05000346/LER-1980-080-03, /03L-0:on 801103,during Testing,Control Rod Drive Trip Breaker C Did Not Trip.Cause Could Not Be Determined. Breaker Was Manually Put in Tripped Position within 5 Minutes of Failure

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/03L-0:on 801103,during Testing,Control Rod Drive Trip Breaker C Did Not Trip.Cause Could Not Be Determined. Breaker Was Manually Put in Tripped Position within 5 Minutes of Failure
ML20002B048
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/02/1980
From: Rudolph J
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20002B042 List:
References
LER-80-080-03L, LER-80-80-3L, NUDOCS 8012090387
Download: ML20002B048 (2)


LER-1980-080, /03L-0:on 801103,during Testing,Control Rod Drive Trip Breaker C Did Not Trip.Cause Could Not Be Determined. Breaker Was Manually Put in Tripped Position within 5 Minutes of Failure
Event date:
Report date:
3461980080R03 - NRC Website

text

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EVENT DESCRIPTIO'3 AND PROBABLE CONSEQUENCES 1 ; i 21 l (NP-33-80-100) On 11/3/80 at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> while performing testing, the control rod driv 4 p:!3l l trip breaker "C" did not trip. This failure put the station in Action Statement 7 of l [o14ll Technical Specification 3.3.1.1.

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31 40 41 42 43 44 47 JJ CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i : l o l lThe cause for the breaker failure has not been determined. During troubleshooting l

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419-259-5000, Ext. 251 Ja.es Rudolph PHONE:

DVR 80-185 NAME Of PREPAHEIl f.

TOLEDO EDISON COMPANY DAVIS-BESSE NbCLEAR POWER STATION UNIT ONE

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SUPPLEMENTAL INFORMATION FOR LER NP-33-80-100 DATE OF EVENT: November 3, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Control rod drive trip breaker "C" failed to open The unit was in Mode 2 with Power (MWT) = 0 and Conditions Prior to Occurrence:

Load (Gross.WE) = 0.

Description of Occurrence: On November 3. 1980 at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> during the performance the control of PT 5155.02, Anticipatory Reactor Trip Jystem Monthly Functional Test, rod drive trip breaker "C" did not trip.

the station in Action Statement 7 of Technical Specification 3.3.1.1.

This failure put This technical specification requires that the reactor protection system (RPS) be available with four control rod drive trip breakers operable. The action statement requiras that the inoperable channel be placed in the tripped condition within one hour; or remove the power supplied to the control rod trip device associated with the inoperative channel. The breaker was manually placed in the tripped position within five minutes of the failure.

Designation of Apparent Cause of Occurrence: The apparent cause for the breaker failure has not been determined. Extensive investigation found no apparent problems with the breaker. During troubleshooting, the breaker was manually and electrically cycled in A General Electric field all positions several times and no problems could be located.

engineer was also called in to troubleshoot and no problems could be found either at the breaker or at the interfacing systems.

Analysis of Occurresce: There was no danger to the health and safety of the public or to station personnel. The breaker was manually put in the tripped condition by had rod insertion been needed, the rods could have been tripped from an operator.

the control room since breaker "A" was still operable.

Corrective Action

Maintenance Work Order 80-3697 was issued to troubleshoot the The undervoltage device uas changed at the breaker but the aew coil later problem.

failed. The original device which was inspected and declared operational was put back on the breaker and satisfactorily tested. Control rod drive trip breaker "A" was swapped with breaker "C" to see if the problem follows the breaker in the future.

Failure Data: There have been no previous similar reportable occurrenc as.

LER #80-080

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