05000267/LER-1981-062, Forwards LER 81-062/03L-0.Detailed Event Analysis Encl

Forwards LER 81-062/03L-0.Detailed Event Analysis Encl

ML20032E969
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/13/1981
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20032E970	List: 05000267/LER-1981-062, Forwards LER 81-062/03L-0.Detailed Event Analysis Encl
References
P-81286, NUDOCS 8111230557
Download: ML20032E969 (6)

LER-1981-062, Forwards LER 81-062/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671981062R00 - NRC Website

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public Service Company *f Coblade VW 16805 Road 19 1/2, Platteville, Colorado 80651-9298 November 13, 1981 Fort St. Vrain Unit No. 1 P-81286

• M@MO\\V/F ls f"!i Mr. Karl V. Seyfrit, Director l (

D l 6 l981 lD*

Nuclear Regulatory Commission

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I' Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive

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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. 50-267/81-062, 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. 50-267/81-062.

Very truly yours, A'.

WLttn&

Don Warembourg

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Manage'r, Nuclear Production DW/cis Enclosure 4

1 cc: Director, MIPC 2

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OCCURRENCE REPORT DISTRIBUTION Number of Copies t

l Department of Energy - - - - - - - - - - - - - - - - - - - - * - - - - - - - - -

1 (P Letter)

San Francisco Operations Office Attn California Patent Group

'1333 Broadway Oakland, California '94612 Department of Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)'

Mr. Glen A. Newby, Chief HTR Branch Division of Nuclear Power Developannt Mail Station B-107 Washington. D.C.

20545 De pa r tme nt o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Attnt Project Manager 110 Vest A Street. Suite 460 San Diego, California 92*^1 Mr. Karl V. Seyfrit Director 1

(Original of P Letter Region IV Office of Inspection and Enforcement and Copy of LER)

Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Dfrector - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter, LER)

Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C.

20555-Mr. Ri cha rd ihe lps -

T- - - -. - ~- - - - - - - - - - - - - - - - - - - - - - 10 (0riginal of PFLC IAtter

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FSV, CA, Site plus Two Copies, One Representative Copy of P Letter. One General Atomic Cogany Copy of LER)

P. O. Box 425 Platteville, Colorado 80651 M r. B i ll Imva lee - - - - - - - - - - -.. - - - - - - - - - - - - - - - - - -

1 (P Letter, LER)

Nuclear Safety Analysis Center 3412 Hillview Avenue P. O. Box 10412 Palo Alto, California 94303 NRC Resident Site Inspector 1

(P Letter, LER)

' b1 REPORT DATE:

November 13, 1981 REPORTABLE'0CCURRENCE 81-062 ISSUE 0 OCCURRENCE DATE:

October 14, 1981 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT N0. 50-267/81-062/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On three separate occasions, during the period from October 14, 1981, to October 19, 1981, the prestressed concrete reactor vessel cooling water system temperatures exceeded the allowable limits. This is a degraded mode of the LCD 4.2.15 and is reportable per Fort St.

Vrain Technical Specification AC 7.5.2(b)2.

EVENT

- DESCRIPTION:

On October 14, 1981, during a planned power reduction for maintenance, the prestressed concrete reactor vessel (PCRV) cooling l

water Loop 2 temperature controller failed.

The Operations personnel j

discovered the problem and returned system operation and temperature to normal by means of an auxiliary bypass controller. Tne Loop 2 cooling water outlet temperature exceeded the 120 degrees fahrenheit limit of LC0 4.2.15 during this event.

The instrument department examined the controller, adjusted the input bridge amplifier, tested the controller, and returned it to service.

The same problem occurred again on October 16, 1981, and Operations personnel again utilized a bypass controller to return the system to l

normal temperature and operation.

The Loop 2 cooling water outlet temperature again exceeded the LCO limit of 120 degrees fahrenheit.

The instrument department inspected the controller, replaced the input bridge amplifier, calibrated the controller, and returned it to service.

On October 19, 1981, the temperature controller failed again with the cooling water temperature decreasing in Loop 2 until the average of the inlet and outlet was less than the 100 degrees fahrenheit required by-LC0 4.2.15.

The operations personnel restored system operations and temperature to' normal with a bypass controller.

The instrument department inspected the controller and found a bad solder

- foint under the auto-manual relay.

The connection was resoldered, and the controller tested and returned to service.

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r REPORTABLE OCCURRENCE 81-062 ISSUE O Page 2 of 3

CAUSE

DESCRIPTION:

- The_ temperature controller failure in all three cases was caused by a bad solder joint uride'r' the auto-manual relay.

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CORRECTIVE ACTION:

Th! cooling water temperature was returned to acceptable values, and the bad solder joint was resoldered.

No further corrective action is anticipated or required.

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- l REPORTABLE OCCURRENCE 81-062 ISSUE 0 Page 3 of 3 M

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Prepared By:

Asa B. Reed Technical-Services Technician Reviewed By: bal da Charles Fuller Technical Services Engineering Supervisor Reviewed By:

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Edwim Df Hill Station Manager Approved By:

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[Auwb Don Warembourg

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Manager, Nuclear Production

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