Similar Documents at Hatch |
---|
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
_
o m ap w connv i
.4 333 P@d*13N Ave'1Uf'
=
'e+; Aare 404 L'O 3105
! Maeg A:1:)cc
, sa w.wv cwe raa u, 1- Por Offee Ba W5
. L me;yhyn, A:atsa+a E9
! .. %pna,o ?05 869 SM1 f
,. 1, .
k
- w. c. samon. m we ,, ya m..:w +
j no eum,es HL-1016
[ 000350D March 19, 1990 L U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 L
PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 LICENSEE EVENT REPORT INADE0VATE PROCEDVRE RESVLTS IN INCORRECT __LIOVID i
RADWASTE DILUTION FLOW MONITOR SETP0lf!I 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 condition which existed that was prohibited by the plant Technical Specifications. This event occurred at Plant Hatch - Units 1 and 2.
Sincerely,
- k. . k
- 4. G. Hairston, III JJP/ct
Enclosure:
LER 50-321/1990-004 c: (See next page.) ;
f 9003290049 900319 /
PDR g
ADOCK 05000321 PDC gj
r,a'
-0.
4 I L ($eCHgia[Poiver A bL f-
- c. .
e I U.S. Nuclear Regulatory Commission !
March 19,~1990 !
Page-Two ;
i cc: Georoia Power Comoany ;
c Mr. H. C. Nix, General Manager - Nuclear Plant i L Mr.'J. D. Heidt, Manager Engineering and Licensing - Hatch >
E NORMS ~:
I U.S. Nuclear Reoulatory Commission.- Washinoton. D.C.
Mr. L. P.-Crocker, Licensing Project Manager - Hatch ;
i E U. S. Nuclear Reaulatory Commission. Reaion II !
Mr. S. D. Ebneter, Regional Administrator !
Mr.-J..E. Monning, Senior Resident Inspector.- Hatch ;
i E
s
+
I; t.
l
'h
.r I
i l1
[.
C t.esn age ya Nuckt A; htoutAfonv COasMisseoN
' APPROVID Out to att001ee LICENSEE EVENT REPORT (LER) 5 "N"' $ ' 8' "
8 ACILITY hAmet m DOCS,8 Y Nutett h (Il PAGE W PLANT HATCHe UNIT 1 0 ]s ] o 10 l 0 I 312 l 1 1loFI015 TTLt .4, INADEQUATE PROCEDURE RESULTS IN INCORRECT LIQUID RADWASTE DILUTION FLOW MONITOR SETPOINT tvtNT Daf t tSi Ltm NL9he$th ($1 htPC3T Daf t (71 OTHkh 9 ACILITitt SWVOLVED 181 MO%TM day vtAm vtAR se A6
,p gggy, pay g g g,, ,acig,y v mawas pocetti Nuwstmist PLANT HATCH UNIT 2 o isio ioioi3 i 66 i
~ -
0l2 1l9 9 0 9l 0 0 l 0l 4 0l 0 Ol 3 1l9 9l0 o isto 1 0 1 0 1 i i o,,,,,,,,,, T is neoat is eu TTto eva vANi to Tot novia MiWT o, 20 C,n i ,Cw .. ., . ., ,. ,im MOOL M 4 20 40216) 30 4061 1 6033mH2Hivl T3.71861 m 20 eenleHt Hil $0 36(sHti 90,78taH2Hel 73.?t tel 1101 0t Q 0 a aosNHum
_ o;ags77,rgg 20 em6eH1 Hull to 406(eH1Htvl
[ DO 736 sit 2Hil 60.73mittHoulHAl 35648 60 73teH2Hul to.?3taH2Houinst to acCleH1Hel 6013IeHaHeill DO 73tay2Hal LICENS$t CON 1 ACT FOR THIS Lim till NAME T6LtPHONE NVM9tR ARE A CODt Steven B. Tipps, Manager Nuclear Safety and Compliance, Hatch 9i1:2 3i 6i 7 i -i 7 8i 511 1 COMPLtf t DNt LINE FOR ( ACH COMPONINT 7 AILUAE DISC 9Htt0 IN TMil fitPont (13p
" "I' '
Clust tv4 TIM COMPON E NT
[ TO Pmf CAult t v 5T E M COMPONt NT "h"[g AC nt,Pomias pp t fyf l I I l I I I I I I l l l l l 1 I I I I I I I I I I I I SUPPLEMENT AL 9ttPORT t RPICitO itel MON 1H DAY YiAM 4tS (1f res rom.wte LAPtCTED Sven,tsSION Da tts %O l l l An T . AC T m, .. . .. ., s, . . ,.. - ., , - .y. N-. ,, . ,. ., ii .,
On 2/19/90 at approximately 1400 CST, Unit 1 was in the Cold Shutdown mode and Unit 2 was in the Run mode at an approximate power level of 2436 CMWT (approximately 100% of rated thermal power). At that time, non-licensed plant trip setpoint for the isolation of the liquid radwaste (personnel LRW, Ellsdetermined Code WD) effluent that the line on low dilution flow was not always set per the requirements of Unit 1 Technical Specifications section 3.14.1 and Unit 2 Technical Specifications section 3.3.6.9.
The LRW effluent line isolation valves were set to close if dilution flow decreased to approximately 10,000 gallons per minute (gpm); however, some Liquid Radwaste Discharge Permits required a minimum dilution flow of greater than the 10,000 gpm ;
isolation setpoint. For these LRW discharges, proper dilution flow was established, but the automatic isolation trip setpoint was not set per Technical Specifications requirements. A review of a sample of LRW releases indicated it is highly unlikely any release limits were exceeded.
The cause of this event is an inadequate procedure. Procedure 64CH-RPT-004-05,
" Liquid Effluents: Reports," did not prohibit the issuance of Liquid Radwaste Discharge Permits with a required minimum dilution flow of more than 10,000 gpm or, alternately, did not require the automatic isolation setpoint to be raised prior to the issuance of the discharge permit.
Corrective actions for this event include temporarily revising procedure 64CH-RPT-004-05, issuing an Operating Order to the Radwaste Operators, and scheduling permanent procedure revisions.
su
b._n. _ .... - - -
LICENSEE EVENT REPORT ILEZ) TEXT CONTINUATION uPaovtoom ao mo-noe
. LXPiml&: $/31/5 IACIMTV 184046 til DOCOL81 WutAtth til LIR WURAtth iti PAtt (3) naa **Ru;P "T.?:
PLANT HATCH. UNIT 1 o151010101 3 211 90 -
01014 -
0D 0 12 0' 0 15 mm . = = % mm.v nn 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 On 2/19/90 at approximately 1400 CST, Unit 1 was in the Cold Shutdown mode and Vait 2 was in the Run mode at an approximate power level of 2436 CMWT (approximately 100%
of rated thermal power). At that time, non-licensed plant personnel determined that the trip setpoint for the isolation of the liquid radwaste (LRW, EIIS Code WD) l effluent line on low dilution flow wa> not always set per the requirements of Unit 1 '
l Technical Specifications section 3.14.1 and Unit 2 Technical Specifications section :
3.3.6.9. The LRW effluent line isolation valves were set to close if dilution flow decreased to approximately 10,000 gallons per minute (gpm); however, some Liquid l Radwaste Discharge Permits required a minimum dilution flow of greater than the i
10,000 gpm isolation setpoint. For these LRW discharges, proper dilutien flow was l established, but the automai;ic isolation trip setpoint was not set per Technical Specifications requirements. A review of a sample of LRW releases indicated it is highly unlikely any release limits were exceeded.
l The cause of this event is an inadequate procedure. Procedure 64CH-RPT-004-0S, I
" Liquid Effluents: Reports," did not prohibit the issuance of Liquid Radwaste Discharge Permits with a required minimum dilution flow of more than 10,000 gpm or, alternately, did not require the automatic isolation setpoint to be raised prior to the issuance of the discharge permit.
Corrective actions for this event include temporarily revising procedure 64CH-RPT-004-05, issuing an Operating Order to the Radwaste Operators, and scheduling permanent procedure revisions.
DESCRIPTION OF EVENT On 2/19/90 at approximately 1400 CST, non-licensed plant personnel were investigating a preliminary site Safety Audit and Engineering Review (SAER) audit finding issued on 2/15/90. The preliminary audit finding stated the possibility existed that the low dilution flow isolation trip setpoint for Unit 1 and Unit 2 liquid radwaste (LRW) effluent releases is not always set to ensure the release will terminate if the predefined minimum dilution flow (i.e., the minimum flow listed on ,
the discharge permit) is not maintained. This isolation trip setpoint is required by Unit 1 Technical Specifications section 3.14.1 and Unit 2 Technical Specifications section 3.3.6.9.
, , , , , , , , .r. . cro, i.,,.s m s , m *
~ C 43)
{ ___ _
tellC Poem NSA
- UJ DeuCLE AR R400LiTORY COMattN408d
) * .
UCENSEE EVENT REPORT (LER) TEXT C^NTINUATION maovto ove no si-
. EXPints. 6'31/N P ACILif y hatte m outs 6tt ,sumenta m LER Wunsten ten tact (si 4.a a m. =.n PLANT HATCH. UNIT 1 TEKT is mim, esoso a wumest ses esisseaw Nec poen Jm4 W (174 0 16101010l 31211 91 0 O l0 h -
0b 0h DF 0h The low dilution flow isolation trip setpoint is set to isolate the LRW effluent discharge line if dilution flow falls below approximately 10,000 gallons per minute (gpm). Occasionally, however, the predefined minimum dilution flow, as given on the Liquid Radwaste Discharge Permit for each release, has been greater than 10,000 ppm. In such instances, the low dilution flow isolation trip setpoint was not raised to reflect the higher predefined minimum dilution flow. Consequently, the release would not terminate automatically if dilution flow fell below the higher predefined minimum.
On 2/19/90, plant personnel determined that LRW effluent releases had been made for which the predefined minimum dilution flow was greater than 10,000 gpm. As part of the investightion, over 600 Liquid Radwaste Discharge Permits were reviewed. This represents roughly nine percent of the releases made since 7/1/85 (the date when the Technical Specifications requirements to have automatic isolation capability on low dilution flow became effective). In this sample, 25 cases (eight on Unit 1 and 17 on Unit 2) were found where the Liquid Radwaste Discharge Permit required a minimum dilution flow greater than the low dilution flow isolation setpoint of 10,000 gpm.
For these 25 cases, the renuired minimum dilution flows ranged from 12,000 gpm to 20,000 gpm. In each case documentation existed to demonstrate that the proper dilution flow had been established initially, however, the low dilution flow isolation setpoint had not been set per the requirements of Unit 1 Technical Specifications section 3.14.1 and Unit 2 Technical Specifications section 3.3.6.9.
This was documented on a Deficiency Card as required by plant administrative procedures.
When notified on 2/15/90 that the low dilution flow isolation trip setpoint may not always be set correctly, plant Chemistry and Operations personnel took im'nediate actions to ensure no LRW effluent releases would be made for which the predefined minimum dilution flow was greater then the isolation trip setpoint of 10,000 gpm.
Procedure 64CH-RPT-004-0S was revised temporarily to prohibit the issuance of any Liquid Radwaste Discharge Permit with a required minimum dilution flow of greater than 10,000 gpm. As an additional barrier, Operating Order 00-02-0290-S was issued to the Radwaste Operators prohibiting them from making any releases for which the required minimum dilution flow was greater than 10,000 gpm.
CAUSE OF EVENT The cause of this event is an inadequate procedure. Procedure 64CH-RPT-004-0S did not prohibit the issuance of Liquid Radwaste Discharge Permits with a required minimum dilution flow of more than 10,000 gpm or, alternately, did not require the automatic isolation setpoint to be raised prior to the issuance of the discharge permit.
,a e ,.. n ... .u. . . m, i .n e n -
@ 03)
e menc e.6 anna , u s wucitan atauctony commissio=
"* UCENSEE EVENT REPORT (LER) TEXT C:NTINUATION **raovto ous =o mo+o4
, EXPiRis: l'3Pg6 f aceuty asanet m oDCkti WuuDlh las ggn wouggm ten I a06131 naa "$'@, OfS PLANT HATCH, UNIT 1 op,;o;o;og}2l1 q0 __
0l 0l4 0,0 0;4 or 0l5 REPORTABILITY ANALYSIS AND SAFETY ASSESSIENT This report is required per 10 CFR 50.73(a)(2)(i) because a condition existed that was prohibited by the plant's Technical Specifications. Specifically, the low dilution flow isolation trip setpoint was not always set at its predefined value as required by Unit 1 Technical Specifications section 3.14.1 and Unit 2 Technical Specifications section 3.3.6.9.
The function of the LRW effluent discharge line flow instrumentation is to monitor dilution flow and generate an isolation signal to terminate the LRW release if dilution flow decreases below the trip setpoint. (The flow instrumentation monitors the combined flow of the waste tank being discharged and the dilution water. However, the tank discharge flow is always less than 1% of the dilution water flow; thus, discharge line flow is considered to be dilution flow.) Non-radioactive dilution water, from Turbine Building Service Water (Ells Code KG) and/or the Circulating Water System (EIIS Code SG) is mixed with the small amount (75 gpm or less) of discharge flow from the waste tank prior to the effluent being discharged to the environment (i.e., the Altamaha River). This serves to dilute sufficiently the LRW effluent to ensure the instantaneous discharge limits of Unit 1 Technical Specifications section 3.15.1.1 and Unit 2 Technical Specifications section 3.11.1.1 are not exceeded at the discharge point. The flow monitor generates a flow signal which is fed to a trip unit. If the dilution flow drops below the trip unit's trip setpoint, the trip unit generates an isolation signal and valves 1(2)G11-F184 and 1(2)Gil-F185, Low Level Waste Discharge to Canal, close, thereby terminating the LRW effluent release. The Unit 1 and Unit 2 trip units are set to generate an isolation signal at a flow of approximately 10,000 gpm.
In this event, several examples were found in which the predefined minimum dilution flow was higher than the low dilution flow isolation trip setpoint of approximately 10,000 gpm. Therefore, for those releases, dilution flow could have dropped below the required minimum without the discharge being terminated automatically. However, it is highly unlikely instantaneous discharge limits were exceeded during any of these releases. Dilution flow is verified to be at or above the predefined minime before the release begins and 10 minutes after the release begins. These two flow: are recorded on the dischargo permit. This ensures adequate dilution flow is present. As a matter of good practice, Radwaste Operators periodically verify adequate dilution flow during the release. If dilution flow drops below the required minimum, immediate action is taken to terminate the release. Finally, the calculations used to determine maximum discharge flow, minimum dilution flow, and radiation monitor isolation trip setpoint have a 100% conservatism factor built-in to ensure a large margin exists between what is released and the Technical Specifications release limits.
Based on the above analysis, it is concluded that this event had no adverse impact on the health and safety of the public. Because the power level of the two units would not have changed the nature of the event, it is concluded this event would not have been more severe under other operating conditions, u , , ,,.. .. . . . cm, i,. 4m. *m
GIIIC fs8m 8884 V3 WuC4 tin RESULitomy COneteeggiew UCENSEE EVENT REPORT (LER) TEXT CONTINUATION A*eaovio own wo poo.
EXPIRIS: Sf31W F ACtLITV fu4446 ell DOC 0Lti NutAbth tal LIR NVIASSR 101 PA06 (31 vtaa "tt.ma' W;r:
PLANT HATCH. UNIT 1 0 Is lo lo lo l 312l1 9l 0 -
0 l0 8 -
01 0 01 5 or 0 l5 itxt u -. o .e u.w., m, CORRECTIVE ACTIONS Procedure 64CH-RPT-004-OS was revised temporarily on 2/15/90 to prohibit the issuance of any Liquid Radwaste Discharge Permit with a required minimum dilution flow of greater than 10,000 gpm.
Operating Order 00-02-0290-S was issued to Radwaste Operators on 2/15/90 prohibiting them from making any releases for which the required minimum dilution flow is greater than 10,000 gpm.
Permanent changes to Procedure 64CH-RPT-004-0S and any applicable radwaste system operating procedures are scheduled to be complete by 5/1/90. In the course of the investigation of this event, plant Chemistry management personnel have been made aware of the ongoing necessity for attention to detail to ensure that proper precautions are taken to provide confidence that the LWR effluent line flow instrumentation is set in accordance with Technical Specifications requirements.
ADDITIONALINFORMATI0t{
No plant components other than the LRW effluent discharge line flow instrumentation for Unit 1 and Unit 2 were affected by this event.
l L A previous similar event in which LRW effluent monitoring instrumentation was not set per Technical Specifications requirements was reported in LER 50-321/1989-017, dated 12/22/89. In that event, the isolation setpoint for the LRW effluent discharge line radiation monitoring instrument was found to be less conservative than that required by the Technical Specifications. Corrective actions included installing updated efficiency factors into system software, reviewing a sample of past LRW discharge l permits, revising three procedures, and counseling personnel. These corrective actions I
would not have prevented the event described in this LER because the causes of the two I events were different, different procedures were involved in each event, different instrumentation was involved in each event, and the isolation logic for the involved instrumentation functioned dif ferently.
I eonw ana v.s.crm meanan u m
-