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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
I
- - Georgis Power Company !
, 40 invemess Center Parkway l Post Offce Box 1295 l l
Bkmingham. Nabama 3s201 i' Teleptyxe 205 877-7279 m -
J. T. Beckham, Jr.
Voe Prat, dent - Nuclear Georgia Power l
Hatch Project t*wf swem M.mc system l
May 10, 1993 Docket No. 50-321 HL-3287 005398 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Edwin I. Hatch Nuclear Plant - Unit 1 Licensee Event Report Personnel Error Results in Missed Diesel Generator Technical Specifications Surveillance .
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 a personnel error which resulted in a mi.ssed Diesel Generator Technical -
Specifications surveillance. This event occurred at Plant Hatch - Unit 1.
Sincerely,
/
hl !
[ J. T. Beckham, Jr. /
OCV/cr
Enclosure:
LER 50-321/1993-003 cc: Georcia Power Company Mr. H. L. Sumner, General Manager - Nuclear Plant NORMS i
U.S. Nuclear Reaulatory Commission. Washinoton. D.C.
Mr. K. Jabbour, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission, Recion II Hr. S. D. Ebneter, Regional Administrator Mr. L. D. Wert, Senior Resident Inspector - Hatch ;
170022 l
9305170238 93o510 PDR ADOCK 05000321 , /. l.
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LICENSEE EVENT REPORT (LER) iALiti4Y hAML (ij .aLAti h uMetet (2) FL'-
- i31 PLAhT HATCH, UNIT 1 05000321 1 j Orl5 IITLE (4) l PERSONNEL ERROR RESULTS IN MISSED DIESEL CIMRATUR TECWICAL SPECIFICATIONS SURVEILLANCE EVEhI DATE (5) LER huMBER (6) REPORT DATE (7) OTHER FACILITIES lhv0LVED (8) f M0hTn CAV YEAR VEAR SEQ hum REV MDhTN DAV VEAR FACILITY hAME5 DOCAET huMBER(5) l PIANT HATCH UNIT 2 05000366 !
r
. 04 12 93 93 003 00 05 10 93 05000 THIS aEF AT 15 SusMIiTED PuR5UANT TO INE REQulREMENT5 0F 10 CFR (11) ~!
OPERAT M MODE (9) N 20.402(b) 20.405(c) 50.73(a)(2)(tv)
_ 73.71(b) -
POUER -
20.405(a)(1)(1) -
50.36(c)(1) - 50.73(a)(2)(v) -
73.71(c) l LEVEL 000 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER (Specify in i 20.405(a)(1)(iii) T 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) Abstract below) 20.405(a)(1)(iv) -
50.73(a)(2)(ii) -
50.73(a)(2)(viii)(B) ?
20.405(a)(1)(v) 50.73(a)(2)(111) 50.73(a)(2)(x) l LICEh5E L C0hTALT FOR InI5 LER (12)
HARE TELEPn0ht huMBER kREA CODE STEVEN B. TIPPS, MANACIR NUCIEAR SAFETY AND NNCE. HATCH 912 367-7851 COMPLETE OhE LlhE FOR EACH F AILURE DESCRlbED Ih Inl5 kEP0kT (13)
CAUSE 3YSTEM COMPONENT N U CAUSE SYSTEN COMPONENT MAhUFAC- P RT TUbAC- RgPRT NPRDS TUR(p i
SUPPLEMENIAL REPORT EAPELIED (14) M0hlN DAY YEAR f EXPECTED ,
SUBMIS$10N '
] YES(If yes. complete EXPECTED SUBMISSION DATE) DATE (15)
% NO AB5 TRACT (16) 1
- On 4/12/93 at 1430 CDT, Unit 1 was in its fourteenth refueling outage with all fuel removed from the reactor vessel and Unit 2 was in the Run mode at a power level of 2436 CMWT (100% rated thermal power). At that time, plant personnel -
determined that the monthly operability test for Diesel Generator 1B had not !'
been performed during its required performance window as required by Unit 1 Technical Specifications section 4.9.A.2.a.1 and Unit 2 Technical Specifications i section 4.8.1.1.2.a. The test was due to be performed on 3/28/93 with a late !
date, based upon the allowed 25% grace period, of 4/4/93. It was not performed l at that time because of a scheduling error. Upon determination that the J~
surveillance had been missed, licensed Operations personnel declared Diesel Generator IB inoperable and initiated Limiting Conditions for Operation (LCOs) 1-93-333 and 2-93-230. Operations personnel performed procedure 345V-R43-002-IS, " Diesel Generator 1B Monthly Test," and, at 1945 CDT on .
4/12/93, following successful completion of the test, declared the diesel [
generator operable. LCOs 1-93-333 and 2-93-230 were terminated at that time.
The cause of this event was personnel error. The person responsible for !
scheduling Technical Specifications surveillances, when changing the computer entry for the diesel generator's monthly operability test, caused the test to be rescheduled for a date after 4/4/93. He did not note this unintended change to !
the test due date. Consequently, the operability test was not scheduled and ,
performed as required.
The involved person is aware of the causes of the error and understands how to avoid this in the future.
- ~. .c- y
g m.w u.s. uun uuum weussim uegju gcis LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION '
FACIL117 NAME (2) DOCKET huMBER (2) LER HUMBER (5) PAGE (3) !
VEAR SEQ hum REV 1 PUMr HATCH, UNIT 1 05000321 93 003 00 2 0F 5 IEXT PIANT AND SYSTEM IDENTIFICATION General Electric - Boiling Water Reactor Energy Industry Identification System codes are identified in the text as (EIIS Code XX).
DESCRIPTION OF EVENT On 4/12/93 at 1430 CDT, Unit 1 was in its fourteenth refueling outage with all fuel removed from the reactor vessel and Unit 2 was in the Run mode at a power level of 2436 CMWT (100% rated thermal power). At that time, plant personnel- i determined that the monthly operability test for Diesel Generator (EIIS Code EK)
IB had not been performed as required by Unit 1 Technical Specifications section 4.9.A.2.a.1 and Unit 2 Technical Specifications section 4.8.1.1.2.a. (Diesel Generator 1B can supply emergency power to either Unit 1 4160V essential bus
[EIIS Code EB) 1F or Unit 2 4160V essential bus 2F and therefore is shared by both units. Hence, it is addressed in both unit's Technical Specifications for emergency diesel generators.) Specifically, the test had not been performed during the required performance window of 3/28/93 to 4/4/93. ;
This event was discovered when non-licensed Engineering personnel, compiling plant performance data for March, noted that Diesel Generator 1B had not been run in that month. Since the diesel generator is required to be run monthly, Engineering personnel asked Operations and Technical Specifications surveillance scheduling personnel to determine if the diesel generator monthly operability test had been performed in March. They confirmed that it had not. They further ascertained that the test should have been performed and thus had been missed.
The test had last been performed on 2/25/93 and therefore should have been performed again on 3/28/93. The latest date for performance of the monthly surveillance was 4/4/93, based on the 25% grace period allowed by the Unit 1 and Unit 2 Technical Specifications. However, due to a scheduling error, the monthly operability test was not scheduled to be performed again until 4/14/93.
Consequently, the test was not performed within the allowed surveillance window of 3/28/93 to 4/4/93.
Upon determination that the monthly operability test for Diesel Generator 1B had b3en missed, plant personnel initiated a Deficiency Card and notified licensed shift Operations personnel. Operations personnel declared the diesel generator inoperable as required by the plant's Technical Specifications and initiated Limiting Conditions for Operation (LCOs) 1-93-333 and 2-93'230 as required by plant administrative control procedures. Surveillance procedure 34SV-R43-002-lS, " Diesel Generator 1B Monthly Test," was performed and, at 1945 CDT on 4/12/93, following successful completion of the surveillance, the diesel generator was declared operable. LCOs 1-93-333 and 2-93-230 were terminated at that time. i
.- ~ .- - _ . . .- . -
M. f om OMA U.5. N141AK ekud.AiJO WEahhaUh At'r%Nta Jt) N3 # 4r-0104 (6-89) -
EXPIRES: 4/30/92 i LICENBEE EVENT REPORT (LER)
-~
TEXT CONTINUATION '
FACILITY NAPE (1) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3)
YLAR SEQ hum REW I i
PIANT HATCH. INIT 1 05000321 93 003 00 3 0F 5 !
Itx1 CAUSE OF THE EVENT !
The cause of this event was personnel error. The person responsible for :
scheduling Technical Specifications surveillances, when changing the computer l entry for the diesel generator's monthly operability test, caused the test to be !
rescheduled for a date after 4/4/93. He did not note this unintended change to l the test due date. Consequently, the operability test was not scheduled and l performed as required.
The Surveillance Tracking and Scheduling Computer Program contains four ,
surveillance entries for Diesel Generator 1B: two monthly operability surveillance tests and two semiannual quick start surveillance tests. There are two monthly and two semiannual test entries for Diesel Generator 1B because the i diesel generator is shared between the two units and therefore has separate- I control logic for Unit 1 and Unit 2. The control logic must be tested, along ,
with the diesel generator, during individual monthly and semiannual tests in !
order to meet Unit 1 and Unit 2 Technical Specifications surveillance l requirements. The Technical Specifications allow one diesel generator test to ;
i be performed per surveillance interval provided the diesel is started and run i using the Unit I control logic for one test and the Unit 2 control logic for the l next test. Therefore, there are surveillance computer data base entries to i track the required tests using each unit's diesel generator control logic. l
- In November 1992, following two consecutive start failures, the test frequency l for Diesel Generator 1B was increased to once per week per the requirements of ;
Unit 1 Technical Specifications section 4.9.A.2.a.1 and Unit 2 Technical ;
4 Specifications section 4.8.1.1.2.a. The surveillance tracking and scheduling !
coordinator changed the frequency of the two semiannual quick start surveillance !
test entries to biweekly and staggered their due dates such that a test was ,
i performed using the Unit 1 control logic one week and the Unit 2 control logic l the next week. The Unit 1 and Unit 2 monthly operability surveillance test {
entries were not changed; the scheduling coordinator maintained them up-to-date l using the appropriate test performance dates for the now weekly quick start !
, tests. (All the requirements of the monthly operability test are met or !
exceeded by the semiannual quick start test.) l i
In February 1993, following over 20 consecutive successful starts of Diesel i Generator 1B, the test frequency was returned to normal as allowed by the Unit 1 [
and Unit 2 Technical Specifications. The surveillance scheduling coordinator j returned the frequency of the two quick start surveillance tests to their original frequency. He then manually changed the due dates of the monthly j operability tests based upon the last performances of the applicable quick start !
tests and the requirement to stagger the testing of the control logic. In ,
particular, he changed the due date for the monthly test using the Unit 1 j control logic to 3/17/93 and the monthly test using the Unit 2 control logic to !
4/14/93. These changes were correct and appropriate. i i
l i
l
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- LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMEER (2) LER NUMBER (5) PAGE (3)
YEAR SEQ hum REW P1/cTT HAT W , UNIT 1 05000321 93 003 00 4 0F 5 TITr Subsequently, the scheduling coordinator updated the Unit 1 monthly operability test's surveillance computer data base entry when this test was performed on 2/25/93. Because the data base was updated after the due date for the Unit 1 monthly test had been changed manually to 3/17/93, the surveillance computer software, per its design, automatically changed the next due date for the Unit 1 monthly operability test based on what it perceived as the "early" performance of the surveillance due 3/17/93. This resulted in the computer assigning a due date of 4/25/93 for the next Unit 1 monthly test. Consequently, both monthly operability tests were now scheduled to be performed after 4/4/93 with no testing scheduled for March.
The surveillance scheduling coordinator did not recall that by updating the Unit 1 monthly test with the 2/25/93 performance date, the computer would automatically change the next due date, effectively overriding the 3/17/93 due date he had input manually. This scheduling error was not discovered until after the window for performance of the March diesel generator monthly operability test had expired resulting in a missed Technical Specifications surveillance.
REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT This report is required by 10 CFR 50.73(a)(2)(1) because a condition existed which was prohibited by the plant's Technical Specifications. Unit 1 Technical Specifications section 4.9.A.2.a.1 and Unit 2 Technical Specifications section 4.8.1.1.2.a require that an operability test of Diesei Generator 1B be performed at least once per 31 days. However, the monthly cperability test of the diesel l generator was not performed from 2/25/93 to 4/12/93, a period greater than the required test frequency plus the allowed grace period of 25% of that frequency.
Consequently, a condition prohibited by the plant's Technical Specifications existed.
The diesel generators comprise the onsite, standby emergency AC power supply for i Unit 1 and Unit 2. There is a total of five diesel generator units which supply emergency power to Unit 1 4160V essential busses 1E, 1F, and 1G, and Unit 2 4160V essential busses 2E, 2F, and 2G. Diesel Generators lA and 1C supply Unit t 1 essential busses 1E and 1G, respectively. Diesel Generators 2A and 2C supply Unit 2 essential busses 2E and 2G, respectively. Diesel Generator 1B supplies Unit I essential bus IF or Unit 2 essential bus 2F depending on which unit is in need of emergency AC power. Thus, each unit has two dedicated diesel generators and a third diesel generator shared with the other unit.
In this event, the monthly operability surveillance test of Diesel Generator 1B was not performed within the required surveillar.ce window of 3/28/93 to 4/4/93.
The test was not performed until 4/12/93, eight days late, when it was discovered it had been missed. The test was performed successfully; therefore, it is reasonable to conclude that the diesel generator was in fact i
l l
i 1
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%(6-8'9) -
- LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION -
FACILITY NAME 11) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3) l YEAR SEO hum REW PIANT IWIDI, LNIT 1 05000321 93 003 00 5 0F 5 f TEAT capable of performing its intended function from 4/4/93 to 4/12/93.
Consequently, it is concluded that this event had no adverse impact on nuclear safety. This analysis is applicable to all power levels and operating modes, CORRECTIVE ACTION The surveillance tracking and scheduling coordinator is aware of the causes of the error and understands how to avoid this in the future.
ADDITIONAL INFORMATION No systems other than those mentioned in this report were affected by this event. -
No failed components caused or resulted from this event.
Previous similar events in the last two years in which personnel error has resulted in a missed Technical Specifications surveillance were reported in the following Licensee Event Reports:
50-321/1991-032, dated 1/27/92, 50-321/1992-002, dated 2/6/92, 50-321/1992-008, dated 4/20/92, 50-321/1992-019, dated 8/4/92, 50-366/1991-016, dated 6/28/91, 50-366/1992-006, dated 6/22/92, 50-366/1992-012, dated 8/25/92, 50-366/1992-022, dated 12/7/92, 50-366/1992-024, dated 12/14/92, 50-366/1992-025, dated 12/21/92, 50-366/1993-003, dated 5/3/93. .
Corrective actions for the previous events would not have prevented this event because the circumstances surrounding this event and the personnel involved were unique. None of the previous events involved a scheduling error, or an error of any type, by the surveillance scheduling coordinator.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _