ML20054H316

Forwards LER 82-019/03L-0.Detailed Event Analysis Encl

ML20054H316
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/16/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20054H317	List: 05000267/LER-1982-019, Forwards LER 82-019/03L-0.Detailed Event Analysis Encl
References
P-82195, NUDOCS 8206230232
Download: ML20054H316 (4)

Text

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Y public Servlee Company Cf Odondo

• 16805 Road 19 1/2, Platteville, Colorado 80651-9298 M M @lNIf Ijfb June 16, 1982

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\l JUN '/ ! lm? Fort St. Vrain

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' \ g'-- Unit No. 1 P-82195 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. DPR-34 Docket No. 50-267

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/82-019, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)1 and AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/82-019.

Very truly yours, WWW Don Warembourg Manager, Nuclear Pro uction DW/cls  ;

Enclosure ,

cc: Director, MIPC e't  ;

B206230232 820616 PDR ADOCK 05000267 i S PDR 1 1

REPORT DATE: June 16. 1982 REPORTABLE OCCURRENCE 82-019 Determinec ISSUE O OCCURRENCE DATE: May 18, 1982 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY RCAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/82-019/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During routine surveillance testing of the helium circulator speed trips, two of the circulator 1A (C-2101) feedwater flow low trip switches and one of the circulator 1A (C-2101) programmed low speed switches were out of calibration. This resulted in operation with instrument setpoints less conservative than those established by Technical Specification LCO 4.4.1, Table 4.4.3 and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)1 and AC 7.5.2(b)2.

EVENT DESCRIPTION:

I On May 5, 1982, with the reactor at 5% thermal power, while performing the monthly surveillance on circulator speed /feedwater flow trips, one of three channels for 1A circulator programmed low speed trip was found out of tolerance. The circulator low speed trip programmed with feedwater flow is to prevent operation with a feedwater flow greater than the heat removal capability which could result in flooding of the superheater section of a steam generator.

If circulator speed is lower than normal for a given feedwater flow, a trip is produced. Although the trip setpoint for the one channel was found less conservative than required by the Technical Specifications, the functional capability of the channel would not have been prevented. The two remaining channels for the 1A circulator programmed low speed trip remained operable.

As part of the same surveillance conducted on May 5, one of three channels for programmed feedwater flow low and one of three channels for the fixed feedwater flow trips for 1A circulator were found out

. of tolerance. Both of these circulator trips are to prevent excessive steam generator superheater temperatures. The functional capabilities of these channels would not have Oeen prevented by the less conservative setpoints, and the remaining two channels for each trip were not affected.

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i-j REPORTABLE CCCURRENCE 82-019 j ISSUE O Page 2 of 3 CAUSE DESCRIPTION:

The cause for the setpoint verification in all three instances was instrument calibration drift.

1 CORRECTIVE j ACTION:

The circulator 1A (C-2101) programmed low speed switch and the two feedwater flow low switches were recalibrated, and the surveillance I was successfully completed.

No further corrective action is anticipated or required.

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REPORTABLE OCCURRENCE 82-019 ISSUE O Page 3 of 3 Prepared By: Md he Robert A. Dickerson Technical Services Technician

( O Reviewed By: C  % V , W &

ChaYleffuTer  ;

Technical Services, n neering Supervisor

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Reviewed By: //

Edwid.,0 V' H fT T Station Manager Approved By: t u_2t M Don Warembourg g7 Manager, Nuclear Produc-ion

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