LER-1979-038, /03L-0:on 791105,diesel Generator 1 Failed to Start During Diesel Generator 20% Plus Load Test.Caused by Component Failure.Breaker Position Switch Readjusted |
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On November 5, 1979, Diesel Generator #1 failed to start during the 1
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Generator breaker position switch 52HH l
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The position switch was found to be out of adjust-l c is 1 i ment.
After the switch was adjusted ar.d checked, the 20% Plus Load Test l
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lGl0l8l0[g 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS
.I Component failure was the cause of this event.
The breaker position j
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The position switch was readiusted.
The I
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The diesel generator breaker position switch will be added to l
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N AME OF PR. E PARER PHONE:
I Jersey C4ntral Power & Ught Corapany rff ( )
Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-38/3L-0 Report Date November 30, 1979 Occurrence Date November 5, 1973 Identification of Occurrence Operating in a degraded mode as permitted by Technical Specifications, parag ph 3.7.C.2, when Diesel Generator #1 failed to start during a survelliance test. This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b. (2).
Conditions Prior to Occurrence The plant was operating at steady state pewer.
The major parameters at the time of the occurrence were:
Power:
Reactor,1853 MWt Generator, 640 MWe Flow:
Recirculation, 14.8 x 104 gpm 6 lb/hr Feedwater, 7.01 x 10 4
Stack Gas:
3.19 x 10 pCi/sec Description of Occurrence On Monday, November 5, 1979, at approximately 4:00 a.m., while performing the Diesel Generator 20% Plus Load Test, diesel generatc.r breaker position switch 52HH did not close when the breaker was racked in.
This prevented Diesel Generator #1 from starting.
Upon immediate investigation, it was found that position switch 52HH was out of adjustment.
Diesel Generator #2 was run for one hour to satisfy Technical Specification requirements before Diesel Generator #1 was serviced.
A Job order was initiated to readjust the switch. The switch was readjusted and checked several times.
Diesel Generator
- 1 was returned to service after satisfactory completion of the 20% Plus Load Test
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?En Jersey Central Power & Light Company is a Member of the General Pub'ic Utilities System
Reportable Occurrence No. 50-219/79-38/3L-0 Page 2 November 30, 1979 Apparent Cause of Occurrence The cause of this occurrence is attributed to component failure.
Position switch for breaker was out of adjustment.
Analysis of Occurrence _
The diesel generators are required to supply a standby source of power to operate equipment required for a safe plant shutdown and to maintain the plant in a safe shutdown condition.
Each diesel is capable of operating the re-quired engineered safety equipment following an accident.
Diesel Generator #2 was verified operable; therefore, the safety significance was considered minimal because there was an adequate amount of standby power and no other safety equipment was out of service.
Corrective Action
The diesel generator breaker position switch check will be added to the 4160 volt breaker preventive maintenance procedure prior to the next year's refueling outage.
The breaker position switch on Diesel Generator #2 was tested and found satisfactory.
Faiiure Data Circuit Breaker Manufacturer:
General Electric Company Type:
AK2 A 1 Switch:
52HH l 'll bb
OC/NRC Distribution:
cc:
S. Bartnoff/R. O. Brokaw J. T. Carroll, Jr. (12)
T. M. Crimmins, Jr.
H. M. Dieckamp/R. C. Arnold /G. Bond /J. C. DeVine/C. R. Montgomery
- 1. R. Finfrock, Jr.
D. P. Gaines J. Knubel S. W. Laird J. B. Liberman H. K. Mayer/E. J. Sherratt E. F. O'Connor W. T. Osborne/M. B. Peters J. K. Pickard F. J. Smith /J. G. Herbein J. R. Thorpe T. i. Tipton G. F. Trowbridge H. J. Williams (2)
R. L. Williams Document Center / Plaza (2)
NJ Bureau of Radiation Protection Attention:
Chief Division of E nvironmental Quality United Sierra Building 380 Scotch Road West Trenton, New Jersey 08625 Mr. Richard E. Smith Nuclear Systems & Materials EPRI 3212 Hillview Avenue Palo Alto, California 94303 Mr. D. Weinstein Plant Component Behavior Analysis General Electric Company 175 Curtner Avenue H.C./138 San Jose, California 95125 151:
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| 05000219/LER-1979-001-03, /03L-0 on 790118:valve V-14-35 Failed to Open Completely During Routine Isolation Condenser Valve Operability Test.Caused by Dirty Torque Limit Switch Contacts,Which Were Subsequently Cleaned & Burnished | /03L-0 on 790118:valve V-14-35 Failed to Open Completely During Routine Isolation Condenser Valve Operability Test.Caused by Dirty Torque Limit Switch Contacts,Which Were Subsequently Cleaned & Burnished | | | 05000219/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000219/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000219/LER-1979-002-03, /03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset | /03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset | | | 05000219/LER-1979-010-03, /03L-0 on 790417:leak of Isotopic Concentration Noticed Near Inside Penetration within Pipe Tunnel.Caused by Component Failure.Drywell Equipment Drain Tank Line Rerouted to Prevent Further Leakage | /03L-0 on 790417:leak of Isotopic Concentration Noticed Near Inside Penetration within Pipe Tunnel.Caused by Component Failure.Drywell Equipment Drain Tank Line Rerouted to Prevent Further Leakage | | | 05000219/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000219/LER-1979-011-03, /03L-0 on 790419:core Spray Pump NZO1A in Sys 1 Failed to Start Upon Initiation Signal.Caused by Fuse Failure.Fuse Replaced & Pump Test Successfully Completed | /03L-0 on 790419:core Spray Pump NZO1A in Sys 1 Failed to Start Upon Initiation Signal.Caused by Fuse Failure.Fuse Replaced & Pump Test Successfully Completed | | | 05000219/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000219/LER-1979-012-03, /03L-0 on 790419:oxygen Level in Suppression Chamber Atmosphere Was Greater than 5%.Caused by Sensitivity of Sampling Sys & Position of Sample Flow Control Valve. Oxygen Analyzer Recalibr;Level Now Below 5% | /03L-0 on 790419:oxygen Level in Suppression Chamber Atmosphere Was Greater than 5%.Caused by Sensitivity of Sampling Sys & Position of Sample Flow Control Valve. Oxygen Analyzer Recalibr;Level Now Below 5% | | | 05000219/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000219/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000219/LER-1979-016-03, /03L-0 on 790506:during Surveillance Test, Isolator Condenser Isolation Sensor Setpoint a Measured Two Inches of Excess Water.Caused by Instrument Drift in Excess of Design Accuracy.Switch Was Recalibr & Put Back in Svc | /03L-0 on 790506:during Surveillance Test, Isolator Condenser Isolation Sensor Setpoint a Measured Two Inches of Excess Water.Caused by Instrument Drift in Excess of Design Accuracy.Switch Was Recalibr & Put Back in Svc | | | 05000219/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000219/LER-1979-017-03, /03L-0 on 790517:during Routine Surveillance of Core Spray Sys Ii,Parallel Isolation Valve V-20-21 Failed to Operate.Caused by Circuit Breaker Contacts Making Poor Contact in B Phase,Creating Overcurrent.Part Replaced | /03L-0 on 790517:during Routine Surveillance of Core Spray Sys Ii,Parallel Isolation Valve V-20-21 Failed to Operate.Caused by Circuit Breaker Contacts Making Poor Contact in B Phase,Creating Overcurrent.Part Replaced | | | 05000219/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000219/LER-1979-018-03, /03L-0 on 790517:snubber 51/21,core Spray Sys II, Had Signs of Grease on Alemite Fitting on Accumulator.Cause Unknown But Appears Related to Rigorous Svc Conditions. Snubber Replaced | /03L-0 on 790517:snubber 51/21,core Spray Sys II, Had Signs of Grease on Alemite Fitting on Accumulator.Cause Unknown But Appears Related to Rigorous Svc Conditions. Snubber Replaced | | | 05000219/LER-1979-019-03, /03L-0 on 790526:reactor High Pressure Isolation Condenser Initiation Switch RE-15A Tripped at 3 Psig Greater than Specified.Caused by Instrument repeatability.RE-158 Reset to Trip at 1,068 Psig | /03L-0 on 790526:reactor High Pressure Isolation Condenser Initiation Switch RE-15A Tripped at 3 Psig Greater than Specified.Caused by Instrument repeatability.RE-158 Reset to Trip at 1,068 Psig | | | 05000219/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000219/LER-1979-020, Forwards LER 79-020/01T-0 | Forwards LER 79-020/01T-0 | | | 05000219/LER-1979-020-01, /01T-0 on 790613:secondary Containment Integrity Breached When Reactor Bldg Airlock Doors Were Opened Simultaneously.Caused by Failure of Procedure to State Correct Method for Securing Airlock Doors.Procedure Revised | /01T-0 on 790613:secondary Containment Integrity Breached When Reactor Bldg Airlock Doors Were Opened Simultaneously.Caused by Failure of Procedure to State Correct Method for Securing Airlock Doors.Procedure Revised | | | 05000219/LER-1979-021-03, /03L-0 on 790620:during Surveillance Testing Activities,Instrument 1P15A Was Found to Trip at Valve Higher than Allowed by Tech Specs.Instrument Found to Be within Expected Accuracy Attainable | /03L-0 on 790620:during Surveillance Testing Activities,Instrument 1P15A Was Found to Trip at Valve Higher than Allowed by Tech Specs.Instrument Found to Be within Expected Accuracy Attainable | | | 05000219/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000219/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000219/LER-1979-022-03, /03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced | /03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced | | | 05000219/LER-1979-023-01, /01T-0 on 790719:reactor Power Was Reduced Above Value for Removal of a Feedwater String.Caused by Removal of Recirculating Pump Reactor for Maint.Inboard & Outboard Collector Rings Resurfaced & Pump Returned to Svc | /01T-0 on 790719:reactor Power Was Reduced Above Value for Removal of a Feedwater String.Caused by Removal of Recirculating Pump Reactor for Maint.Inboard & Outboard Collector Rings Resurfaced & Pump Returned to Svc | | | 05000219/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | | | 05000219/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000219/LER-1979-024-03, /03L-0:on 790730,control Rod Drive Pump a Discovered Spraying Water Through Seal.Caused by Failure of Mechanical Seal.Inboard Mechanical Seal & Inboard Bearing Replaced | /03L-0:on 790730,control Rod Drive Pump a Discovered Spraying Water Through Seal.Caused by Failure of Mechanical Seal.Inboard Mechanical Seal & Inboard Bearing Replaced | | | 05000219/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000219/LER-1979-025-03, /03L-0:on 790806,10,000 Gallons of Torus Water Drained & Ability of Primary Containment Degraded.Caused by Isolation Valve Left Open After Water Samplings.Change to Sampling Procedure Submitted on Use of Valve | /03L-0:on 790806,10,000 Gallons of Torus Water Drained & Ability of Primary Containment Degraded.Caused by Isolation Valve Left Open After Water Samplings.Change to Sampling Procedure Submitted on Use of Valve | | | 05000219/LER-1979-026-03, /03L-0:on 790807,while Excavating to Repair Equipment Drain Tank Line,Leak in Laundry Tank Discharge Pipe Discovered.Caused by Levels of Mn-54 & Co-60.Line Temporarily Rerouted Until Repairs Made | /03L-0:on 790807,while Excavating to Repair Equipment Drain Tank Line,Leak in Laundry Tank Discharge Pipe Discovered.Caused by Levels of Mn-54 & Co-60.Line Temporarily Rerouted Until Repairs Made | | | 05000219/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000219/LER-1979-027, Forwards LER 79-027/01T-0 | Forwards LER 79-027/01T-0 | | | 05000219/LER-1979-027-01, /01T-0 on 790807:four Seismic restraints,NZ-2-R5 NZ-2R7,NZ-2-R8 & NZ-2-R9,in Positions Other than Required by Original Design.Caused by Improper Installation & Damage Due to Unrestrained Pipe Movement | /01T-0 on 790807:four Seismic restraints,NZ-2-R5 NZ-2R7,NZ-2-R8 & NZ-2-R9,in Positions Other than Required by Original Design.Caused by Improper Installation & Damage Due to Unrestrained Pipe Movement | | | 05000219/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000219/LER-1979-028-03, /03L-0:on 790807,during Routine Surveillance of Core Spray Sys 1,parallel Isolation Valve V-20-15 Became Inoperable in Open Position.Caused by High Motor Current Drawn When Close Signal Inadvertently Initiated | /03L-0:on 790807,during Routine Surveillance of Core Spray Sys 1,parallel Isolation Valve V-20-15 Became Inoperable in Open Position.Caused by High Motor Current Drawn When Close Signal Inadvertently Initiated | | | 05000219/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000219/LER-1979-029-03, /03L-0:on 790822,rod Block Trip Setting Was Below 100 Counts Per Second 26 Times During QA Audit.Caused by Calibr Procedure Setting Rod Trip at Tech Spec Limit.Rod Withdrawal Block Setpoint Increased | /03L-0:on 790822,rod Block Trip Setting Was Below 100 Counts Per Second 26 Times During QA Audit.Caused by Calibr Procedure Setting Rod Trip at Tech Spec Limit.Rod Withdrawal Block Setpoint Increased | | | 05000219/LER-1979-030, Revised Attachment to LER 79-030/03L-0:on 790812,control Rod Drive Pump a Removed from Svc for Repair of Pump Vent Piping.Piping Cracked at Bushing at Entry to Pump Casing. Caused by Operator Carelessness.Bushing Replaced | Revised Attachment to LER 79-030/03L-0:on 790812,control Rod Drive Pump a Removed from Svc for Repair of Pump Vent Piping.Piping Cracked at Bushing at Entry to Pump Casing. Caused by Operator Carelessness.Bushing Replaced | | | 05000219/LER-1979-030-03, /03L-0:on 790812,control Rod Drive Pump Removed from Svc Due to Excessive Leakage from Pump Vent Piping. Piping Was Cracked at Bushing.Caused by Use of Vent Line as Operator Foot Support.Bushing & Pipe Nipple Replaced | /03L-0:on 790812,control Rod Drive Pump Removed from Svc Due to Excessive Leakage from Pump Vent Piping. Piping Was Cracked at Bushing.Caused by Use of Vent Line as Operator Foot Support.Bushing & Pipe Nipple Replaced | | | 05000219/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000219/LER-1979-031-03, /03L-0:on 790829,seal Water Piping Found Cracked on Short Pipe Nipple Section Where Threaded Into Seal Cartridge.Caused by Operator Using half-inch Piping as Foot Support.Pipe Nipple Replaced | /03L-0:on 790829,seal Water Piping Found Cracked on Short Pipe Nipple Section Where Threaded Into Seal Cartridge.Caused by Operator Using half-inch Piping as Foot Support.Pipe Nipple Replaced | | | 05000219/LER-1979-032, Forwards LER 79-032/03L-0 | Forwards LER 79-032/03L-0 | | | 05000219/LER-1979-032-03, /03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended | /03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended | | | 05000219/LER-1979-033, Forwards LER 79-033/03L-0 | Forwards LER 79-033/03L-0 | | | 05000219/LER-1979-033-03, /03L-0:on 790917,electromatic Relief Valve Pressure Switch 1A83A Tripped at Pressure in Excess of Limit.Caused by Defective High Pressure Microswitch. Replacement Switch Installed | /03L-0:on 790917,electromatic Relief Valve Pressure Switch 1A83A Tripped at Pressure in Excess of Limit.Caused by Defective High Pressure Microswitch. Replacement Switch Installed | | | 05000219/LER-1979-034, Forwards LER 79-034/01T-0 | Forwards LER 79-034/01T-0 | | | 05000219/LER-1979-034-01, /01T-0:on 791008,both Personnel Access Air Lock 15ors of Reactor Bldg Were Simultaneoulsy Open.Caused by Contractor Personnel Disconnecting Automatic Closing Device on One Door.Device Reconnected | /01T-0:on 791008,both Personnel Access Air Lock 15ors of Reactor Bldg Were Simultaneoulsy Open.Caused by Contractor Personnel Disconnecting Automatic Closing Device on One Door.Device Reconnected | | | 05000219/LER-1979-035, Forwards LER 79-035/03L-0 | Forwards LER 79-035/03L-0 | | | 05000219/LER-1979-035-03, /03L-0:on 790926,during Normal Operation,Reading on Main Steam Line Radiation Monitor Lower than Other Three Monitors.Caused by Drift of Zero Setpoint of Amplifier in Monitor.Setpoint Reset to Zero | /03L-0:on 790926,during Normal Operation,Reading on Main Steam Line Radiation Monitor Lower than Other Three Monitors.Caused by Drift of Zero Setpoint of Amplifier in Monitor.Setpoint Reset to Zero | |
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