LER-1979-131, /03L-0:on 791212,steam & Feedwater Rupture Control Sys Channel 4x15-volt Dc Power Supply PS-4 Failed.Caused by Overvoltage Trip Setpoint Actuating at Lower Value than Initial Adjustment.Installed New Power Supply |
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| 3461979131R03 - NRC Website |
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U. S. NUCLEAR REGULATOR o.uMlbu.
NFC FORf.1 C 3G (7 771 LICENSEE EVENT REPORT CONTROL BLOCK l l
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(PLE ASE PRINT OR TYPE ALL REQUIRED INFORf.1ATION)
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REPOHT DAT E BJ EVENT DESCRIPTION AND PROBABLE CCNSEGUENCES h lOn 12/12/79, and again on 1/6/80, the Steam and Feedwater Rupture Control System l
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l (SFRCS) Chanel 4 +15 volt DC power supply PS-4 f ailed causing a Channel 4 half trip l
goj3; lin Channel 2/4. Technical Specification 3.3.2.2 requires all four channels operable 1 9
lin Modes 1, 2, 3, and 4.
The station was in !! ode 5 on 12/12/79 and in !! ode 1 on
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1 1/6/80. There was no danger to the health and safety of the public or station per-l l C l 7 l l sonnel. Loss of the power supply places the channel in the tripped (safe) position.
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43 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l The cause of the initial occurrence was the overvoltage trip setpoint actuating at a l i
o l lower value than the initial adjustment. The trip setpoint was readjusted and the j
g l: l gg l channel declared operable on 12/27/79. The power supply failed on 1/6/80 and will be [
l returned to the vendor for further analysis. A new power supply was installed, and 3
[,,,,,lthe channel returned to operability on 1/7/80.
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4 TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-53-79-148 DATE OF EVENT: December 12, 1979, January 6,1980 FACILITY: Davis-Besse Unit 1 Failure of +15 volt DC power supply PS-4 in Steam IDENTIFICATION OF OCCURRENCE:
and Feedwater Rupture Control System (SFRCS) Channel 4.
The unit was in Mode 5, with Power (MWT) = 0, Conditions' Prior to First Occurrence:
and Load (Gross MWE) = 0.
tlc unit was in Mode 1, with Power (MWT) = 27 Conditions Prior to Second Occurrence:
and Load (Gross MWE) = 0.
Description of Occurrence: On December 12, 1979 at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />, the SFRCS Channel 4
+15 volt DC power supply PS-4 failed causing a Channel 4 half trip in Channel 2/4.
This did not place the unit in the action statement of Technical Specification 3.3.2.2 which requires all four channels to be operabic in Modes 1, 2, and 3 only.
This event is being reported The unit was in Mode 5 at the time of the occurrence.
to document a component failure.
On January 6, 1980 at 2039 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.758395e-4 months <br />, the SERCS Channel 4 power supply PS-4 failed caus-This event did place the unit in Action in; a Channel 4 half trip in Channel 2/4.13 of Technical Specification 3.3.2.2 which re The channel Statement of the channel to be placed in the tripped condition within one hour.
was declared inoperable at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> and maintained in the tripped condition.
Investigation has revealed that the Designation of Apparent Cause of Occurrence:
a lower cause of the first occurrence was in the overvoltage trip setting actuating at The reason for the value than the initial installation setpoint of October 4, 1979.
drif t in the overvoltage prntection setpoint is unknown at this time. The power will be returned to the vendor (Sorenson) for further supply PS-4 (Serial No. 01 analysis of the cause of the failure.
There was no danger to the health and safety of the public Analysis of Occurrence:
The SFRCS Channel 4 performed as designed in both occur-or to station personnel.
The power supply PS-4 caused a trip condition in Channel 4 of SFRCS rences.
Channel 2/4.
During the time interval between the initial occurrence and
Corrective Action
when power was restored to the power supply, the input and output December 26, 1979, No trips of the power supply occurred during this time of the supply were monitored.
period.
i747 004
TOLEDO ED1 SON COMPANY Di.VIS-BESSE NUCLEAR PO'4ER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-148 PAGE 2 On December 26, 1979 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, the 15 volt DC power supply Serial No. 0148 was removed from the SFRCS channel and bench tested. The overvoltage protection setpoint was re-adjusted to the value as required by the mcaufacturer's technical information.
The power supply (Scrial No. 0140) was reinstalled in the SFRCS Channel 4.
The channel was declared operable on December 28, 1979. At the time of the second occurrence on January 6,1980, the SFRCS Channel 4 power supply PS-4 (Serial No. 0148) was removed from the SFRCS Channel 4.and tested again.
The overvoltage trip setting was not the cause of this f ailure and no apparent cause for the failure was discovered at this time.
On January 7,1980 at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, a new 15 volt DC power supply (Serial No. 0345) was installed as PS-4 in SFRCS Channel 4.
The channel was declared operable on January 7, 1980 at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />.
Failure Data: There has been one previous failure of an SFRCS 15 volt DC power supply, see Licensee Event Report NP-33-79-113.
1747 005
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| 05000346/LER-1979-001-03, /03L-0 on 790102:monthly Functional Test Not Performed on Reactor Protection Sys Channel 2 within Allowable Time.Caused by Breakdown in Communications Between Testing Personnel & Test Coordinator | /03L-0 on 790102:monthly Functional Test Not Performed on Reactor Protection Sys Channel 2 within Allowable Time.Caused by Breakdown in Communications Between Testing Personnel & Test Coordinator | | | 05000346/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000346/LER-1979-002-03, /03L-1 on 790102:main Steam Valves 106 & 106A Failed to Open,Resulting in Auxiliary Feed Pump Afp 1-1 Being Taken Out of Operation.Caused by Dirt Buildup on Valve Stems as Result of New Const | /03L-1 on 790102:main Steam Valves 106 & 106A Failed to Open,Resulting in Auxiliary Feed Pump Afp 1-1 Being Taken Out of Operation.Caused by Dirt Buildup on Valve Stems as Result of New Const | | | 05000346/LER-1979-002, Forwards LER 79-002/03L-1 | Forwards LER 79-002/03L-1 | | | 05000346/LER-1979-003-03, /03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable | /03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable | | | 05000346/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000346/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000346/LER-1979-004-03, /03L-0 on 790105:failure to Post Guards at Entrance to Containment During Periods of Free Access. Caused by Personnel Error.Special Order 84 Revised to Require Posting of Guards | /03L-0 on 790105:failure to Post Guards at Entrance to Containment During Periods of Free Access. Caused by Personnel Error.Special Order 84 Revised to Require Posting of Guards | | | 05000346/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000346/LER-1979-005-03, /03L-0 on 790106:during Surveillance Testing, Borated Water Storage Tank Level Bistable Was Tripped;Valves DH9A Opened & DH7A Closed.Caused by Component Failure of Output Relay K51A & Instrument Drift | /03L-0 on 790106:during Surveillance Testing, Borated Water Storage Tank Level Bistable Was Tripped;Valves DH9A Opened & DH7A Closed.Caused by Component Failure of Output Relay K51A & Instrument Drift | | | 05000346/LER-1979-006-03, /03L-0:on 790105,reviewer Noted 781228 Record of Continuous Alarm at Contact Data Record Point F018.Panel C4705 Not Reset.Caused by Failure of Indicator Lights on Panel C4705.Panel Reset,Clearing F018.Surveillance Modified | /03L-0:on 790105,reviewer Noted 781228 Record of Continuous Alarm at Contact Data Record Point F018.Panel C4705 Not Reset.Caused by Failure of Indicator Lights on Panel C4705.Panel Reset,Clearing F018.Surveillance Modified | | | 05000346/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000346/LER-1979-007-03, /03L-0 on 790110:during Performance of Surveillance Test,Channel 2 of Containment Hydrogen Analyzer Was Found Inoperable.Caused by Defective Zener Diode in Millivolt Converter | /03L-0 on 790110:during Performance of Surveillance Test,Channel 2 of Containment Hydrogen Analyzer Was Found Inoperable.Caused by Defective Zener Diode in Millivolt Converter | | | 05000346/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000346/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000346/LER-1979-008-03, /03L-0 on 790109:during Surveillance Testing, Containment Recirculation Fan 1-1 Failed to Run.Cause Attributed to Buildup of non-conductive Film on Auxiliary Controller Contacts | /03L-0 on 790109:during Surveillance Testing, Containment Recirculation Fan 1-1 Failed to Run.Cause Attributed to Buildup of non-conductive Film on Auxiliary Controller Contacts | | | 05000346/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000346/LER-1979-009-03, /03L-0:on 790112,power to Vital Bus Y2 Lost. False Integrated Control Sys Signal Resulted in Reactor & Full Steam & Feedwater Rupture Control Sys Trip.Caused by Blown 125 Volt DC Fuse to Inverter | /03L-0:on 790112,power to Vital Bus Y2 Lost. False Integrated Control Sys Signal Resulted in Reactor & Full Steam & Feedwater Rupture Control Sys Trip.Caused by Blown 125 Volt DC Fuse to Inverter | | | 05000346/LER-1979-010-03, /03L-0:on 790112,Sys 7 Data Logger Experienced Core Dump,Voiding Computer Memory Bank Which Rendered Remote Monitoring of Fire Detection Sys Inoperable & Placed Unit in Action Statement of Tech Spec 3.3.3.8.Cause Unknown | /03L-0:on 790112,Sys 7 Data Logger Experienced Core Dump,Voiding Computer Memory Bank Which Rendered Remote Monitoring of Fire Detection Sys Inoperable & Placed Unit in Action Statement of Tech Spec 3.3.3.8.Cause Unknown | | | 05000346/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000346/LER-1979-011-03, /03L-0:on 790115,reactor Coolant Pump 1-2-2 Started W/Incorrect Breaker Alignment,Causing Low Voltage Relays to Trip Which de-energized Both 4.16 Kv Essential Buses C1 & D1.Caused by Personnel Error | /03L-0:on 790115,reactor Coolant Pump 1-2-2 Started W/Incorrect Breaker Alignment,Causing Low Voltage Relays to Trip Which de-energized Both 4.16 Kv Essential Buses C1 & D1.Caused by Personnel Error | | | 05000346/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000346/LER-1979-012-03, /03L-0:on 790116,during Surveillance Testing,Heat Traced Line Temp Measurement Points Below 105 F Limit.Caused by Injection of Makeup (Flush) Water After Boron Injection at Temp Lower than 105 F.Tests Rerun Satisfactorily | /03L-0:on 790116,during Surveillance Testing,Heat Traced Line Temp Measurement Points Below 105 F Limit.Caused by Injection of Makeup (Flush) Water After Boron Injection at Temp Lower than 105 F.Tests Rerun Satisfactorily | | | 05000346/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000346/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000346/LER-1979-013-03, /03L-0:on 790116,when Makeup Pump 1 Started for Surveillance testing,1/2 Inch Nipple at Discharge of Attached Gear Driven Lube Oil Pump Failed,Resulting in Oil Spray Which Required Pump Shutdown | /03L-0:on 790116,when Makeup Pump 1 Started for Surveillance testing,1/2 Inch Nipple at Discharge of Attached Gear Driven Lube Oil Pump Failed,Resulting in Oil Spray Which Required Pump Shutdown | | | 05000346/LER-1979-014-03, /03L-0:on 790116,during Shutdown,Boric Acid Addition Tanks (Baat) Total Vol 3-1/3% Below Tech Spec 3.1.2.9 Requirements.Caused by Reduced Baat Vol After Completion of Required Testing Followed by RCS Boration | /03L-0:on 790116,during Shutdown,Boric Acid Addition Tanks (Baat) Total Vol 3-1/3% Below Tech Spec 3.1.2.9 Requirements.Caused by Reduced Baat Vol After Completion of Required Testing Followed by RCS Boration | | | 05000346/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000346/LER-1979-015-03, /03L-0:on 790117,core Flood Tank 1-2 Isolation Valve CF1A Would Not Close by Remote Operation.Caused by Loose Set Screw.Cracked Pinion Gear & Associated Key Replaced Per Maint Work Order 78-2928 | /03L-0:on 790117,core Flood Tank 1-2 Isolation Valve CF1A Would Not Close by Remote Operation.Caused by Loose Set Screw.Cracked Pinion Gear & Associated Key Replaced Per Maint Work Order 78-2928 | | | 05000346/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000346/LER-1979-016-03, /03L-0:on 790124,emergency Lock Failed Leak Rate Test While Unit in Mode 5.Caused by Loosening of Shaft Seal (Teflon Packing) Due to Routine Use of Escape Lock.Packing Will Be Replaced During Next Convenient Outage | /03L-0:on 790124,emergency Lock Failed Leak Rate Test While Unit in Mode 5.Caused by Loosening of Shaft Seal (Teflon Packing) Due to Routine Use of Escape Lock.Packing Will Be Replaced During Next Convenient Outage | | | 05000346/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000346/LER-1979-017-03, /03L-0:on 790130,photoelectric Smoke Detector Ds 8605-E in Emergency Diesel Generator 1-1 Area Not Functional.Caused by Failure of Detector.New Detector Ordered & Fire Watch Patrol Established in Area | /03L-0:on 790130,photoelectric Smoke Detector Ds 8605-E in Emergency Diesel Generator 1-1 Area Not Functional.Caused by Failure of Detector.New Detector Ordered & Fire Watch Patrol Established in Area | | | 05000346/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000346/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000346/LER-1979-018-03, /03L-0:on 790130,valves SP17A2 & SP17B2 Lifted Below Setpoint Range & Declared Inoperable.Caused by Loose Spindle on Main Steam Line Code Safety Valve SP17A2.Valve SP17A2 Gagged & SP17B2 Tested Satisfactorily | /03L-0:on 790130,valves SP17A2 & SP17B2 Lifted Below Setpoint Range & Declared Inoperable.Caused by Loose Spindle on Main Steam Line Code Safety Valve SP17A2.Valve SP17A2 Gagged & SP17B2 Tested Satisfactorily | | | 05000346/LER-1979-019-03, /03L-0 on 790129:suction & Discharge Valves on Containment Spray Pump Were Closed.Caused by Personnel Error | /03L-0 on 790129:suction & Discharge Valves on Containment Spray Pump Were Closed.Caused by Personnel Error | | | 05000346/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000346/LER-1979-020-03, /03L-0 on 790205:10 of 18 Main Steam Safety Valves Found Outside Setpoint Range.Believed Caused by Changing Ambient Conditions at Valve Locations.Valves Adjusted & Retested Satisfactorily | /03L-0 on 790205:10 of 18 Main Steam Safety Valves Found Outside Setpoint Range.Believed Caused by Changing Ambient Conditions at Valve Locations.Valves Adjusted & Retested Satisfactorily | | | 05000346/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000346/LER-1979-021-03, /03L-0 on 790205:containment High Pressure Alarms Were Received & Safety Features Actuation Sys Channel 2 Erroneously Tripped.Cause Unknown.No Deficiencies Found from Surveillance Tests.Channel Returned to Operation | /03L-0 on 790205:containment High Pressure Alarms Were Received & Safety Features Actuation Sys Channel 2 Erroneously Tripped.Cause Unknown.No Deficiencies Found from Surveillance Tests.Channel Returned to Operation | | | 05000346/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000346/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000346/LER-1979-022-03, /03L-0 on 790208:diesel Fire Pump Battery Electrolyte Level in Four Cells Was Below Top of Cell Plates.Caused by Procedural Error.Levels Restored,Pump Declared Operable & Unit Removed from Action Statement | /03L-0 on 790208:diesel Fire Pump Battery Electrolyte Level in Four Cells Was Below Top of Cell Plates.Caused by Procedural Error.Levels Restored,Pump Declared Operable & Unit Removed from Action Statement | | | 05000346/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | | | 05000346/LER-1979-023-01, /01T-0 on 790228:Startup Transformer 01 Taken Out of Svc;Surveillance Tests Not Performed within One Hour, Contrary to Tech Spec Requirements.Caused by Personnel Error.Testing Completed as Soon as Error Realized | /01T-0 on 790228:Startup Transformer 01 Taken Out of Svc;Surveillance Tests Not Performed within One Hour, Contrary to Tech Spec Requirements.Caused by Personnel Error.Testing Completed as Soon as Error Realized | | | 05000346/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000346/LER-1979-024-03, /03L-0 on 790214:fire Alarm Panel C4706 Signaled, Indicating Laundry Room Detector DS8630 as Source.Detector Declared Inoperable as No Cause for Signal Found.Cause of Event Undetermined.Possibly Due to Gases or Dust | /03L-0 on 790214:fire Alarm Panel C4706 Signaled, Indicating Laundry Room Detector DS8630 as Source.Detector Declared Inoperable as No Cause for Signal Found.Cause of Event Undetermined.Possibly Due to Gases or Dust | | | 05000346/LER-1979-025-03, /03L-0 on 790213:Ohio Edison Relay Testing Actuated Transfer Trip Receiving Relay & Tripped Switchyard Breakers.Caused by Failure of Util to Notify Toledo Edison Before Performing Relay Testing | /03L-0 on 790213:Ohio Edison Relay Testing Actuated Transfer Trip Receiving Relay & Tripped Switchyard Breakers.Caused by Failure of Util to Notify Toledo Edison Before Performing Relay Testing | | | 05000346/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | |
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