05000409/LER-1982-019, Forwards LER 82-019/03L-0.Detailed Event Analysis Submitted

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

ML20028C699
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/29/1982
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20028C700	List: 05000409/LER-1982-019, Forwards LER 82-019/03L-0.Detailed Event Analysis Submitted 05000409/LER-1982-019-03, /03L-0:on 820927,during Power Escalation Following Refueling Outage,Water Level Safety Channel 3 Determined Nonconservative W/Respect to Possible Low Water Level Condition.Caused by Transmitter Drift.Channel Adjusted
References
LAC-8767, NUDOCS 8301140007
Download: ML20028C699 (2)

LER-1982-019, Forwards LER 82-019/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
4091982019R00 - NRC Website

text

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.ct, D DA/RYLAND 8

COOPERAfNE

• PO BOX 817 2615 EAST AV SOUTH

• LA CROSSE. WISCONSIN 54601

<608) 788-4000 December 29, 1982 In reply, please refer to LAC-8767

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DOCKET NO. 50-409 Mr. James G. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 SUBJECT: DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE N0. DPR-45 REPORTA3LE OCCURRENCE NO. 82-19

REFERENCES:

(1) DPC Letter, Linder to Keppler, LAC-8675, dated October 27, 1982

Dear Mr. Keppler:

Reference 1 reported an incident in which reactor protection system instruments were found to be operating nonconservatively, but which did not prevent the fulfillment of the required protective function of the affected system. Further investigation has determined that information contained in that submittal was inaccurate, so please disregard it. This letter will describe the circumstances of the incident and corrective action taken.

During power escalation following the 1982 refueling outage which concluded on f,.tember 27, 1982, it was noticed that Water Level Safety Channel 3 and the narrow range water level recorder were indicating approximately five inches above Water Level Safety Channels 1 and 2.

During an unplanned reactor shutdown on October 12, the water level channels were investigated.

Water Level Channels 1 and 2 were calibrated and found to be satisfactory.

Channel 3 was adjusted. Following reactor startup, Water Level Channels 1, 2, and 3 indicated approximately the same. The recorder indicated approximately three inches higher.

While Water Level Channel 3 was indicating higher than actual water level, it was performing nonconservatively with respect to a low water level transient, since a low water level scram would have occurred at about sixteen inches below normal water level, rather than the Technical Specification limit of -12 inches. Water Level Channels 1 and 2 would have tripped the reactor prior to water level falling below -12 inches. No water level transient occurred during the time period the channel was out of calibration.

8301140007 821229 JAN 71983 PDR ADOCK 05000409 S

PDR WP-6 $Nb.

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8' : Mr. James G. Keppler, Director D:cemb2r 29, 1982.

U. JS. Nuclear Regulatory Commission LAC-8767' The instrument accuracy of-the water. level. channels is approximately + 2.5-inches. The water level channels will be monitored for-further signs of -

unacceptable drifting. - A calibration test on Channel 3 performed on December 16,:1982 was acceptable.

A'LicenseeEventReport.(Reference: Regulatory Guide 1.16, Revision' 4) is enclosed.

- If'there any questions, please contact'us.

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Yours truly,

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DAIRYLAND POWER C00PE ATIVE N

" Frank Linder, General anager FL:LSG:eme Enclosure cc: Document Control Desk INP0 NRC Resident Inspector l

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