05000255/LER-1990-001, :on 900109,reactor Manually Tripped Following Loss of All Main Feedwater Flow When Main Feedwater Pump a Tripped.Possibly Caused by burned-out Solenoid in Dump Valve.Governor Oil Pressure Will Be Monitored

:on 900109,reactor Manually Tripped Following Loss of All Main Feedwater Flow When Main Feedwater Pump a Tripped.Possibly Caused by burned-out Solenoid in Dump Valve.Governor Oil Pressure Will Be Monitored

ML18054B434
Person / Time
Site:	Palisades
Issue date:	02/08/1990
From:	Johnson B, Kozup C CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-001, LER-90-1, NUDOCS 9002230093
Download: ML18054B434 (4)

LER-1990-001, on 900109,reactor Manually Tripped Following Loss of All Main Feedwater Flow When Main Feedwater Pump a Tripped.Possibly Caused by burned-out Solenoid in Dump Valve.Governor Oil Pressure Will Be Monitored

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
2551990001R00 - NRC Website

text

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• consumers Power POWERINli NllCHlliAN'S PROliRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 February 8, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

LICENSEE EVENT REPORT 90-001 - MANUAL REACTOR TRIP FOLLOWING TRIP OF MAIN FEEDWATER PUMP Licensee Event Report (LER)90-001 (Manual Reactor Trip Following Trip of Main Feedwater Pump) is attached.

This event is reportable to the NRC per 10CFR50.73(a)(2)(iv).

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment 9002230093 900?og PDR ADOCR b~650~55 S

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1...:11 Abstract On January 9, 1990 at 0514 with power at a steady state of 35 percent, the reactor was manually tripped following the loss of all main feedwater flow.

main feedwater was lost at 0512 when "A" main feedwater pump was secured as part of the normal power reduction procedure for preparation for condenser [SG;COND]* tube leak identification and repair.

The Plant response to the trip was considered normal with no safety significant deviations or anomalies observed.

The root cause of the event has not yet been conclusively determined.

Troubleshooting is ongoing.

A supplemental Licensee Event Report will be submitted pending the results of the investigation.

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Description

On January 9, 1990 at 0514, with power at a steady state of 35 percent, the reactor was manually tripped following the loss of all main feedwater flow.

Main feedwater was lost at 0512 when "A" main feedwater pump rsJ;P] tripped.

At the time of the event, "B" main feedwater pump was secured as part of the normal power reduction procedure for the preparation for condenser [SG;COND] tube leak identification and repair.

The Plant response to the trip was considered normal with no safety significant deviations or anomalies observed.

The "A" auxiliary feedwater pump, [BA;P] was manually started because steam generator level remained above the auxiliary feedwater actuation system auto start setpoint.

Equipment deficiencies observed after the trip included a loss of condenser vacuum after the Plant trip.

This was caused when moisture separator and reheater relief valves failed to properly reseat.

Condenser vacuum was restored by actions which reseated the relief valves.*

Cause Of The Event

The root cause of the main feedwater pump trip has not been conclusively determined.

Troubleshooting prior to restart included a complete hydraulic and electric checkout of the feedwater pump control system.

This checkout found a burned-out solenoid in the feedwater pump control oil dump valve.

It was inconclusive whether this solenoid failure occurred prior to the trip, or as a result of the trip.

The failure of this solenoid would maintain the oil control valve in a closed position which is its normal operating.condition.

Therefore, the failure of the solenoid was not the root cause of the trip.

Electrical schematics were reviewed to determine all potential feedwater pump trip paths.

Two trip paths, low suction pressure and thrust bearing failure, were possible. It was determined from the datalogger that the pump did not trip from low suction pressure.

In addition, the thrust bearing trip device has a seal-in feature and it was determined that this feature was not seal-in.

To provide information for further troubleshooting; a pair of strip recorders have been installed on the "A" main feed pump to monitor the governor oil pressure and the lube oil pressure.

We will continue to monitor these par_ameters and a supplemental report will be submitted pending the results of this investigation.

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Analysis Of The Event

Plant response to the reactor trip was as expected with no safety significant deviations or abnormalities observed.

Both trains of safety equipment were available throughout the transient to perform their safety functions.

Corrective Actions Taken The trip of "A" main feedwater pump is still being investigated.

In the interim we will continue to monitor governor oil pressure and lube oil pressure; Frequent walkdowns of the system are taking place.

Regarding the moisture separator and reheater relief valves, we are in the process of evaluating their possible future replacement.

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