LER-1980-086, /03L-0:on 801203,while Performing ST 5030.12, Alligator Clip Slipped Off Terminal Studs 3 & 4 Causing Short Circuit.Caused by Design Error.St 5030.12 Modified & F101 Fuse Replaced |
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6 EVENT DESCmPTION AND FROB ABLE CONSECUENCES h lo12]l(NP-33-SO-111) On 12/3/80 at approximately 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br /> during testing in Reactor Pro-l terminal stud caus-l l tection System (RPS) Channel 3, an alligator clip slipped off the [o#3l l a l 4 ] l ing a short circuit between terminals 3 and 4.
A loss of power to the Y3 essential j
including RPS Chan-l ioI5l l power bus followed which in turn de-energized several instruments I; 161 l nel 3 and Safety Features Actuation Systen (SFAS) Channel 3.
This placed the unit in J J a l il l violation of T.S. 3.8.2.1.
There was no danger. RPS and SFAS Channels 1, 2, and 4 l
lwere continuously available as were the 120 VAC essential buses YI, Y2, and Y4.
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[,j3; l Order 80-3918 replaced the YV3 inverter input fuse F101 and the RPS trip circuit fuse.
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DVR 80-198
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TOLED0 EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-111 DATE OF EVENT:
December 3, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Loss of Instrument Bus Y-3 Conditions Prior to Occurrence:
T'ne unit was in Mode 3 with Power (MWT) = 0 and Load (Gross KJE) = 0.
Description of Occurrence: On December 3, 1980 at about 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br /> while performing ST 5030.12, Control Rod Drive Trip Breaker Logic Functional Test in Reactor Protection System (RPS) Channel 3, one of a set of insulated alligator clips attached to terminal board 1-10-6 terminals 3 and 4 slipped of f causing a short circuit between terminals 3 and 4.
These terminals are used to monitor 115 VAC to the trip breaker undervoltage coil. The short circuit resulted in the RPS trip circuit fuse F2 and the YV3 inverter input fuse F101 blowing. The failure of YV3 fuse F101 caused a loss of power to the Y3 essential power bus de-energizing several instruments including RPS Channel 3 and Safety Features Actuation System (SFAS) Channel 3.
The loss of instrument bus Y3 caused the station to be placed in the action statement of Technical Specification 3.8.2.1.
The action statement requires the inoperable bus to b.
restored to operable status within eight hours or be in at least hot standby within the next six hours and in cold shutdown within the following thirty hours. Bus Y3 was manually transferred to its alternate source and the SFAS and RPS channels were re-energized.
Designation of Apparent Cause of Occurrence: The apparent cause of this occurrence was two-fold.
The short circuit was the result of too large a stud placed on these terminals, specifically for this surveillance test, such that the alligator clips utilized are almost entirely opened in order to grip the stud, thus preventing a secure, tensioned hold. These studs were put in place by Facility Change Request 79-273. The second cause is in the design in that the 200 amp inverter fuse blew, de-energizing the whole bus, before a 30 amp RPS supply fuse or the 25 amp RPS circuit breaker could pro-vide the necessary protection.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel.
RPS and SFAS Channels 1, 2, and 4 were continuoualy available as were 120 VAC essential buses Yl, Y2, and Y4
Corrective Action
Maintenance Work Order 80-3918 was issued to investigace the loss of the Y3 bus.
F101 was found blown and was replaced. There was no apparent damage to the inverter. The Y3 bus was transferred back to its normal source.
ST 5030.12 was modified to delete the requirement to measure the trip breaker voltage. Facility Change Request 80-217 was prepared in September of 1980 to correct the inverter fuse problem.
LER #80-086
P-TOLEDO EDIS0N COMPANY DAVIS-BESSE NUCLEAR PO'n'ER STATION UNIT ONE PAGE 2 SUPPLE >tENTAL INFOPJtATION FOR LER NP-33-80-111 Previous failures of 120 VAC essential power inverters due to accidental Failure Data:
shorting were reported in Licensee Event Reports NP-32-79-09, NP-33-79-13, and NP-33-80-70.
LER #80-086 I
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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. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | | | 05000346/LER-1980-006-03, /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | | | 05000346/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000346/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000346/LER-1980-007-03, /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | | | 05000346/LER-1980-008-03, Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | | | 05000346/LER-1980-008, Forwards Revised LER 80-008/03L-1 | Forwards Revised LER 80-008/03L-1 | | | 05000346/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000346/LER-1980-009-03, /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | | | 05000346/LER-1980-010-01, /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | | | 05000346/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000346/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000346/LER-1980-011-03, /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | | | 05000346/LER-1980-012-03, /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Reposition | /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Repositioned | | | 05000346/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000346/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | | | 05000346/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000346/LER-1980-014-03, /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | | | 05000346/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000346/LER-1980-015-03, /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | | | 05000346/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000346/LER-1980-016-03, /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | | | 05000346/LER-1980-017-03, /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | | | 05000346/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000346/LER-1980-018-03, /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | | | 05000346/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000346/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000346/LER-1980-019-01, /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | | | 05000346/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000346/LER-1980-020-03, /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | | | 05000346/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000346/LER-1980-021-03, /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. 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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