LER-1979-031, /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 |
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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE fJ EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O
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During normal operation,
CRD pump was removed from service due to I
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The pipino was I
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The affected short pipe nipple in the line was reolaced i
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DESCRIPTION
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n 68 69 go, e 9 1C Donald A. Ross 20'-455-8784 teAME OF PRED ARER PHONE:
Jersey Central Power & Light Company
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Madison Avenue at Punch Bowl Road yp Morristown, New Jersey 07960
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(201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-31/3L-C Report Date September 26, 1979 Occurrence Date August 29, 1979 Identification of Occurrence "B" CRD hydraulic pump was removed from service to repair leaking seal water piping. This event is considered to be a recortable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.
Conditions Prior to Occurrence Load changes during routine power operation were being made.
Power:
Core, 1704.3 MWt Electric, 554 MVe 4
Flow:
Recirculating 15.4 x 10 gpm 6 lb/hr Feedwater, 6.341 x 10 Stack Gas Activity:
32,100 pCi/sec.
Description of Occurrence "B" CRD hydraulic pump seal water piping connection on the outboard seal was found to be leaking on Wednesday, August 29, 1979, at approximately 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />.
The "A" control rod drive pump was placed into service and the "B" pump removed from service and isolated for the purpose of performing corrective maintenance.
On August 30, 1979, at 1602 hours0.0185 days <br />0.445 hours <br />0.00265 weeks <br />6.09561e-4 months <br />, the "B" control rod drive pump was placed into service and considered operable.
Apparent Cause of Occurrence The seal water piping was found to be cracked on a short pipe nipple section where it is threaded into the seal cartridge.
Failure of the piping is attributed to use of the 1/2" piping as a support by operators during valving operations in the area.
17',2 296 Jersey Central Power & Light Compey is a Member of the Genera! Pub'c Ut '.t.es System
Reportable Occurrence No. 50-219/79-31/3L-0 Page 2 September 26, 1979 Analysis of Occurrence in addition to supplying drive cooling and accumulator charging pressure, the control rod drive hydraulic system can provide high pressure coolant injection capability.
For break sizes up to 0.002 ft.2, a single control rod drive pump with flow of 110 gpm is adequate for maintaining the reactor water level nearly five feet above the core, thus alleviating the necessity for electromatic relief valve actuation.
The safety significance of this event is considered to be minimal, since the redundant pump was operable.
Corrective Action
The "B" control rod drive pump was removed from service, isolated, and the pipe nipple replaced. Af ter completion of the corrective maintenance, the "B" control rod drive pump was placed into service.
A memorandum has been issued to operations and maintenance personnel to stress the importance of not using small pipes as a suppo.*t when climbing or rigging equipment.
Failure Data 1/2" pipe Material - Carbon Steel 7
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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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