LER-1980-051, /03L-0:on 800619,while Performing ST 5031.07 Phase Ii,Sequencer Logic Channels 2 & 4 Did Not Operate as Designed.Caused by Component Failure of Relay Seqx & CR-3X in C3618.Relay Seqx Was replaced.CR-3X Was Cleaned |
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'FSCRIPTION AND PROBABLE CONSEQUENCES h EVE' l (Nr, 80-62) On 6/19/80 at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> while perferming ST 5031.07 Phase II, the I
o 2 o a l sequencer logic channels 2 and 4 did not operate as designed. The action statement ofi l o 14 l l T.S. 3.3.2.1 was not entered as the station was in Mode 6.
This is being reported to l ITTT] I document a component failure. There was no danger to the public or station personnel.l ITTTI I All emergency safety features equipment eventually started within two minutes of the l I Safety Features Actuation System trip.
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40 41 42 43 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h y l The cause was a component failure of relay SEQX in RC3702 and relay CR-3X in C3618.
I l Relay SEQX was replaced and CR-3X was cleaned. This phase of the test was rerun on I
1 i 1 6/20/80 at 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br /> and the sequencers were declared operable.
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-62 DATE OF EVENT: June 19, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Safety Features Actuation System (SFAS) Sequencer Logic Channels 2 and 4 failed to operate as designed Conditions Prior to Occurrence: The unit was in Mode 6, with Power (MWT) = 0 and Load (Gross MWE) = 0.
Description of Occurrence: On June 19, 1980 at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, during the performance of the Integrated SFAS Test ST 5031.07, Phase II, the sequencer logic channels 2 and 4 did not operate as designed.
This changed the order in which some of the equipment started, even though all started within two minutes.
Technical Specification 3.3.2.1 requires the sequencer logic channels to be opera-ble in Modes 1, 2, 3, and 4.
Being in Mode 6 at the time of the finding, the station did not enter any action statement.
This is being reported to document a component failure.
Designation of Apparent Cause of Occurrence: The cause of the event is the component failure of two relays.
Relay SEQX in RC3702 was introducing noise in the sequencer circuit.
Relay CR-3X in C3618 was dirty and not operating properly. These two prob-lems caused the sequencer for channels 2 and 4 to operate out of step. The sequencer logic of both channels must be in step to cause the equipment to start in the designed crder.
Analysis of Occurrence: There was no danger to the health and safety of the public cr to station personnel.
Even though the SEAS loads did not sequence in the designed crder, all emergency safety features equipment started within two minutes of the SEAS trip.
Corrective Action
Relay SEQX in the circuit for the channel 2 sequencer was re-placed and relay CR-3X was cleaned. This phase of the test was rerun at 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br /> on June 20, 1980, and the sequencers were declared operable.
The CR-3X relays have been added to the preventive maintenance program for periodic cleaning.
i Failure Data: None previously reported for the above reasons.
LER #80-051 L
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| 05000346/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000346/LER-1980-001-01, /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | | | 05000346/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000346/LER-1980-002-03, /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | | | 05000346/LER-1980-003-03, /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | | | 05000346/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000346/LER-1980-004-03, /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | | | 05000346/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000346/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000346/LER-1980-005-03, /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. 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Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | | | 05000346/LER-1980-022-03, /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | | | 05000346/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000346/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000346/LER-1980-023-03, /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | | | 05000346/LER-1980-024-03, /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | | | 05000346/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000346/LER-1980-025-03, /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | | | 05000346/LER-1980-025, Forwards LER 80-025/03X-1 | Forwards LER 80-025/03X-1 | |
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