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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029E2071994-05-0909 May 1994 LER 94-004-00:on 940416,discovered That Surveillance Frequency for Sp 34SV-SUV-008-1S Not Correct for Seven Primary Containment Vent & Purge Valves Due to Personnel Error.Surveillance Brought Up to date.W/940509 Ltr ML20029C8681994-04-25025 April 1994 LER 94-003-00:on 940329,automatic Reactor Shutdown Occurred Due to Trip of Main Turbine.Caused by Loss of Main Generator Field Excitation.Damaged Main Generator Exciter Rotor replaced.W/940425 Ltr ML20029C6981994-04-19019 April 1994 LER 94-002-00:on 940325,personnel Error Resulted in ESF Actuations.Personnel Counseled & Trained & EDG Control Circuit Wire repaired.W/940419 Ltr ML20046D5941993-08-18018 August 1993 LER 93-006-00:on 930721,determined That Valves Could Not Be Closed by Use of Normal Motive Power Due to Inadequate Procedural Controls Resulting in Valve Actuators Being Set Up Improperly.Isolated Affected penetration.W/930818 Ltr ML20045H7441993-07-0909 July 1993 LER 93-012-00:on 930615,automatic Reactor Scram & Isolation of Inboard Group 2 PCIS Valves Occurred.Caused by Loose Packing Nut on Instrument Isolation Valve.Valve Repaired & Similar Installations on Units checked.W/930709 Ltr ML20045B0371993-06-10010 June 1993 LER 93-009-00:on 930514,scram Occurred When Mode Switch Moved to Run Position Due to Blown Fuses in Rps.Procedures 52PM-B21-005-1S,52PM-B21-005-2S & 52GM-MEL-007-0S Revised. W/930610 Ltr ML20045B0401993-06-10010 June 1993 LER 93-010-00:on 930514,unplanned ESF Actuation Occurred Due to Less That Adequate Procedures.Procedures 34SV-B21-001-1S & 34SV-B21-001-2S, MSIV Closure Instrument Functional Test revised.W/930610 Ltr ML20045B0761993-06-10010 June 1993 LER 93-011-00:on 930521,partial Group 1 Primary Containment Isolation Sys Actuation Occurred Due to Component Failure. MSLRM Returned to Svc,Failed electro-pneumatic Control Valve in MSIVs replaced.W/930610 Ltr ML20045B7111993-06-10010 June 1993 LER 93-005-00:on 930521,unplanned Insertion of Manual Scram Initiated Due to Personnel Error.Personnel Involved Temporarily Removed from License Duties & Being Subjected to Formal discipline.W/930610 Ltr ML20045A2121993-06-0303 June 1993 LER 93-008-00:on 930505,determined That B Train of SBGT Sys Had Been Inoperable.Caused by Procedure Error.C/As Included Bringing Missed Surveillances Up to Date,Revising Procedures & Counselling personnel.W/930603 Ltr ML20044F6021993-05-21021 May 1993 LER 93-007-01:on 930504,unplanned ESF Actuations Occurred. Caused by Inappropriate Jumper Placement by Plant Engineer. Personnel Performing LSFTs Made Aware of Event & Instructed Not to Install Jumpers on Relay Contact arms.W/930521 Ltr ML20044F5851993-05-18018 May 1993 LER 93-004-00:on 930419,isolation Valve Unexpectedly Closed While Trip Unit Was Tested.Cause for Valve Closing Undetermined.Logic of Trip Unit Correctly Configured to Prevent Closing.No Corrective Actions taken.W/930518 Ltr ML20044D5931993-05-15015 May 1993 LER 93-005-00:on 930414,fuse 1D11-A-f14B Blew,Resulting in Initiation of Train B of Both Standby Treatment Sys Units & Isolation of Damper B of Both Secondary Containments.Blown Fuse & Several Relays in Logic Replaced ML20044D4881993-05-14014 May 1993 LER 93-004-00:on 930414,unplanned ESF Sys Actuation Occurred When LPCI Valve Automatically Reclosed.Caused by Inadvertent Grounding of Logic Circuit,Resulting in Blown Fuse.Fuse Replaced & Operating Order Issued ML20044D1111993-05-10010 May 1993 LER 93-003-00:on 930412,determined That Monthly Operability Test for DG 1B Not Performed During Required Performance Window on 930328.Caused by Personnel Error.Surveillance Coordinator Aware of causes.W/930510 Ltr ML20044C9891993-05-0303 May 1993 LER 93-003-00:on 930407,scram Time Testing on All Control Rods Not Completed Prior to Exceeding 40% Rated Thermal Power.Caused by Personnel Error.Personnel Counseled & Procedures Will Be revised.W/930503 Ltr ML20024G6961991-04-25025 April 1991 LER 91-007-00:on 910326,unknown Inadequacy in Jumper Connection Results in Scram During Surveillance in Cold Shutdown.Cause Unknown.Functional Test Completed & Surveillance Procedure revised.W/910422 Ltr ML20024G7401991-04-24024 April 1991 LER 91-008-00:on 910327,main Steam Isolation Valve Local Leak Rate Test Failed Due to Normal Equipment Wear Resulting in Degradation of Valve Seating Surfaces.Valves Repaired & retested.W/910424 Ltr ML20029B0691991-03-0505 March 1991 LER 91-002-00:on 910203,partial Outboard Group 2 Primary Containment Isolation Sys Isolation Signal Resulted in Closure of Containment Isolation Valves.Caused by Failed Relay Coil.Coil replaced.W/910301 Ltr ML20029B0621991-02-26026 February 1991 LER 91-001-00:on 910129,determined That Setpoints for Condensate Storage Tank Level Switches Not Set to Initiate Required Transfer When 10,000 Gallons Water Available.Caused by Inadequate Documentation.Setpoints raised.W/910226 Ltr ML20028H8431991-01-27027 January 1991 LER 90-024-00:on 901228,pretreatment Monitoring Station Offgas Samples Not Collected & Analyzed within 4 H of Increased Fission Gas Release.Caused by Misinterpretation of Tech Specs.Personnel instructed.W/910125 Ltr ML20044A6411990-06-22022 June 1990 LER 90-011-00:on 900601,full Reactor Protection Sys Actuation Occurred When Mode Switch Moved to Run Position, Resulting in Scram Signal on MSIVs Less than 90% Open.Caused by Personnel Error.Individual counseled.W/900622 Ltr ML20043G7111990-06-15015 June 1990 LER 90-004-00:on 900521,personnel Error & FSAR Deviation Occurred & Resulted in Tech Spec Violation.Procedure 62CI-OCB-031-OS Incorrectly Directed Personnel to Periodically Open Airlock Doors.Memo issued.W/900615 Ltr ML20043G7141990-06-15015 June 1990 LER 90-009-00:on 900522,determined That Requirements of Tech Spec 3.14.2,Actions 105 & 107 Not Met.Caused by Inadequate Procedure.Normal Range Monitoring Sys Restored to Operable Status & Procedure 64CH-SAM-005-OS revised.W/900615 Ltr ML20043G7581990-06-0808 June 1990 LER 90-001-01:on 900112,component Failure & Inadequate Design Caused Group I Isolation & Scram W/Main Steamline Isolation Valves Less than 90% Open.Root Isolation Valves Replaced W/New Type of valve.W/900608 Ltr ML20043C7281990-05-31031 May 1990 LER 90-008-00:on 900505,determined That Reactor Vessel Head Vent Valves 1B21-F004 & 1B21-F005 Closed Contrary to Tech Spec 3.7.C.2.a(2) Requirements.Caused by Cognitive Personnel Error.Reactor Vessel Head Vent Valves reopened.W/900531 Ltr ML20043A5091990-05-14014 May 1990 LER 90-006-00:on 900418,discovered That Wiring Error Existed in Junction Box Leading to Strip Recorder That Resulted in Inadequate Tech Spec Surveillance.Caused by Personnel Error. Wiring Error Corrected & Personnel counseled.W/900514 Ltr ML20043A5131990-05-14014 May 1990 LER 90-007-00:on 900419,determined That Errors in Calculations for Measuring Feedwater Flow Resulted in Nonconservative Calibr of Flow Transmitters.Caused by Error in Design Calculation.Transmitters recalibr.W/900514 Ltr ML20042E6851990-04-27027 April 1990 LER 90-003-00:on 900328,reactor Scram & Group II Containment Isolation Occurred.Caused by Inadequate Procedure.Procedure Will Be Changed to Require Instruments to Be Pressurized to Process Pressure Before Valved Into svc.W/900423 Ltr ML20042E6841990-04-27027 April 1990 LER 90-005-00:on 900329,safety Relief Valves Experienced Setpoint Drift in Excess of Tolerance.Caused by corrosion- Induced Bonding of Surface Between Pilot Valve Disc & Seat. Valves refurbished.W/900424 Ltr ML20012D8861990-03-19019 March 1990 LER 99-004-00:on 900219,trip Setpoint for Isolation of Liquid Radwaste Effluent Line on Low Dilution Flow Not Set Correctly.Caused by Inadequate Procedure.Procedure Revised temporarily.W/900319 Ltr ML20012C2891990-03-12012 March 1990 LER 90-003-00:on 900212,determined That Surveillance Procedures for Monthly Functional Testing of Drywell High Pressure Instrumentation Logic Channels Less than Adequate. Caused by Personnel Error.Procedures revised.W/900312 Ltr ML20011F4291990-02-26026 February 1990 LER 90-002-00:on 900131,discovered That Functional Test of Turbine Stop Valve Position Limit Switches Not Performed. Caused by Personnel Error When Writing Recent Rev.Rev to Procedure 34SV-C71-001-1S/2S written.W/900226 Ltr ML20006E2891990-02-0707 February 1990 LER 90-001-00:on 900112,reactor Scrammed Because MSIVs Were Less than 90% Open.Caused by Component Failure & Configuration of Condenser Vacuum Sensing Lines & Instruments.Valves replaced.W/900207 Ltr ML20006E0111990-02-0606 February 1990 LER 90-002-00:on 900114,RWCU Experienced High Differential Flow,Indicating Possibility of Leak in Sys.Caused by Component Failure & Less than Adequate Mounting for Relay. Relay Replaced W/Time Delay relay.W/900206 Ltr ML20006A8881990-01-22022 January 1990 LER 90-001-00:on 900104,HPCI Pump Declared Inoperable Due to Rated Flow Not Maintained During Surveillance Testing. Caused by Component Failure.Defective Resistor Replaced & Procedure 34SV-E41-002-1S performed.W/900122 Ltr ML20005E6541990-01-0202 January 1990 LER 89-010-00:on 891204,determined That Plant Was Not Fully Meeting Surveillance Requirements of Tech Spec Table 4.3.6.4-1,item 10.b.Caused by Inadequate Procedure.Recorder Calibr Steps to Be Removed from procedure.W/900102 Ltr ML20005E1851989-12-27027 December 1989 LER 89-009-00:on 891129,reactor Protection Sys Actuation Occurred from Scram Discharge Vol High Level Condition. Caused by Equipment Failure.Backup Temporary Air Compressor Placed Into Svc & Blown Fuse replaced.W/891227 Ltr ML20005E5131989-12-22022 December 1989 LER 89-017-00:on 891128,discovered That Efficiency Factors Used for Old Liquid Radwaste Discharge Radiation Monitors Incorrect.Caused by Personnel Not Incorporating Updated Efficiency Factor Into Sys software.W/891222 Ltr ML19332F8691989-12-14014 December 1989 LER 89-018-00:on 891114,sys High Differential Flow Condition Occurred Causing Actuation of Primary Containment Isolation Sys Valve Group 5 Logic Resulting in Closure of RWCU Valve. Caused by Personnel Error.Personnel counseled.W/891214 Ltr ML19332E6141989-11-30030 November 1989 LER 89-016-00:on 891103,discovered That Procedures 57SV-C51-001-1/2S Did Not Fully Test Rod Block Monitor Function.Caused by Procedural Deficiency.Limiting Condition for Operation Initiated & Procedure revised.W/891130 Ltr ML19332D8791989-11-29029 November 1989 LER 89-008-00:on 891102,RWCU Sys Experienced Partial Primary Containment Isolation Sys Group 5 Isolation Involving Valve 2G31-F004.Caused by Component Failure of Relay 2G31-R616D. Relay replaced.W/891129 Ltr ML19324C3271989-11-0808 November 1989 LER 89-014-00:on 891010,primary Containment Isolation Sys Group 5 Isolation Occurred Due to Opening of Valve 1G31-D002A.Caused by Personnel Error.Personnel Counseled & Memo Issued Re Confirming commands.W/891108 Ltr ML19325F1781989-11-0606 November 1989 LER 89-015-00:on 891009,diesel Generator 1R43-S001B Failed to Start Manually During Monthly Generator Test.Caused by Personnel Error & Incorrect Model Number Assigned to Pump. Pump Replaced & Oil Drained from cylinders.W/891106 Ltr ML19332B6191989-10-31031 October 1989 LER 89-013-00:on 891003,RWCU Sys Valve 1G31-F020 Closed, Rendering Inservice Reactor Coolant Monitor Inoperable. Caused by Cognitive Personnel error.In-line Conductivity Surveillance Initiated & Personnel counseled.W/891031 Ltr ML19325E6911989-10-31031 October 1989 LER 89-012-00:on 891003,plant Operators Received Indication That RWCU Sys Experiencing High Differential Flow Which Resulted in Isolation of Primary Containment Isolation Sys Valves.Caused by Component failure.W/891031 Ltr ML19327B3281989-10-23023 October 1989 LER 89-007-00:on 890926,four Safety Relief Valves Had Exhibited Drift in Mechanical Lift Setpoints in Excess of 3% Tolerance Specified by Inservice Testing Requirements.Root Cause Being Investigated.Valves refurbished.W/891023 Ltr ML19327B2991989-10-23023 October 1989 LER 89-006-00:on 890926,Procedure 34SV-SUV-019-2S, Surveillance Checks Did Not Fully Implement Requirements of Tech Spec Table 4.3.2-1.Caused by Personnel Error. Personnel Counseled & Procedure revised.W/891023 Ltr ML20024F4081983-09-0101 September 1983 LER 83-079/03L-0:on 830809,main Steam Line & Reactor Water Sample Valve Relay 1A71-K7A Determined Operating in Degraded Mode.Caused by Component Failure.Coil & Contacts Replaced. W/830901 Ltr ML20024F3341983-09-0101 September 1983 LER 83-064/03L-0:on 830811,during post-maint Review of DCR 83-76 Determined Torus Vent Valves Instrument Air Piping Returned to Svc W/O Performance of HNP-6907.Caused by Personnel oversight.W/830901 Ltr 1994-05-09
[Table view] Category:RO)
MONTHYEARML20029E2071994-05-0909 May 1994 LER 94-004-00:on 940416,discovered That Surveillance Frequency for Sp 34SV-SUV-008-1S Not Correct for Seven Primary Containment Vent & Purge Valves Due to Personnel Error.Surveillance Brought Up to date.W/940509 Ltr ML20029C8681994-04-25025 April 1994 LER 94-003-00:on 940329,automatic Reactor Shutdown Occurred Due to Trip of Main Turbine.Caused by Loss of Main Generator Field Excitation.Damaged Main Generator Exciter Rotor replaced.W/940425 Ltr ML20029C6981994-04-19019 April 1994 LER 94-002-00:on 940325,personnel Error Resulted in ESF Actuations.Personnel Counseled & Trained & EDG Control Circuit Wire repaired.W/940419 Ltr ML20046D5941993-08-18018 August 1993 LER 93-006-00:on 930721,determined That Valves Could Not Be Closed by Use of Normal Motive Power Due to Inadequate Procedural Controls Resulting in Valve Actuators Being Set Up Improperly.Isolated Affected penetration.W/930818 Ltr ML20045H7441993-07-0909 July 1993 LER 93-012-00:on 930615,automatic Reactor Scram & Isolation of Inboard Group 2 PCIS Valves Occurred.Caused by Loose Packing Nut on Instrument Isolation Valve.Valve Repaired & Similar Installations on Units checked.W/930709 Ltr ML20045B0371993-06-10010 June 1993 LER 93-009-00:on 930514,scram Occurred When Mode Switch Moved to Run Position Due to Blown Fuses in Rps.Procedures 52PM-B21-005-1S,52PM-B21-005-2S & 52GM-MEL-007-0S Revised. W/930610 Ltr ML20045B0401993-06-10010 June 1993 LER 93-010-00:on 930514,unplanned ESF Actuation Occurred Due to Less That Adequate Procedures.Procedures 34SV-B21-001-1S & 34SV-B21-001-2S, MSIV Closure Instrument Functional Test revised.W/930610 Ltr ML20045B0761993-06-10010 June 1993 LER 93-011-00:on 930521,partial Group 1 Primary Containment Isolation Sys Actuation Occurred Due to Component Failure. MSLRM Returned to Svc,Failed electro-pneumatic Control Valve in MSIVs replaced.W/930610 Ltr ML20045B7111993-06-10010 June 1993 LER 93-005-00:on 930521,unplanned Insertion of Manual Scram Initiated Due to Personnel Error.Personnel Involved Temporarily Removed from License Duties & Being Subjected to Formal discipline.W/930610 Ltr ML20045A2121993-06-0303 June 1993 LER 93-008-00:on 930505,determined That B Train of SBGT Sys Had Been Inoperable.Caused by Procedure Error.C/As Included Bringing Missed Surveillances Up to Date,Revising Procedures & Counselling personnel.W/930603 Ltr ML20044F6021993-05-21021 May 1993 LER 93-007-01:on 930504,unplanned ESF Actuations Occurred. Caused by Inappropriate Jumper Placement by Plant Engineer. Personnel Performing LSFTs Made Aware of Event & Instructed Not to Install Jumpers on Relay Contact arms.W/930521 Ltr ML20044F5851993-05-18018 May 1993 LER 93-004-00:on 930419,isolation Valve Unexpectedly Closed While Trip Unit Was Tested.Cause for Valve Closing Undetermined.Logic of Trip Unit Correctly Configured to Prevent Closing.No Corrective Actions taken.W/930518 Ltr ML20044D5931993-05-15015 May 1993 LER 93-005-00:on 930414,fuse 1D11-A-f14B Blew,Resulting in Initiation of Train B of Both Standby Treatment Sys Units & Isolation of Damper B of Both Secondary Containments.Blown Fuse & Several Relays in Logic Replaced ML20044D4881993-05-14014 May 1993 LER 93-004-00:on 930414,unplanned ESF Sys Actuation Occurred When LPCI Valve Automatically Reclosed.Caused by Inadvertent Grounding of Logic Circuit,Resulting in Blown Fuse.Fuse Replaced & Operating Order Issued ML20044D1111993-05-10010 May 1993 LER 93-003-00:on 930412,determined That Monthly Operability Test for DG 1B Not Performed During Required Performance Window on 930328.Caused by Personnel Error.Surveillance Coordinator Aware of causes.W/930510 Ltr ML20044C9891993-05-0303 May 1993 LER 93-003-00:on 930407,scram Time Testing on All Control Rods Not Completed Prior to Exceeding 40% Rated Thermal Power.Caused by Personnel Error.Personnel Counseled & Procedures Will Be revised.W/930503 Ltr ML20024G6961991-04-25025 April 1991 LER 91-007-00:on 910326,unknown Inadequacy in Jumper Connection Results in Scram During Surveillance in Cold Shutdown.Cause Unknown.Functional Test Completed & Surveillance Procedure revised.W/910422 Ltr ML20024G7401991-04-24024 April 1991 LER 91-008-00:on 910327,main Steam Isolation Valve Local Leak Rate Test Failed Due to Normal Equipment Wear Resulting in Degradation of Valve Seating Surfaces.Valves Repaired & retested.W/910424 Ltr ML20029B0691991-03-0505 March 1991 LER 91-002-00:on 910203,partial Outboard Group 2 Primary Containment Isolation Sys Isolation Signal Resulted in Closure of Containment Isolation Valves.Caused by Failed Relay Coil.Coil replaced.W/910301 Ltr ML20029B0621991-02-26026 February 1991 LER 91-001-00:on 910129,determined That Setpoints for Condensate Storage Tank Level Switches Not Set to Initiate Required Transfer When 10,000 Gallons Water Available.Caused by Inadequate Documentation.Setpoints raised.W/910226 Ltr ML20028H8431991-01-27027 January 1991 LER 90-024-00:on 901228,pretreatment Monitoring Station Offgas Samples Not Collected & Analyzed within 4 H of Increased Fission Gas Release.Caused by Misinterpretation of Tech Specs.Personnel instructed.W/910125 Ltr ML20044A6411990-06-22022 June 1990 LER 90-011-00:on 900601,full Reactor Protection Sys Actuation Occurred When Mode Switch Moved to Run Position, Resulting in Scram Signal on MSIVs Less than 90% Open.Caused by Personnel Error.Individual counseled.W/900622 Ltr ML20043G7111990-06-15015 June 1990 LER 90-004-00:on 900521,personnel Error & FSAR Deviation Occurred & Resulted in Tech Spec Violation.Procedure 62CI-OCB-031-OS Incorrectly Directed Personnel to Periodically Open Airlock Doors.Memo issued.W/900615 Ltr ML20043G7141990-06-15015 June 1990 LER 90-009-00:on 900522,determined That Requirements of Tech Spec 3.14.2,Actions 105 & 107 Not Met.Caused by Inadequate Procedure.Normal Range Monitoring Sys Restored to Operable Status & Procedure 64CH-SAM-005-OS revised.W/900615 Ltr ML20043G7581990-06-0808 June 1990 LER 90-001-01:on 900112,component Failure & Inadequate Design Caused Group I Isolation & Scram W/Main Steamline Isolation Valves Less than 90% Open.Root Isolation Valves Replaced W/New Type of valve.W/900608 Ltr ML20043C7281990-05-31031 May 1990 LER 90-008-00:on 900505,determined That Reactor Vessel Head Vent Valves 1B21-F004 & 1B21-F005 Closed Contrary to Tech Spec 3.7.C.2.a(2) Requirements.Caused by Cognitive Personnel Error.Reactor Vessel Head Vent Valves reopened.W/900531 Ltr ML20043A5091990-05-14014 May 1990 LER 90-006-00:on 900418,discovered That Wiring Error Existed in Junction Box Leading to Strip Recorder That Resulted in Inadequate Tech Spec Surveillance.Caused by Personnel Error. Wiring Error Corrected & Personnel counseled.W/900514 Ltr ML20043A5131990-05-14014 May 1990 LER 90-007-00:on 900419,determined That Errors in Calculations for Measuring Feedwater Flow Resulted in Nonconservative Calibr of Flow Transmitters.Caused by Error in Design Calculation.Transmitters recalibr.W/900514 Ltr ML20042E6851990-04-27027 April 1990 LER 90-003-00:on 900328,reactor Scram & Group II Containment Isolation Occurred.Caused by Inadequate Procedure.Procedure Will Be Changed to Require Instruments to Be Pressurized to Process Pressure Before Valved Into svc.W/900423 Ltr ML20042E6841990-04-27027 April 1990 LER 90-005-00:on 900329,safety Relief Valves Experienced Setpoint Drift in Excess of Tolerance.Caused by corrosion- Induced Bonding of Surface Between Pilot Valve Disc & Seat. Valves refurbished.W/900424 Ltr ML20012D8861990-03-19019 March 1990 LER 99-004-00:on 900219,trip Setpoint for Isolation of Liquid Radwaste Effluent Line on Low Dilution Flow Not Set Correctly.Caused by Inadequate Procedure.Procedure Revised temporarily.W/900319 Ltr ML20012C2891990-03-12012 March 1990 LER 90-003-00:on 900212,determined That Surveillance Procedures for Monthly Functional Testing of Drywell High Pressure Instrumentation Logic Channels Less than Adequate. Caused by Personnel Error.Procedures revised.W/900312 Ltr ML20011F4291990-02-26026 February 1990 LER 90-002-00:on 900131,discovered That Functional Test of Turbine Stop Valve Position Limit Switches Not Performed. Caused by Personnel Error When Writing Recent Rev.Rev to Procedure 34SV-C71-001-1S/2S written.W/900226 Ltr ML20006E2891990-02-0707 February 1990 LER 90-001-00:on 900112,reactor Scrammed Because MSIVs Were Less than 90% Open.Caused by Component Failure & Configuration of Condenser Vacuum Sensing Lines & Instruments.Valves replaced.W/900207 Ltr ML20006E0111990-02-0606 February 1990 LER 90-002-00:on 900114,RWCU Experienced High Differential Flow,Indicating Possibility of Leak in Sys.Caused by Component Failure & Less than Adequate Mounting for Relay. Relay Replaced W/Time Delay relay.W/900206 Ltr ML20006A8881990-01-22022 January 1990 LER 90-001-00:on 900104,HPCI Pump Declared Inoperable Due to Rated Flow Not Maintained During Surveillance Testing. Caused by Component Failure.Defective Resistor Replaced & Procedure 34SV-E41-002-1S performed.W/900122 Ltr ML20005E6541990-01-0202 January 1990 LER 89-010-00:on 891204,determined That Plant Was Not Fully Meeting Surveillance Requirements of Tech Spec Table 4.3.6.4-1,item 10.b.Caused by Inadequate Procedure.Recorder Calibr Steps to Be Removed from procedure.W/900102 Ltr ML20005E1851989-12-27027 December 1989 LER 89-009-00:on 891129,reactor Protection Sys Actuation Occurred from Scram Discharge Vol High Level Condition. Caused by Equipment Failure.Backup Temporary Air Compressor Placed Into Svc & Blown Fuse replaced.W/891227 Ltr ML20005E5131989-12-22022 December 1989 LER 89-017-00:on 891128,discovered That Efficiency Factors Used for Old Liquid Radwaste Discharge Radiation Monitors Incorrect.Caused by Personnel Not Incorporating Updated Efficiency Factor Into Sys software.W/891222 Ltr ML19332F8691989-12-14014 December 1989 LER 89-018-00:on 891114,sys High Differential Flow Condition Occurred Causing Actuation of Primary Containment Isolation Sys Valve Group 5 Logic Resulting in Closure of RWCU Valve. Caused by Personnel Error.Personnel counseled.W/891214 Ltr ML19332E6141989-11-30030 November 1989 LER 89-016-00:on 891103,discovered That Procedures 57SV-C51-001-1/2S Did Not Fully Test Rod Block Monitor Function.Caused by Procedural Deficiency.Limiting Condition for Operation Initiated & Procedure revised.W/891130 Ltr ML19332D8791989-11-29029 November 1989 LER 89-008-00:on 891102,RWCU Sys Experienced Partial Primary Containment Isolation Sys Group 5 Isolation Involving Valve 2G31-F004.Caused by Component Failure of Relay 2G31-R616D. Relay replaced.W/891129 Ltr ML19324C3271989-11-0808 November 1989 LER 89-014-00:on 891010,primary Containment Isolation Sys Group 5 Isolation Occurred Due to Opening of Valve 1G31-D002A.Caused by Personnel Error.Personnel Counseled & Memo Issued Re Confirming commands.W/891108 Ltr ML19325F1781989-11-0606 November 1989 LER 89-015-00:on 891009,diesel Generator 1R43-S001B Failed to Start Manually During Monthly Generator Test.Caused by Personnel Error & Incorrect Model Number Assigned to Pump. Pump Replaced & Oil Drained from cylinders.W/891106 Ltr ML19332B6191989-10-31031 October 1989 LER 89-013-00:on 891003,RWCU Sys Valve 1G31-F020 Closed, Rendering Inservice Reactor Coolant Monitor Inoperable. Caused by Cognitive Personnel error.In-line Conductivity Surveillance Initiated & Personnel counseled.W/891031 Ltr ML19325E6911989-10-31031 October 1989 LER 89-012-00:on 891003,plant Operators Received Indication That RWCU Sys Experiencing High Differential Flow Which Resulted in Isolation of Primary Containment Isolation Sys Valves.Caused by Component failure.W/891031 Ltr ML19327B3281989-10-23023 October 1989 LER 89-007-00:on 890926,four Safety Relief Valves Had Exhibited Drift in Mechanical Lift Setpoints in Excess of 3% Tolerance Specified by Inservice Testing Requirements.Root Cause Being Investigated.Valves refurbished.W/891023 Ltr ML19327B2991989-10-23023 October 1989 LER 89-006-00:on 890926,Procedure 34SV-SUV-019-2S, Surveillance Checks Did Not Fully Implement Requirements of Tech Spec Table 4.3.2-1.Caused by Personnel Error. Personnel Counseled & Procedure revised.W/891023 Ltr ML20024F4081983-09-0101 September 1983 LER 83-079/03L-0:on 830809,main Steam Line & Reactor Water Sample Valve Relay 1A71-K7A Determined Operating in Degraded Mode.Caused by Component Failure.Coil & Contacts Replaced. W/830901 Ltr ML20024F3341983-09-0101 September 1983 LER 83-064/03L-0:on 830811,during post-maint Review of DCR 83-76 Determined Torus Vent Valves Instrument Air Piping Returned to Svc W/O Performance of HNP-6907.Caused by Personnel oversight.W/830901 Ltr 1994-05-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207E7631999-06-0303 June 1999 Safety Evaluation Concluding That Licensee Proposed Alternative to Use Code Case N-509 Contained in RR-4 Provides Acceptable Level of Quality & Safety.Considers Rev 2 to RR-4 & RR-6 Acceptable HL-5795, Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with ML20206G1691999-05-0404 May 1999 SER Approving Requirements of Istb 4.6.2(b) Pursuant to 10CFR50.55a(a)(3)(ii) HL-5784, Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5766, Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207M1891999-03-11011 March 1999 SER Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Weld HL-5755, Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20206P6981999-01-0707 January 1999 Ehnp Intake Structure Licensing Rept HL-5726, Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20196J4931998-12-0707 December 1998 Safety Evaluation Accepting Proposed Alternatives in Relief Requests RR-V-12,RR-V-15,RR-P-15,RR-V-7,RR-V-12,RR-V-14 & RR-V-15 HL-5714, Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5706, Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With ML20155B6121998-10-28028 October 1998 Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Topical Rept. Rept Acceptable HL-5691, Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20153G2481998-09-24024 September 1998 SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request ML20239A2531998-09-0303 September 1998 SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl HL-5675, Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20238F7131998-08-31031 August 1998 9,change 2 to QAP 1.0, Organization HL-5667, Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998 Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures ML20236W3441998-07-30030 July 1998 Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2 ML20236V5191998-07-28028 July 1998 Safety Evaluation Accepting Proposed License Amend Power Uprate Review ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L1821998-07-0707 July 1998 Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3) HL-5653, Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5640, Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20248B8651998-05-15015 May 1998 Quadrennial Simulator Certification Rept HL-5628, Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant1998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant HL-5604, Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20216B2711998-02-28028 February 1998 Extended Power Uprate Safety Analysis Rept for Ei Hatch Plant,Units 1 & 2 HL-5585, Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5571, Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 11998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 1 HL-5551, Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20199B0561997-12-31031 December 1997 Rev 0 GE-NE-B13-01869-122, Jet Pump Riser Weld Flaw Evaluation Handbook for Hatch Unit 1 HL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 21997-12-31031 December 1997 Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2 HL-5533, Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5514, Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 21997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20212A1981997-10-16016 October 1997 Safety Evaluation Denying Licensee Request for Relief from Implementation of 10CFR50.55a Requirements Re Use of 1992 Edition of ASME Code Section XI for ISI of Containments ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H5311997-10-0101 October 1997 Rev 2 to Unit 1,Cycle 17 Colr ML20211H5251997-10-0101 October 1997 Rev 3 to Unit 1,Cycle 17 Colr 1999-09-30
[Table view] |
Text
- - -
q
%' ' N 7333 L Georgia Power Company Pc1mont Avenue ,
- I- D *' * "W . * = Atlanta. Georg:a 30308 ]
. g; - Telephorie 404 526 3195 '
, Maing Address -
.u% ' 40 inverness Conter Parkway
+, Post Offce Dax 1295
, . Birmingham, Alabama 35201
> i' Telephone 205 868 558J ~
t!e souttwvn m:ke sn tem 1
W. G. Hairston, lit i Senior Vce President l Nuclear Operations 0362V l 1 I November 6, 1989 I s .
O.S.! Nuclear Regulatory Commission '
' ATTN: Document Control Desk .I Hashington, D.C. 20555 1
PLANT HATCH - UNIT 1 :
NRC DOCKET 50-321 ,
i OPERATING LICENSE DPR-57 LICENSEE EVENT REPORT ,
DIESEL GENERATOR 1B INOPERABLE DUE TO INSTALLATION OF INCORRECT PART -
Gentlemen:
In accordance with the requirements of 10 CFR 50.73(a)(2)(i), Georgia Power Company .is submitting the enclosed Licensee Event Report (LER) concerning the inoperability of the IB diesel generator due to the installation of an incorrect part. This event occurred at Plant Hatch -
Units 1 and 2.
Sincerely, 1
g.h., $Y _ ,)}p H. G. Hairston, III 1
JKB/eb
Enclosure:
LER 50-321/1989-015 c: (See next page.)
8911150103 891106 PDR S
ADOCK 05000321 PDC rh tg a
7 I
i E (Jecngia Potver Abbi
'U.S. Nuclear Regulatory Commission November 6, 1989
~
y 'Page_Two e
c: Georaia Power Company Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Nuclear Engineering and Licensing - Hatch GO-NORMS U.S. Nuclear Regulatory Commission. Washinaton. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Region II Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Menning, Senior Resident. Inspector - Hatch r
r 0362V
Peren ses
- U s. NUCLE AA kE1ULATORY COMMISSION
- , APPROvtD OMS NO. 3166-0184 LICENSEE EVENT REPORT (LER) **a'*8"
PACILITY 8eAME Hi DOCKET NUMBER 121 FAGE G PLANT HATCH. UNIT 1 0161010101312 D 1 loFl 017 ftTLS 646 l
D/G 1B INOPERABLE DUE TO INSTALLATI0k 0F WRONG PART GVSNT DATE Ill LER NUMBER (61 REPORT DATE 17) OTHER P ACILITIES INVOLVED (el l MONTH DAY YEAR YEAR N n
- b ",'/,",$ MONTH DAY YEAR F ACILif v N Auks DOCKET NUMBERi$l Plant Hatch Unit 2 0 15101010 31 1 6 16 )
__ _ 1 1 l0 ) l9 89 8l9 0 l1l5 0l0 1l1 0l6 8! 9 0151010iOIIl !
OPE RATING THIS REPORT IS SusMITTIO PUREilANT TO THE REQUIREMENTS OF 10 CPR l- (Casc4 ene er aiore of she fonowmal lit) 8800E m) 20.402(bl 20 406(el 90.731sH2H6,1 73.71M 1 _ _ _
R 20 406teH1Hij 00.381ellt) go.73sH2Hol 73.711s1 nE 1 in i n ==Hua _
= =.im a.nwaH+
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{ 60.73(eH2HI) to.73ieH2HetitHA) JssAl 20 405teH1Hav) 90.73teH2Hal to.73taH2HeillHul N '
20.4086sll11M S0.73sa H2Hieil 50.73(sH2Hal
.lCENSEE CONT Af17 FOR THIS LEtt H2)
NAME TELEPHONE NbMBER ARE A CODE Steven B. Tipos. Manaaer Nuclear Safety and Compliance. Hatch 911I2 31617 I -17 i 81 Sil j COMPLETE ONE LINE FC R EACH COMPONENT FAILURE DESCRIBED IN THl0 REPORT H31 lE CAUS$ system COMPONENT M $ AC. R{ORTAgg
, pq CAUSE sv8 TEM COMPONENT "Aj[ R y,RTpnA E f s s
i i i I i i i i i i I i i i I i l i i I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 114) MONTH DAY YEAR YES (If ven. temple,e txPECTIO SU049tS$1CN DATEI 9*O l l l A T R ACT a , . ,. . . ,,...e-, , , . -,,. , , n .,
L On 10/9/89 at approximately 0900 CDT, Unit 1 was in the Run mode at approximately 2436 CMWT (approximately 100% of rated thermal power) and Unit 2 was in the Refuel modo with all fuel removed from the core. At that time, procedure 34SV-R43-002-23, " Diesel Generator 1B Monthly Test," was being '
performed. While attempting a local, manual start of Diesel Generator (D/G) 1R43-S001B per procedure, the D/G failed to start. Subsequent investigation revealed that approximately two gallons of lubricating oil had accumulated between the pistons of the number 2 cylinder, hydraulically locking the pistons. The oil accumulated as a result of an incorrect type of pump that
, had been installed in the D/L's standby circulating lubricating oil cystem on 9/5/89. Monthly operability testing of D/G 1R43-S001B was completed satisfactorily on 9/15/89, ten days after the incorrect pump was installed and placed in service. Therefore, it is concluded D/G 1R43-S0018 became inoperable at some indeterminate point between 9/25/89 and 10/9/89. The other four D/Gs were not affected by this event.
The root cause of this event is personnel error. The incorrect model number had been assigned to the warehouse stock number for the circulating lubricating oil punip MPL number. Consequeritly, the incorrect type of punp was issued and installed.
Corrective actions for this event include replacing the pump, draining the lubricating oil from the cylinders, visually inspecting the D/G, correcting the model number assigned to the pump's stock number, changing the required functional test for pump repair / replacement, and performing a review of a sample of D/G parts information.
""'IE"~ " - . . . . -
i+ 6 s >
80AC Perm 384.
. U.S. NUCLEA](.E!ULAroRY COMMr5SION l UCENSEE EVENT REPORT (LER) TEXT C NTINUATION . mr.ovco oue wo sino-oio4 EXPIRES: t/31/N f; @LirY agamt (gg DOCMt1 NUMSSR W LOR NUMSER le) PA06 (3) , 1
'E + m. u um ., =g PLANT HATCH, UNIT 1 o l510 lo io i 31211 81 9 0 11 'l 5 -
010 01 2 oF 017 rext ;., - . = w anc e m on PLANT AND SYSTEM. IDENTIFICATION General: Electric -' Boiling Water Reactor
~ Energy' Industry Identification System codes are identified in the text p .as'(EIIS. Code XX). l l . 1 SUMI1ARY OF EVENT L
OnL1 0/9/89 at'approximately 0900 CDT, Unit 1 was in the Run mode at approximately 2436 CMWT (approximately 100% of rated thermal power) and I Unit 2 was'in the Refuel mode with the Reactor Pressure Vessel head ;
removed, the cavity flooded,'and all fuel removed from the core. At '
that time, procedure 34SV-R43-002-25, " Diesel Generator 1B Monthly Test,"'was being performed. While attempting a-local, manual start of Diesel Generator' (D/G, EIIS Code EK) 1R43-S001B per procedure, the D/G
' failed'to start. Subsequent investigation revealed the D/G was-
. hydraulically . locked. Approximately two gallons of lubricating oil had accumulated between the pistons of the number 2 cylinder, locking the j
' pistons. The oil ' accumulated between the pistons as a result of an - 1 incorrect type of pump that had'been installed in the D/G's standby l circulating lubricating oil system (EIIS Code LA) during maintenance ;
activities. performed on 9/5/89. Monthly operability testing of 'D/G l
-1R43-S001B was completed. satisfactorily on 9/15/99, ten days after the
~
'irtorrect pump was installed and placed in service. Therefore, it' is
. concluded D/G-1R43-S0018 became inoperable at some indeterminate point between. 9/25/89 and 10/9/89. The other four D/G's were not affected by
.this event.
The. root cause of this event is personnel error. The incorrect model number had been assigned to the warehouse stock number for the standby circulating' lubricating oil pump (EIIS Code LA). Consequently, the incorrect' type of pump was issued from the warehouse and installed.
. Corrective actions for this event include replacing the pump with the correct type of pump, draining the lubricating oil from the cylinders, V!sually inspecting the D/G, correcting the model number assigned to the pap's stock number, changing the required functional test for pump upir/ replacement, and performing a review of a sample of D/G parts information.
DESCRIPTION OF CVENT On 9/4/89, Maintenance Work Order (MW0) 1-89-3940 was initiated on the Standby Circulating Lubricating 011 Pump,1R43-C006B, for D/G 1R43-S001B (1B D/G) to correct excessive tripping of the supply breaker. On C/5/89, Maintenance personnel found that the cause of the breaker tripping was a defective motor. In removing the defective motor, the pump had to be disassembled. As an alternative to rebuilding the pump, it was decided to replace it with a new pump. Accordingly, Maintenance
esac Poem ageA U.S. NUCLEM 051ULAv0RY COMMISSION
'" M ' LICENSEE EVENT REPORT (LER) TEXT CONTINUATIEN er;.ovto ove' No. am-om s tXPIRES S/31/98 F AClLifV NAMS (H DOCRET NUMBER W LER NUMetR 10) PA05 (31 -
naa
"Sm;',', ' '
5 730 i
PLANT 4ATCH. UNIT 1 015101010 l 31211 81 9 011l5 -
010 01 3 0F 0 17 vm c - . 4 M Nau as = !m .
, personnel completed Stock Material Issue (SMI) requests for a new pump l L - and motor from an on-site warehouse. They obtained the stock numbers '
, corresponding to the. replacement pump and motor for pump 1R43-C006B and l entered that information on the SMI requests. This is per plant ,
l procedure for obtaining parts from the warehouse. Warehouse personnel,' l when given the properly completed and approved SMI requests, located the ;
pump and motor by the given stock numbers and issued them to the :
requesting Maintenance personnel, j l
Maintenance personnel installed the new pump.and motor in the 1B D/G's j standby circulating lubricating oil system. They then performed a 1 functional test of the new pump by verifying no oil flow into the upper )
crankcase per procedure 52PM-R43-013-0S, " Diesel Engine Main and !
Connecting Rod Bearing Inspection." Two maintenance foremen '
independently verified " oil not flowing into upper crankcase." The pump was placed into service.and the 10 D/G was declared operable. Monthly operability testing of the 1B D/G was completed satisfactorily on 9/15/89.
On 10/9/89, Operations personnel began the performance of procedure 34SV-R43-002-25 as part of another scheduled surveillance of the 1B D/G. At approximately 0900 CDT, a local, manual start of the D/G was !
attempted as required by the procedure. The D/G failed to start. l Another attempt was made to start the D/G, but it also was unsuccess ful . The 1B D/G was declared inoperable and Limiting i Conditions for Operation (LCOs) 1-89-477 and 2-89-511 were initiated.
l Maintenance personnel began an investigation of the start failure. They manually rotated the D/G crankshaft, but could produce only 1/4 turn of 1 the crankshaft. This indicated the D/G was hydraulically locked. Upon inspection, it was discovered that approximately two gallons of lubricating oil had accumulated between the opposed pistons of the number 2 cylinder. This locked the pistons and prevented the engine ,
from starting. Approximately 20 gallons of lubricating oil also was I found in the cylinders' exhaust line.
Further investigation revealed pump 1R43-C006B was continuously pumping oil into the upper crankcase. Although the pump is designed to run j continuously, the discharge head developed by the pump should be '
insufficient to allow oil to reach the upper crankcase at oil temperatures above 102*F (normal oil temperature is approximately 135*F; the pump trips if oil temperature drops to 105"F).
The model number of the installed pump was checked and found to be .
incorrec'. The installed pump was a model HL75M rated at 20 gpm rather I than the correct model H75M rated at 10 gpm. The incorrect pump had been installed on 9/5/89 when the pump and motor were replaced. The other four D/Gs were checked and found to have the correct pump installed in their standby circulating lubricating oil systems,
w -
/ GIRCPer.n NSA U.6, NUCLEAR G.ElVLATORY COMMISSION 1
.- LICENSEE EVENT REPORT (LER) TEXT C NTINUATION t
g.
A**. ovio ove No. siso-oio. !
EXP1Rit: 8/31/M l tyCitfTV IsAN4 (16 DocetET 8# UMBER (2) ggn gyuggn qq, paog (3) e ,
n*n "WA':' W, .'n PLANT HATCH, UNIT 1 Tam . ,wei.,,,maa nn o ls lo lo lo l 3l2 l1 8l9 -
0l1l5 -
0l0 0l4 0F 0 l7 I
The stock. number assigned to pump 1R43-C006B showed both pump model numbers, H75M and.HL75M; as appropriate. Both models were stored in the same location in-the warehouse and, because they were both assigned to the same stock number, were consideted acceptable for issuance as a i replacement for pump 1R43-C006B. Both models were tagged with stock number 87120-30918 and MPL number 1R43-C006B. When the pump.and motor were issued on 9/5/89, personnel obtained a pump tagged with the stock number and MPL number given on the SMI request. l
) !
[ The outward appearance of the two pumps is almost identical. The only difference is slight (one end face of the model H75M pump is' recessed 1
approximately one inch, the same end face of the model HL75M pump is almost flush) and is not obvious without a detailed inspection. The overall size and shape of the two pumps are the same, consequently, tne -
model HL75M pump fit into the standby circulating lubricating oil
. sy stem. When the incorrect pump was functionally tested, it was thought that no oil was flowing into the. upper crankcase; however, oil flow is slow (on the order of a few drops per minute) and is difficult to detect.
The lubricating oil was drained from the cylinders and the exhaust lir.e, pump 1R43-C006B was replaced with the correct model (H75M), the 1B D/G was visually inspected with no damage identified, procedure i 34SV-R43-002-1S was successfully performed, and the D/G was declared '
operable at approximately 0140 CDT on 10/12/89. LCOs 1-89-477 and 2-89-511 were terminated.
CAUSE OF THE EVENT '
The root'cause of this event is personnel error. The incorrect model number (HL75M) was assigned to the warehouse stock number for pump 1R43-C006B. .This resulted in model HL75M being tagged for use as Standby Circulating Lubricating Oil oump 1R43-C006B. Consequently, the incorrect model was issued and installed as pump 1R43-C006B on 9/5/89.
It is inconclusive as to when the stock number was incorrectly assigned.
Also contributing to this event was a less than adequate functional test on 9/5/89. The functional test for the new pump was performed using a portion of procedure 52PM-R43-013-0S. It consisted of removing the upper crankcase inspection covers and visually verifying no oil flow into the upper crankcase. This functional test method is less than fully adequate since it is very difficult to detect oil flow of the small magnitude experienced in this event.
t'IIC f orm .1084
.G-LICENSEE EVENT REPORT (LER) TEXT C3NTINUATl3N U S. DeUCLE AR RIOUL' TDRV COMW9510N ;
urRo<eo ous No.sisowio.
(KPIRE$. 8/31/N PACILITT fBAMS til DOCKt." NUhIDER 40 ttR NUhtttR tel l PA06 (3) via "$!.T "'#si PLANT HATCH, UNIT 1 0151010101312 l1 81 9 Ol115 -
010 01 5 0F 0 I7 I TEXT R move apses 4 #seused amo settaenst Mtc penn mW (In l
REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT i This report is required by 10 CFR 50.73'(a)(2)(1) because a condition l existed which was prohibited by the plant's Technicel Specifications.
l I
'Specifically, the 1B D/G was inoperable for an indeterminate period of time between 9/25/89 and 10/9/89 without the appropriate actions being taken as required by Unit 1 Technical Specifications section 3.9.B and .i Unit 2 Technical Specifications section 3.8.1.2. l
'In this event, the 10 D/G was inoperable due to the accumulation of lubricating oil between the pistons of the number 2 cylinder as a result <
of an incorrect type of. pump being installed in the standby circulating !
lubricating oil system. The 1B D/G provides emergency power to Unit 1 or Unit 2 emergency equipment in the event of a loss of offsite power
.(LOSP). Each unit also has two other D/Gs which provide emergency power to redundant emergency equipment in the event of an LOSP.
During the time period in question, 9/25/89 to 10/9/89, Unit 1 was at full power with its other two D/Gs,1R43-S001A and 1R43-S001C operable.
Therefore, two Unit 1 D/Gs were operable and one was not. This l
condition has already been analyzed in Unit 1 Final Safety Analysis '
Report (FSAR) section 8.4.4. A detailed analysis of a loss of coolant accident in conjunction witn an LOSP and the loss of one D/G is given in Unit 1 FSAR section 14.4.3. It was determined that "with one diesel out of service, the remaining diesel generator units are capable of furnishing power for safe shutdown" of Unit'1. Based on existing analysis, it is concluded this event had no adverse impact on Unit l's nuclear safety.
During the same time period, Unit 2 was in the Refuel mode with no fuel in the vessel. Fuel movement was in progress in the Spent Fuel Pool curing a portion of this time. Unit 2 Technical Specifications require at least one D/G to be operable under these conditions. This requirement was not met for an indeterminate period of time from 9/25/89 to 10/1/89 when neither D/G 2R43-S001A (2A) nor D/G 2R43-S001C (20) was operable. D/G 2A was operable from 10/1/89 to 10/9/89.
There are two events which could occur during the Unit 2 conditions stated above: a fuel handling accident and a loss of Spent Fuel Pool inventory. In a fuel handling accident, a spent fuel bundle is dropped during movement resulting in damage to the bundle and releases of gaseous fission products. This, in turn, would result in high radiation levels on the Refueling Floor and automatic start of the Unit 1 and Unit 2 Standby Gas Treatment (SBGT, EIIS Code BH) system filter trains. Even if this event were to occur in conjunction with an LOSP (a highly unlikely event), D/G 1 A and 1C wnuld provide emergency power to the Unit 1 SBGT system. The two Unit 1 SBGT system filter trains are adequate to maintain offsite doses within analyzed limits (see Unit 1 FSAR section 14.4.4 ).
ef * ,p 002C Poem SPSA UO WUCLlia LE;U'.ATORY COMMISSION !
UCENSEE EVENT REPORT (LER) TEXT C2NTINUAT12N - geRono ous wo. mo-oio4 i EXPtRES: t!31/M PACIUTY 88AME m DOClltiNUMSER W LER IdVMSIR 40) . PA06 (3) u*a .
a t = aw.y:
PLANT HATCH. UNIT 1 o is lo l0 lo l 312l1 8l 9 -
0 l1 l 5 -
0l0 01 6 or 0 l 7i nxi s A < - =cu asuunn
. A loss of Spent Fuel Pool invento'y r is an analyzed event (Unit 2 FSAR section 9.1.2.3.1 ) . If such an event were to occur concurrent with an ,
LOSP, emergency power would be needed to power safety related pumps to l 1 replace the lost SFP water. Due to the design of the Spent Fuel Pool, l pumps powered by the 1 A and 1C D/Gs are capable of providing makeup to l
the SFP.
Based on the above, it is concluded this event had no adverse impact on Unit 2's nuclear safety. Had this event occurred with Unit 2 at full power (as Unit 1 was), it would have had no' adverse impact on nuclear safety since the 2A and 2C D/Gs would have been operable (they were out i of service for outage related work which would not have been performed during operation). As on Unit 1, one D/G out of service has been analyzed on Unit 2 (Unit 2 FSAR sections 8.3.1.1.3 and 8.3.1.2.1) and found not to prevent safe unit shutdown. Therefore, this event would not have been worse had it occurred under other conditions.
CORRECTIVE ACTIONS The lubricating oil was drained from the cylinders and the exhaust line, !
pump 1R43-C006B was replaced with the correct model (H75M), the 1B D/G l was visually inspected with no damage found, procedure 34SV-R43-002-1S was successfully performed, and the D/G was declared operable at approximately 0140 CDT on 10/12/89. At that time LC0's 1-89-477 and 2-89-511 were terminated. Additionally, it was verified the correct model pump was installed in the standby circulating lubricating oil systems of the other four D/Gs.
The incorrect model number was deleted from the stock number for the standby circulating lubricating oil pumps and assigned its own unique stock number. The two types of pumps were physically separated. They now are stored in different locations in the warehouse. The tags on the pumps were corrected to reflect the change in stock numbers and intended use.
The affected portion of procedure 52PM-R43-013-0S will be revised to change the steps used as a functional test to make them more meaningful and easier to perform (e.g., verify pump discharge pressure within acceptable range). These changes will be made prior to use of the procedure as a functional test following repair / replacement of the pump.
IIRC Pere 330A- U.S. NUCLE *2 CEGULATORY C0heesem#0ef ,
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LICENSEE EVENT EEPORT (LER) TEXT CENTINtlATl!N APPa veo oue NO.3160 -0104 4 l5h'E EXPIRES: 8131/ND PActL47V $$Atllt til DOCR4T NUtdBER (3) Ltn tsubseta tel PA06 (3) u*a "Mr.;',', ' ' "trf,7 PLANT HATCH, UNIT 1 o ls [o lo lo l 3l 2 l1 819 -
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As of December 1988, stock numbers are assigned by plant Nuclear Procurement Review Group personnel at the time of equipment requisition review while performing procedure 26MC-MTL-006-0S, " Requisition Review for Quality Requirements." However, a review of a 10% sample of U/G l parts on file will be performed by 3/1/90 The review will check the i part records for MPL number, stock number, and model number to ensure I
this information is correct and the part's intended use is properly identified. Further corrective actions (e.g., expanding sample size, 4 physical walkdown of D/Gs) may be taken based on the results of the review.
Since the persons responsible for assignment of the erroneous stock number could not be identified, no disciplinary actions have been taken against any individual.
ADDITIONAL INFORMATION No systems other than the 18 D/G were affected by this event.
No similar events in which a safety system was rendered inoperable due 1 to the installation of a wrong part were noted. I