moisture Levels in Primary Coolant Resulting in Water Condensation within Sample Lines.Lines Purged
References
P-82559, NUDOCS 8301180001
Download: ML20064J306 (5)

LER-1982-046, Forwards LER 82-046/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671982046R00 - NRC Website

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16805 Road 19 1/2, Platteville, Colorado 80651-9298 December 29, 1982 Fort St. Vrain Unit No. 1 P-82559 Mr. John T. Collins, Regional Administrator Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Reference:

Facility Operating License No. OPR-34 Docket No. 50-267

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/82-046, 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. 50-267/82-046.

Very truly yours, IhtS[ Q Don darembourg Manager, Nuclear Production D',l/c 1 s Enclosure cc:

Director, MIPC 0s

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8301100001 g23p79 gDRADOCK 05000267 r

PDR

REPORTABLE OCCURRENG DISTRIBUTION Number of Copies De p a r t men t o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

San Francisco Operations Of fice Attn: California Patent Crong 1333 Broadway Oakland, California 94612 De p a r t me n t o f En e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Mr. Glen A. Newby, Chie f HTR Branch Division of Nuclear Power Development Mail Station B-107 Washin gton, D.C.

20545 De p a r t men t o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Attn Project Manager P. O. Box 81608 San Diego, California 92138 1 (Original of P latter)

!!r. John T. Collins, Regional Administrator Region IV Nuclear Regulatory Coramission 611 Ryan Plaza Drive S uite 1000 Arlington, Texas 76011 f t r. Ge o r g e K uz my c z - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P latter)

Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20034 D i re c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Latter)

Of fice of Managenwnt Information and Program Control Nuclear Regulatory Commission Washington, D. C.

20555 1 (P Letter)

INPO Recorda Center Suite 1500 1100 Circle 75 Parkway I

Atlanta, G4 30339 i

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1 Mr. Richard Phelps, PSV, CA, S i te Rep re sen tati ve - - - - - - - - - - - - - - - -

1 (P Letter)

Ceneral Atomic Cocpany 1

16664 Weld County Road 191/2 Platteville, Colorado 80651 1 (P Letter)

SRC Resident Site Inspector 1

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i REPORT DATE:

December 29, 1982 REPORTABLE OCCURRENCE 82-046 ISSUE O OCCURRENCE DATE:

November 30, 1982 Page 1 of 3 i

FORT ST. VRAIN NUCLEAR GENERATING STATION

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PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/82-046/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On two occasions on November 30, 1982, with the reactor operating at less than 1% thermal power, two analytical system moisture monitors, ME-9306 and ME-9307, were taken out of service, leaving only one operable monitor in service. This is reportable as a degraded mode of LCO 4.4.5 per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

Entrapped moisture in the primary coolant sample lines to ME-9306 and ME-9307 was suspected of causing erroneous reactor dewpoint temperature indications.

The monitors were taken out of service on two occasions for purposes of purging the moisture from these lines.

Event No. 1:

On November 30, 1982, from approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> until 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, moisture monit< s ME-9306 and ME-9307 were simultaneously taken out l

of service f-a period of two hours. During this time, moisture monitor ME-930 was placed in service to indicate prima ry coolant moisture.

1 Event No. 2:

On November 30, 1982, from approximately 1700 hcurs until 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on December 1, 1982, moisture monitors ME-9306 and ME-9307 were again taken out of service for an 11 1/2 hour period. During this time, moisture monitor ME-9305 was placed in service to indicate primary coolant moisture.

1, The moisture monitors, ME-9306 and ME-9307, were returned to service within the allowable 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period of LCO 4.4.5 in buth events.

CAUSE

DESCRIPTION:

High moisture levels in the primary coolant resulted in water condensation within the primary coolant sample lines to ME-9306 and i

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s REPORTABLE OCCURRENCE 82-046 ISSUE O l

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ME-9307.

This situation was suspected of causing erroneous reactor 4

dewpoint temperature indications and therefore, made it necessary to i

remove the monitors from service and purge the water from the lines.

CORRECTIVE ACTION:

l Temporary Configuration Report, TCR 82-112, was issued to direct a high flow rate helium purge through the primary coolant sample lines to ME-9306 and ME-9307 in both events. To ensure an unobstructed flow path through the moisture monitors, temporary connections were l

made from the high pressure helium supply tanks to the primary coolant sample lines.

Following the helium purge, the primary coolant sample lines were reconnected, and flow was re-established through the moisture monitors.

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No further corrective action is anticipated or required.

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REPORTABLE OCCURRENCE 82-046 ISSUE O Page 3 of 3

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Prepared By:

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Tocert A. Dickerson Senior Technical Services Technician Reviewed By:

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Charles Fuller ~

Technical Services Engineering Supervisor l

'b'[NO Reviewed By:

Edwin D. Hill Station Manager Approved By:

f iS[ be Do'n Wremcourg Manager, Nuclear Production