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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 0 Geog'a Power Company - ,
.? 333 P.edmont twenae ,i e/ i Atlada Georoa 30308 l
, ' *I L lek # tone 404 520 3195 e
Ma$ng Address 40 inwrnew center Par >way Post Ofice Box 1295 Onminghami Alat>ama 35201
- Telephone 205 808 5581
. He smbwta c!vct'sc sntem W. G. Hairston, til Somor Vice Pretdont '
- Nucinar Operahons HL-1142 1 000669 '
June 15, 1990 U.S. Nuclear Regulatory Commission i ATTN:' Document Control Desk Washington, D.C. 20555 i
, i PLANT HATCH-- UNITS, 1 2 l NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 ;
LICENSEE EVENT REPORT :
PROCEDURAL DEFICIENCY RESULTS IN :
VIOLATION OF TECHNICAL SPECIFICATION REQUIREMENTS
' 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 procedure deficiency which resulted in a violation .of 1
- Technical Specifications requirements. This event occurred at Plant Hatch - Unit 1.
Should you have any questions in this - regard,' please contact this office at-any time. ,
Sincerely, hM. .
W. G. Hairston, III RDG/JKB/eb s
[
l
Enclosure:
LER 50-321/1990-009 l c:- (See next page.)
L 9006210049 900615 PDR S
ADOCK 05000321 PDC p
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U.S. Nuclear Regulatory Commission June 15, 1990 Page Two c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant 1 Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS U.S. Nuclear Reaulatory Commission. Washinaton. D.C. r Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion 11 ,
Mr. S. D. Ebneter, Regional Administrator Senior Resident Inspector - Hatch 000669
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LICENSEE EVENT REPORT (LER) '
P ACILif Y NAML {1) DOCKS T NUMSL R tyi PAGE G PLANT HATCH, UNIT 1 o I610 Io 1013121 1 1 IDFl 016 ,
titLt ter PROCEDURAL DEFICIENCY RESULTS IN VIOLATION OF TECHNICAL SPECIFICATION RE0VIREMENTS tytNT DAf t IS) LE R hUMBER 161 REPORT DATE (71 OTHtft F ACILif tE8 INVOLVED (8)
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On 5/22/90, at approximately-1355 CDT, Unit 1 was in the Refuel mode with fuel loaded in the core, and Unit 2 was in the Run mode at approximately 2436 CMRT (approximately 100% rated thermal power). At that time, it was determined that the requirements of Unit 1 Technical Specifications, section 3.14.2, Actions 105 and 107, and Unit 2 i Technical Specifications, section 3.3.6.10, Actions 105 and 107, had not been met.
Specifically, with the Main Stack Normal Range Monitoring (NRM, EIIS IL) system inoperable, it was discovered that samples taken to comply with the action statements
-had been drawn from an isolated line and were not representative of main stack ef fl uent. The NRM system became inoperable on 5/19/90 when a fuse blew in the internal power supply for Process Radiation Monitor 1D11-K600B. This caused a . false high-high radiation signal to be generated which resulted in isolation of the normal
. range system and automatic start of the accident range system. A potential did not exist for exceeding gaseous effluent release limits during this event because other instrumentation providing equivalent protection remained operable.
The root cause of this event is a less than adequate procedure. Sampling procedure 64CH-SAM-005-0S did not provide provisions for taking samples with the Main Stack NRM System isolated.
1 Corrective actions for this event include: restoring the NRM system to operable l status, revising procedure 64CH-SAM-005-0S, and providing training to Chemistry '
personnel.
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esRC Formm U.S. 5:UCLE A3 7.41ULATORY COMMl08108d
- LICENSEE EVENT REPORT (LER) TEXT CONTINUAT13N APenovto ove no 3 iso-oio.
EXPIRIS: 8/3tM F ACILITY NAME (1) DOCOLif NUMBER (23 LtR NUMS(R (S) PA04 (31 vtan .
St @[,ak , nt y eya g
N PLANT HATCH, UNIT 1 o15l0l01013l211 910 -
01019 -
0 10 012 0F 0l6 TEXT G eure spece a sovveelt, use espoonef #4C form JABCat il7)
I PLANT AND SYSTEM IDENTIFICATION General Electric - Boiling Water Reactor !
Energy Industry Identification System codes are identified in the text as (EIIS Code-XX).
SUMMARY
OF EVENT I On 5/22/90, at approximately 1355 CDT, Unit 1 was in the Refuel mode with fuel l'oaded in the core, and Unit 2 was in-the Run mode at approximately 2436 CMWT (approximately 100% rated thermal power). At that time, it was determined that the requirements of Unit 1_ Technical Specifications, section 3.14.2, Actions 105 and s 107, and Unit 2 Technical Specifications, section 3.3.6.10, Actions 105 and 107, had !
not been met. Specifically, with the Main Stack Normal Range Monitoring,(NRM, EIIS I
_IL) system inoperable, fit was discovered that samples taken to comply with the i action statemerts had been drawn from an isolated line and were not representative ,;
of main stack effluent. The NRM system became inoperable on 5/19/90 when a fuse i blew in the internal power supply for Process Radiation Monitor 1011-K6008. This caused a false high-high radiation signal to be generated which resulted in j
_j isolation oflthe normal range system and automatic. start of the accident range !
system. A potential did not exist for exceeding gaseous effluent release limits during this event because othar instrumentation providing equivalent protection .l remained operable, j i
The root cause of this event is a less than adequate procedure. Sampling procedure i 64CH-SAM-005-0S did not provide provisions for taking samples with the Main Stack NRM = System isolated. !
l i
Corrective actions for this event include: restoring the _ NRM system to operable status, revising procedure 64CH-SAM-005-0S, and providing training to Chemistry l
personnel. l j
DESCRIPTION OF EVENT !
- On 5/19/90, at approximately 1630 CDT, a fuse blew in the internal power supply for ;
Process Radiation Monitor 1Dll-K600B. The loss of power caused generation of a j false Hi-Hi Radiation Alarm trip signal which resulted in isolation of the NRM. i' system and automatic start of the accident range monitoring system (KAMAN system)
(EIIS Code IL). The. system design is such that both the. normal- and accident range systems share a comon sensing probe in the main stack. When a normal range monitor trips, a. motor operated valve for the normal range system closes and a motor ;
operated valve for the accident range system opens in order to provide adequate flow to the accident range monitor. Thus, the NRM system, common to both units, was inoperable and Operations personnel initiated Limiting Conditions for Operation (LCO's) 1-90-337 and 2-90-154. Deficiency Card 1-90-3384 was critten to document the condition.
NIC f(AM $ceA *U,$. GFOs 1945*S20 50000010 G 7)
NRCFoewee6A U.S. NUCLt131 f.EIULAfoRY CoMMieSloN UCENSEE EVENT REPORT (LER) TEXT CUNTINUATION uezovio ove wo sm-oio4
, EXPIRES: l'3i!aB F ACILITY NAME 11) DOCKET NUMhth til LtR NUMSIRd61 PAOt (31 vtAm -
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PLANT HATCH, UNIT 1 TEXT M more asance de esqrunod, was echaeons/ mc Fam. Jud w tin o is lo lo lo l3l2 l1 9l0 -
0l0l9l- 0p 0l3 oF 0 l6 A qualified replacement fuse was not available from warehouse stock. Consequently, on 5/20/90, at approximately 1630 CDT, daily grab samples and continuous monitoring were initiated in accordance with with Unit 1 Technical Specifications section 3.14.2,
' Actions 105 and 107, and Unit 2 Technical Specifications section 3.3.6.10, Actions 105 and 107.
The sampling was performed in accordance with procedure 64CH-SAM-005-0S, " Gaseous Effluents: Sampling." However, the sampling points called-for in the procedure are '
downstream of the NRM system isolation valve. Since the isolation valve was closed, the grab samples were not representative of main stack effluent. This was not !
immediately apparent to the Chemistry technicians performing the sampling for two reasons. First, the position indications for the isolation valve are on a separate ,
elevation of the main stack building from where the sample is taken and the procedure did not require the technician to verify that a sample flow path exists. Second, sample flow was indicated because leakage existed from a set of quick disconnects giving a misleading indication that the flow was from the sensor probe.
On 5/19/90, chemistry technicians performed a routine changeout of the particulate sampler filter. During reassembly, the quick disconnects apparently were incorrectly installed resulting in leakage. The daily grab samples initiated on 5/20/90 were obtained and analyzed with no deficiencies identified (i.e., flow and activity were !
within nominal ranges). On 5/22/90, chemistry technicians performed another routine changeout of the particulate sampler filter. During this activity, the leakage from the quick disconnects was identified and corrected.
On 5/22/90 at approximately 1355 COT, a chemistry technician reviewing the sample data obtained subsequent to correcting-the leakage noticed the flow rates were unusually low. Upon investigation by a chemistry supervisor it was discovered that the samples had been taken on the isolated normal range sample line and were not representative of main stack effluent. Deficiency Card 1-90-3467 was written to document the condition.
On 5/22/90, at approximately 1430 CDT, the NRM system was returned to operable status .
following installation of a qualified fuse in monitor 1D11-K600B.
CAUSE OF THE EVENT The root cause of this event is a less than adequate procedure. Procedure 64CH-SAM-005-0S did not provide provisions for taking samples with the NRM system i solated. A contributing factor was lack of training on the interaction between the NRM and the Kaman systems.
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- LICENSEE EVENT REPORT (LER) TEXT CONTINUATI';N ma0vio 0ve ao mo-o*
(XPIRES Of31@
f ACILIT V NAME til DOCKET NUM0tR t2l ggg gygggg gg, pagg (3p vi*a '
" n= ==.T PLANT HATCH, UNIT 1 0 l5 ie lo lo l 3l2 l 1 9 l0 -
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0 l0 0 14 oF Ql6 rixt . n -ac i.- == nn REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT ,
This report is required per 10 CFR.73(a)(2)(1) because a condition existed which was prohibited by the plant's Technical Specifications. Specifically, representative Main
-Stack effluent samples were not obtained and analyzed while the Main Stack NRM system was inoperable. These actions are required by Unit 1 Technical Specifications Section 3.14.2, Actions 105 and 107, and Unit 2 Technical Specifications Section 3.3.6.10, !
Actions 105 and 107.
The Main Stack NRM system monitors gaseous effluents released to the enviorns from each unit's Main Condenser Off-Gas system (EIIS Code WF) via the common Main Stack. A gaseous effluent sample is continuously drawn at a fixed rate of flow through an isokinetic probe. The probe is located high enough in the Main Stack to assure representative sampling. The sample passes through two shielded chambers where the 4 radiation level of the effluent is measured by two scintillation detectors which provide inputs to two separate monitoring systems.
Each monitoring system has two upscale setpoints and one downscale setpoint. .Each setpoint initiates an alarm in the Control Room. The upscale alams indicate high and high-high radiation and the downscale alarm indicates instrument trouble. The high radiation alarm is set at a level equivalent to or below the average quarterly release rate limit. The high-high radiation alarm is set at a level equivalent to or below the -
instantaneous release rate limit. This alarm contact also provides the start signal
- for the Kaman system and isolates the NRM system.
l In this event, a false high-high radiation alarm isolated the NRM system. This L rendered it inoperable. Due to procedural problems, representative samples were not obtained and analyzed during the period the system was inoperable as required by l Technical Specifications.
It is concluded that no release limits were exceeded during the time the Main Stack's NRM system was inoperable as each unit's Off-Gas Radiation Monitoring system was operable. These systems are designed to alarm whenever the radioactivity level of the off-gas from the respective unit's Main Condenser reaches the Technical Specifications average release rate limit and to isolate that unit's off-gas releases to the Main Stack- and~ the enviorns to prevent exceeding instantaneous release rate limits with respect to Unit 1 section 3.15.2.7 ad Unit 2 section 3.11.2.7.
Each unit's off-gas radioactivity levels are monitored by two separate monitoring i systems. The first is the pretreatment monitor. This monitor provides input to low, high, and high-high alarm circuits. Both alarm in the Control Room. +
Similarly, the second monitor, the post-treatment monitor, provides input to low, high, high-high, and high-high-high alarm circuits. The lower level upscale trip (high) is used to close the bypass line, open the treatment line, and alarm; the intermediate upscale trip (high-high) is used to alarm; and the upper level upscale trip (high-high-high) is used to isolate the off-gas system outlet valves and alarm.
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NAC PoemetA . - U $ NUCL11R KLIULATDAY COMM8BSIOes'
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION' unovto ove No mo-om o EXPIRES: 8'316 PACILif y asAME til Docetti NUMBE R (2) LER NUMetR (Si PAOC (3) vtan 't $[,',At nE1e y g PLANT HATCH, UNIT 1 01510 l o 10 l 312 l 1 9 l0 -
01019 -
0 10 0 15 oF 016 i itXT I# siste assee 6 mewust ses esMeiwist #4C Awm m W 11M The Off-Gas Radiation Monitoring systems provided adequate effluent sampling and Control Room annunciation _in order to conclude that no release limits were exceeded i during the time the main stack's NRM system was inoperable. Additionally, they provided isolation capability which would have resulted in the termination of gaseous effluent releases via the Main Stack prior to releases exceeding Technical l
- Specifications limits. Based on the above, it is concluded this event did not l adversely affect the public's health and safety. This analysis is applicable to all
- power levels.
?
CORRECTIVE ACTIONS Corrective actions for this event include:
- 1. Chemistry personnel involved were instructed on the interaction between the Main Stack NRM system and the KAf%N system. ;
'2. Procedure 64CH-SAM-005-0S will be revised to provide provisions for sampling of I Main Stack effluents with the NRM system isolated. This revision is expected to l be completed by 7/15/90.
- 3. This event will be included in applicable continuing training lesson plans for i Chemistry personnel. Also, the NRM system lesson plans will be revised per the changes made to 64CH-SAM-005-0S. These actions will be completed by 7/15/90.
d ADDITIONAL-.INFORMATION !
- 1. Previous Similar Events j There have been previous similar events in which less than adequate plant procedures resulted in a violation of the plant's Technical Specifications. These events were reported in the following License Event Reports:
50-321/1990-004, dated 03/19/90 50-321/i989-016, dated 11/30/89 50-321/1989-011, dated 09/26/89 E 50-321/1989-009, dated 09/21/89 l' 50-321/1989-005, dated 04/21/89 50-366/1989-006, dated 10/23/89 l- 50-366/1989-002, dated 03/14/89 l
l The corrective actions for the above events would not have prevented this event l because the involved procedures and Technical Specifications requirements were unique to those events.
l 4
NRC FORM 386A 83,3, ON: 1988-520-559:000TO t9 8h
- , _ ~ _ _ _ __
NHC Fdem*3esA U s. NUCLE A3 ELOULATMY COMMISSION
""' ; ;.. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Arraovio ove ho siso-oio4 e EXPIRES: 8/31/N ,
F ACIL41Y NAME (1) DOCKET NURISOR 131 (gn NUMgga fel PA04 (3)
~~
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'I$U'[' "y'[y*,yn" PLANT HATCH, UNIT 1 o ls lo lo lo l3l2 l1 9l0 -
'0l0l9 - 0F 0 l0 016 0 16 itKT IV more ams k reeamed, one eenheenalNMC Form JnAy l11)
- 2. Failed Component Information j No failed components caused or resulted from this event. Although a blown fuse l
caused the NRM system to isolate,-it did not contribute to the failure to obtain a l representative grab sample. This was the result of an inadequate procedure.
- 3. Other Affected Systems No systems other than the Main Stack's normal range monitoring system were affected by this event.
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NAC FORM 3eca 'U.S. 0708 19 88
. G43)