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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 Georgia fbwer Comphny. ~
,_ .3 L 40 Inv etness Center Parkway
' Cont Ofite Dox 1295 -
humingham. Alabama 35201 .;
. .' ! )
hiephone 205 677-7279
,]
<- J. T. Beckham, Jr. . Georgia '
Power 'i
- Wce President-Naclear . Ps udNvo enrPre, syst.in-Hatch Project .
HL-1580 001449 April 22, 1991 U.S. Nuclear Regulatory Commission ATTN: Document-Control Desk ~
-t
. Washington, D.C. 20555 g PLl14T HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5
-LICENSEE EVENT REPORT UNKNOWN INADEQUACY IN.JVMPER CONNECTION RESULTS IN SCRAM DURING SVRVEIllANCE IN COLD SHUTDOWN Gentlemen:-
In-raccordance with the requirements-of 10.CFR 50.'73(a)(2)(iv), Georgia
- Power . Company- is submitting the enclosed Licensee Event Report (LER) concerning the unanticipated actuation of an Engineered Safety Feature (ESF)l, This event occurred at Plant Hatch - Unit.2.
Sincerely, 7 _-
J. T. Beckham, Jr,
-SWR /ct
Enclosure:
LER 50-366/1991-007 f
.cc:-(See next page.)
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Georgia Power 1 U.S. Nuclear Regulatory Commission April 22, 1991 Page Two l
cc: Gjorai_a Power Comp _am ;
Mr. H. L. Sumner, General Manager - Nuclear Plant l Mr. J. D, Heidt, Manager Engineering and Licensing - Hatch NORMS V.S. Nuclear Reaulatory Commission. Washinaton. D.C.
Mr. K. Jabbour, Licensing Project Manager - Hatch j V.S. Nuclear Reaulatory Commission. Reaica 11 '
Mr. S. D. Ebneter, Regional Administrator Mr. L. D. Wert, Senior Resident Inspector - Hatch 001449
g re ass . , u.s. nucin a aima, o u m .- - ur a n g u iO4 LICENSEE EVENT REPORT-(LER) ,
rACILITT mAME (1) DocEET WUMnER (2) . mr o i .
PIANT HATCH, UNIT 2 - 05000366 !
1 l0Fl 4 TITLE (4).
UWNOW INADEQUACY IN JUMFER CONNECTION RESULTS IN SCRAM SIGNAL DURIfC SURVEILLANCE IN COLD SHUTDOW I EVENT DATE (5) LER NUMBER (6) REPORT DATE (1) oTHER FACILITIES INYoLVED (8)
MogrrH DAT TEAR TEAR SEQ NUM REV MoirrH DAY TEAR FACl!JTT NAMES DOCEET NUMBER (s) 05000 0'3 26 91 91 0 0 7- 00 04 25 91 05000
, , , , Tuts REPORT s susMirrED PuRsuArr To Tut REoutREMEnTs or 10 crR tit) node (9) 4 20.402(b) 20.405(c) ^ 50.73(a)(2)(iv) 7L 11(b)
PowtR 20.40$(a)(1)(1) 50.36(c)(1) 50.13(a)(2)(v) 73.71(c) 20.405(a)(1)(ii) _
50.36(e)(2) _
50.73(a)(2)(v11) _
OTHER (specify in 20.405(a)(1)(iii) 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) Abstract below)
~
20.405(a)(1){lv) 50.73(a)(2)(ii) 50.7)(a)(2)(v111)(B) 20.405(a)(1)(v) 50.73(a)(2)(lill l 50.13(a)(2)(a)
L3CEnsEE cofrrACT Poa TuIs LEn (12i M TELEPHONE NUMBER PJtEA CODE STEVEN B. TIPPS, MANAGER NUCLFAR SAFETY AND COMPLIANCE, HATCH 912 367-7851 COMPLETE oss LinE roR EAcn rAILuRE described in Tuts REPORT (13) cAusE sisTEP coMPonEsrr QF,AC- y,8,73, cAust sTsTEp coMPonEwT QrAC-suPPLEMElfrAL REPORT EEPECTED (14) MOIrrH DAT TEAR EXPECTED sunMission
] TEstif yes,~: complete EXPECTED susMIssion DATE) ] No - DATE (15)
AasTRAct (16)
On-3/26/91, at approximately 1155 CST, Unit 2 was in Cold Shutdown with reactor coolant torperature at approximately 100 degrees Fahrenheit, reactor pressure at
' atmospheric, and all control rods fully inserted. . At_that time, licensed plant y
-operators observed indications that a full scram' signal had been received.
In accordance with-Technical' Specifications requirements _priot-to entering _
Refuel. mode, surveillance procedure 345V-C51-00142S vas being performed:to test the_ Neutron Monitorir.g System (NMS, EIIS Code 1G) noncoincident scram logic. lThis required the placement of electrical-jumpers in the Reactor Protection ~ System (RPS, EIIS Code JE)= logic to ensure a full scram was not-generated while-testing NHS trip functions. In this event, it appears that at least o_ne jumper. failed to maintain contact resulting in- a full scram signal
~
when NHS-signals vere induced.per the surveillance procedure.
The cause of this event could-not.be conclusively determined. However, it appears to be an isolated event resulting from an unknown inadequacy in a jumper connection.
Corrective actions for this event. Include completing the functional test which verified operability of the NHS noncoincident scram logic and revising the surveillance' procedure to reduce the probability of recurrence.
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L(M) q FActLITY mans (1) Docast mmata (2) Lam summa (s) rAos (3) 4 rsAn sto mw arv j PLANT HA1DI, LNIT 2 -- 05000366 91 007- 00 2 0F 4 TsFT
- PLANT AND SYSTEM IDENTIFICATION General Electric - Boiling' Vater Reactor EnergyLIndustry Identification System codes are identified in the text as (EIIS l Code-XX).
DESCRIPTION OF THE EVENT I
On-3/26/91,=at approximately 1155 CJT, licensed plant operators were performing
.a functional test of the Startup Range Neutron Monitors (SRMs) in accordance l vith procedure 34SV-C51-001-2S, "SRM: FUNCTIONAL TEST." This procedure is '
routinely performed to verify'the operability of the SRMs and to test the_ ,
. Neutron _Honitoring System (NMS, EIIS Code IG) noncoincident scram logic, in
-accordance vith1 Technical Specifications requirements, prior to the plant fentering the Refuel mode.- The noncoincident; scram-logic is required when in the
-Refuel mode during core alterations and shutdown margin demonstrations and is made effective via removal of the ' shorting links' from the Reactor Protection-System (RPS,' EIIS Code'JE). logic, Vith the RPS shorting links removed, a trip of any single _NMS instrument,-specifically.any one of the SRMs, Intermediate Range Monitors-(IRMs),,and Average Power Range Monitors (APRMs), vill initiate a -
L. full _ scram ./Lactuating both channels of RPS. logic.
LThe procedure requires-one of the RPS shorting links to be removed so that noncoincident NHS scram logic can be tested.' Then electrical _ jumpers are-
-installed in the RPS logic so thatEtest signals. emanating from the NHS vill affect only one-channel of RPS logic (half scram) at a time.- This allows foru all the noncoincident NHS scram logic to be tested without' generation of a full scram; signal. NHS test signals are then: generated by opening various links in-the logic;to simulate the.various NHS instrument trips. Annunciators and lights are Used to" verify that the RPS channel actuates as expected.
On 3/26/91,111 censed Operations personnel installed. the jumpers on the correct relay terminals as required by the procedure. However, when a link vas opened -
to simulate:an_NHS trip, both channels of RPS actuated, resulting in a full scram: signal rather than a' half scram as expected.
Although all:the control rods vere already fully inserted, actuation of the.
l control rod drive accumulators due to the full ~ scram signal was indicated by the
- romentary overtravel of the control rods and corresponding illumination of drift lights. 'The scram was reset.by approximately 1157 CST.
- CAUSE OF THE EVENT The cause of this event could not be conclusively determined. Electrical jumpers-designed to prevent an NHS' signal from actuating both channels of RPS logic veresinstalled'between the correct connection points but apparently-failed to maintain good-electricalicontact. Therefore, when an NHS trip signal was induced in accordance with the procedure, the trip signal was sensed in two channels of RPS logic rather than_one, resulting in a full scram signal.
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FACILITT NAME (!) luoCF.tf mfmpta (3) 1.ER mmsth (t) Pact (3)
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! : .Am sto mm arv PLANT llA101, tNIT 2 05000366 91 ,007 00 3 0F 4 TSET The investigation into the cause of the event yielded the following information:
1 Immediately after the event, at least one licensed operator insp',eted the l jumper installation and determined the jumpers vere connected rsross the correct poiras.
- 2. The suspect jumpers vere electrically tested by Instrumenta. ton and Control technicians and vere found to be in good condition with no electrical discontinuities or loose connections. i
- 3. The applicable portion of procedure 345V-C51-001-25 vas subjected tv a :
detailed review. It was determined to be correct in that there vere no anomalies in step order, technical detail or equipment identification which could have contributed to the event.
-4.- The-panel.in which the jumpers vere located was inspected and was found to be.in good condition with respect to physical condition, lighting, accessibility and labeling.
- 5. The Nuclear Plant Reliability Data Systen (NPRDS) was queried for information concerning failed electrical jumpers. No events similar to this event vere identified.
- 6. A review of industry experience vas performed. No events similar to this event vere identified.
Therefore, it was concluded that this vas-apparently an iso'ated event resulting from an unknown inadequacy in a jumper connection.
REPORTABILITY ANALYSIS AND SAFETY ASSESSHENT TMs event-is reportable per 10 CFR 50.73(a)(2)(iv) because an Engineered Safety Teature, specifically the Reactor Protection System, experienced an unplanned, automatic actuation.
The Reactor Protection System automatically initiates a reactor scram to ensure the radioactive materials barriers, such as fuel cladding and pressure system boundary, are maintained, and to mitigate the consequences of transients and accidents. The NHS-inputs into the RPS are designed to monitor neutron flux levels and to initiate a rod withdrawal block or=an RPS actuation if neutron flux exceeds preset levels. In the event described in this report,-the RPS actuated per design given the NHS signals which vere induced in the system during a required surveillance.
Based on the above analysis, it is concluded that this event had no adverse impact on nuclear safety.
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TLAk St.Q NUM KEV 007 00 UP 4 PLA!G llATCll, LNIT 2 05000366 91 4 ftXT CORRECTIVE ACTIONS Corrective actions for this event include:
- 1. Completing the SRM functional test. This action is completed.
- 2. Revising procedure 345V-C51-001-25 to require fever jumpers to be installed, it is believed this vill reduce the probability that the event could recur.
This action vill be ampleted prior to returning the unit to operation, currently scheduled for 5/24/91.
- 3. Revieving the feasibility of ut.;ng a different kind of jumper for this procedure, such as a " banana plug" jumper. This reviev vill be completed prior to returning the unit to operation, currently scheduled for 5/24/91.
ADDITIONAL INFORMATION
- 1. Other Systems Affected: No other systems vere affected by this event.
- 2. Previous similar Events: No events were identified in which a jumper installed in the correct location apparently failed to maintain electrical continuity resulting in the actuation of an Engineered Safety Feature (ESF).
- 3. Failed Components Identification: No failed components contributed to this event.
_. -.... - ,