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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARNRC-94-0025, LER 93-014-01:on 931225,turbine Generator Tripped When Mechanical Overspeed Device Was Activated.Caused by Severe Vibration.Corrective Action:Assessment of Structural Integrity of Pedestal Was conducted.W/940425 Ltr1994-04-25025 April 1994 LER 93-014-01:on 931225,turbine Generator Tripped When Mechanical Overspeed Device Was Activated.Caused by Severe Vibration.Corrective Action:Assessment of Structural Integrity of Pedestal Was conducted.W/940425 Ltr NRC-93-0058, LER 93-008-00:on 930518,discovered That Recorder T50-R802A Could Not Be Considered Operable Per TS 3.3.7.5.Caused by Personnel Error.Lessons Learned Will Be Incorporated Into Training Programs & Plant procedures.W/930618 Ltr1993-06-18018 June 1993 LER 93-008-00:on 930518,discovered That Recorder T50-R802A Could Not Be Considered Operable Per TS 3.3.7.5.Caused by Personnel Error.Lessons Learned Will Be Incorporated Into Training Programs & Plant procedures.W/930618 Ltr NRC-93-0055, LER 93-007-00:on 930420,reactor Tripped on Intermediate Range Monitor Upscale During Reactor Pressure & Feedwater Transient.Caused by Personnel Error.Affected Pressure Transmitters replaced.W/930520 Ltr1993-05-20020 May 1993 LER 93-007-00:on 930420,reactor Tripped on Intermediate Range Monitor Upscale During Reactor Pressure & Feedwater Transient.Caused by Personnel Error.Affected Pressure Transmitters replaced.W/930520 Ltr NRC-91-0058, LER 91-008-00:on 910424,reactor Bldg HVAC Tripped,Div I SGTS Auto Started & Div I Control Ctr HVAC Shifted to Recirculation Mode Due to Mispositioned Trip Output Logic switch.W/910524 Ltr1991-05-24024 May 1991 LER 91-008-00:on 910424,reactor Bldg HVAC Tripped,Div I SGTS Auto Started & Div I Control Ctr HVAC Shifted to Recirculation Mode Due to Mispositioned Trip Output Logic switch.W/910524 Ltr NRC-91-0069, LER 90-012-01:on 901016,HPIC Steam Line Flow Transmitter Failed Due to Short Circuit Across Capacitor Plates.Circuit Boards Replaced & Failure Analysis Performed by Rosemount,Inc.W/910524 Ltr1991-05-24024 May 1991 LER 90-012-01:on 901016,HPIC Steam Line Flow Transmitter Failed Due to Short Circuit Across Capacitor Plates.Circuit Boards Replaced & Failure Analysis Performed by Rosemount,Inc.W/910524 Ltr NRC-91-0055, LER 91-006-00:on 910410,balance of Plant Breaker Opened Causing Reactor Bldg HVAC Isolation.Caused by Component Failures.Nprds Search Conducted for Similiar Problems. W/910510 Ltr1991-05-10010 May 1991 LER 91-006-00:on 910410,balance of Plant Breaker Opened Causing Reactor Bldg HVAC Isolation.Caused by Component Failures.Nprds Search Conducted for Similiar Problems. W/910510 Ltr NRC-91-0004, LER 90-013-00:on 901228,determined That Inadequate Control Could Occur During Air Grab Sampling Process.Caused by Lack of Proper Administrative Controls in Sampling Procedure. Sample Suction added.W/910128 Ltr1991-01-28028 January 1991 LER 90-013-00:on 901228,determined That Inadequate Control Could Occur During Air Grab Sampling Process.Caused by Lack of Proper Administrative Controls in Sampling Procedure. Sample Suction added.W/910128 Ltr NRC-90-0144, LER 90-007-00:on 900829,control Ctr Ventilation Shifted to Recirculation Due to Blown Fuse.Caused by Design Deficiency in Div 1 & 2 Radiation Monitor Trip Circuitry.Design Change Implemented to Eliminate Trip Relay logic.W/900928 Ltr1990-09-28028 September 1990 LER 90-007-00:on 900829,control Ctr Ventilation Shifted to Recirculation Due to Blown Fuse.Caused by Design Deficiency in Div 1 & 2 Radiation Monitor Trip Circuitry.Design Change Implemented to Eliminate Trip Relay logic.W/900928 Ltr NRC-90-0107, LER 88-034-01:on 880831,RWCU Outboard Isolation Valve Closed,Causing RWCU Pumps to Trip.Caused by Loss of Continuity to Relay Due to Deposits Built Up on Surface of Contacts.Relay in Isolation Circuits replaced.W/900622 Ltr1990-06-22022 June 1990 LER 88-034-01:on 880831,RWCU Outboard Isolation Valve Closed,Causing RWCU Pumps to Trip.Caused by Loss of Continuity to Relay Due to Deposits Built Up on Surface of Contacts.Relay in Isolation Circuits replaced.W/900622 Ltr NRC-90-0087, LER 90-002-01:on 900202,determined That Area Radiation Surveillance Procedure 44.080.301 Listed Incorrect Values for Alarm Setpoints.Caused by Unavailable Setpoint Calculations.Procedure revised.W/900608 Ltr1990-06-0808 June 1990 LER 90-002-01:on 900202,determined That Area Radiation Surveillance Procedure 44.080.301 Listed Incorrect Values for Alarm Setpoints.Caused by Unavailable Setpoint Calculations.Procedure revised.W/900608 Ltr NRC-90-0075, LER 87-045-02:on 870908,operator Removed Fuse Which Deenergized Dc Control Power to Bus 72C,resulting in Loss of Power Supply to Swing Bus & to LPCI Loop Selection Valves. Caused by Design Flaw.Design Change initiated.W/900518 Ltr1990-05-18018 May 1990 LER 87-045-02:on 870908,operator Removed Fuse Which Deenergized Dc Control Power to Bus 72C,resulting in Loss of Power Supply to Swing Bus & to LPCI Loop Selection Valves. Caused by Design Flaw.Design Change initiated.W/900518 Ltr NRC-90-0073, LER 90-003-00:on 900410,Div I Reactor Protection Sys Power Supply Failure & Subsequent MSIV Closure.Caused by Coil Burn Up.Relays Replaced & MG Sets Returned to svc.W/900508 Ltr1990-05-0808 May 1990 LER 90-003-00:on 900410,Div I Reactor Protection Sys Power Supply Failure & Subsequent MSIV Closure.Caused by Coil Burn Up.Relays Replaced & MG Sets Returned to svc.W/900508 Ltr NRC-90-0048, LER 89-037-01:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed Prior to Expiration on 891125. Caused by Personnel Error.Procedure revised.W/900322 Ltr1990-03-22022 March 1990 LER 89-037-01:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed Prior to Expiration on 891125. Caused by Personnel Error.Procedure revised.W/900322 Ltr NRC-90-0027, LER 89-034-01:on 891208,two Members of Fire Watch Did Not Complete Assigned Hourly Rounds from 891002-1207 in Reactor & Auxiliary Bldgs.Both Individuals Terminated & Fire Stations Equipped W/Unique Bar code.W/900221 Ltr1990-02-21021 February 1990 LER 89-034-01:on 891208,two Members of Fire Watch Did Not Complete Assigned Hourly Rounds from 891002-1207 in Reactor & Auxiliary Bldgs.Both Individuals Terminated & Fire Stations Equipped W/Unique Bar code.W/900221 Ltr NRC-90-0021, LER 90-001-00:on 900108,annunciator 2D5 Alarmed for Div II ECCS Testability Logic/Power Failure.Caused by Blown Fuse. Fuse Installed During Course of Troubleshooting W/No Subsequent Problems noted.W/900207 Ltr1990-02-0707 February 1990 LER 90-001-00:on 900108,annunciator 2D5 Alarmed for Div II ECCS Testability Logic/Power Failure.Caused by Blown Fuse. Fuse Installed During Course of Troubleshooting W/No Subsequent Problems noted.W/900207 Ltr NRC-90-0019, LER 89-028-01:on 891028,eight Safety Relief Valves Failed Set Pressure Tolerance Test.Cause Under Review by Util & Generically by BWR Owners Group Safety Relief Valve Set Point Drift Committee.Valves Removed & cleaned.W/900131 Ltr1990-01-31031 January 1990 LER 89-028-01:on 891028,eight Safety Relief Valves Failed Set Pressure Tolerance Test.Cause Under Review by Util & Generically by BWR Owners Group Safety Relief Valve Set Point Drift Committee.Valves Removed & cleaned.W/900131 Ltr NRC-90-0018, LER 89-039-00:on 891226,Div I Emergency Equipment Cooling Water & Svc Water Sys Automatically Started Due to Partial Load Shed of Bus 72E.Caused by Personnel Error. Accountability Meeting Held on 900117.W/900125 Ltr1990-01-25025 January 1990 LER 89-039-00:on 891226,Div I Emergency Equipment Cooling Water & Svc Water Sys Automatically Started Due to Partial Load Shed of Bus 72E.Caused by Personnel Error. Accountability Meeting Held on 900117.W/900125 Ltr NRC-90-0008, LER 89-037-00:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed.Caused by Personnel Error. Critique of Event Being developed.W/900119 Ltr1990-01-19019 January 1990 LER 89-037-00:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed.Caused by Personnel Error. Critique of Event Being developed.W/900119 Ltr NRC-90-0007, LER 89-036-00:on 891218,control Room Operator Inadvertently Depressed Closed Push Buttons on Inboard MSIVs A,B & C & Reactor Scram Resulted.Caused by Operator Error.Operator Involved Was Removed from Licensed duties.W/900117 Ltr1990-01-17017 January 1990 LER 89-036-00:on 891218,control Room Operator Inadvertently Depressed Closed Push Buttons on Inboard MSIVs A,B & C & Reactor Scram Resulted.Caused by Operator Error.Operator Involved Was Removed from Licensed duties.W/900117 Ltr ML19354E0971990-01-12012 January 1990 LER 89-038-00:on 891223,reactor Scrammed When Fire Occurred in Vicinity of High Pressure Turbine.Caused by Oil Soaked Inlagging Pads & Ignited When Turbine Casing Heated Up to Oil Flashpoint.Insulation Pads replaced.W/900122 Ltr NRC-90-0005, LER 89-035-00:on 891210,steam Jet Air Ejectors Placed in Svc W/O Required Surveillance Completed & Required Grab Sample Not Started Until 891213.Caused by Personnel Error.Off Gas Sys Operating Procedure Will Be revised.W/900111 Ltr1990-01-11011 January 1990 LER 89-035-00:on 891210,steam Jet Air Ejectors Placed in Svc W/O Required Surveillance Completed & Required Grab Sample Not Started Until 891213.Caused by Personnel Error.Off Gas Sys Operating Procedure Will Be revised.W/900111 Ltr NRC-90-0004, LER 89-030-00:on 891026,Channel C Level 1 & 2 Replacement Transmitter Found to Be Installed Incorrectly & Condition Recognized on 891210,when Level 2 Trip Unit Was Reading Upscale.Caused by Personnel error.W/900109 Ltr1990-01-0909 January 1990 LER 89-030-00:on 891026,Channel C Level 1 & 2 Replacement Transmitter Found to Be Installed Incorrectly & Condition Recognized on 891210,when Level 2 Trip Unit Was Reading Upscale.Caused by Personnel error.W/900109 Ltr NRC-90-0002, LER 89-033-00:on 891207,volt-ohm Meter Connected to Incorrect Terminal,Causing Div II of Emergency Equipment Cooling Water Sys to Actuate.Caused by Personnel Error.Sys Secured & Channel Test Successfully completed.W/900108 Ltr1990-01-0808 January 1990 LER 89-033-00:on 891207,volt-ohm Meter Connected to Incorrect Terminal,Causing Div II of Emergency Equipment Cooling Water Sys to Actuate.Caused by Personnel Error.Sys Secured & Channel Test Successfully completed.W/900108 Ltr NRC-90-0003, LER 89-034-00:on 891208,review of Key Card Transactions Showed That Fire Watch Personnel Missed Assigned Hourly Fire Watch from 891020-1207.Fire Watch Person Discharged.Plan Re Improvement of Fire Watches developed.W/900108 Ltr1990-01-0808 January 1990 LER 89-034-00:on 891208,review of Key Card Transactions Showed That Fire Watch Personnel Missed Assigned Hourly Fire Watch from 891020-1207.Fire Watch Person Discharged.Plan Re Improvement of Fire Watches developed.W/900108 Ltr NRC-89-0261, LER 89-028-00:on 891129,ESF Actuations Occurred During Set Up for Surveillance.Caused by Blown Fuse.Blown Fuse Replaced & Affected Sys Returned to Normal Operation Following Completion of surveillance.W/891228 Ltr1989-12-28028 December 1989 LER 89-028-00:on 891129,ESF Actuations Occurred During Set Up for Surveillance.Caused by Blown Fuse.Blown Fuse Replaced & Affected Sys Returned to Normal Operation Following Completion of surveillance.W/891228 Ltr NRC-89-0260, LER 89-021-01:on 890906,35 of 237 Containment Isolation Valves Exceeded Administrative Allowable Leakage Rate When Tested.Caused by Normal Wear & Degradation During Specified Time Interval.Valves Cleaned & repaired.W/891221 Ltr1989-12-21021 December 1989 LER 89-021-01:on 890906,35 of 237 Containment Isolation Valves Exceeded Administrative Allowable Leakage Rate When Tested.Caused by Normal Wear & Degradation During Specified Time Interval.Valves Cleaned & repaired.W/891221 Ltr NRC-89-0255, LER 89-031-00:on 891120,both Div II Emergency Equipment Cooling Water (EECW) & Emergency Equipment Svc Water Sys Pumps Tripped Immediately.Caused by Inadequacies in Stated Procedures.Procedures revised.W/891220 Ltr1989-12-20020 December 1989 LER 89-031-00:on 891120,both Div II Emergency Equipment Cooling Water (EECW) & Emergency Equipment Svc Water Sys Pumps Tripped Immediately.Caused by Inadequacies in Stated Procedures.Procedures revised.W/891220 Ltr NRC-89-0259, LER 89-017-01:on 890810,new Analysis of Feedwater Line Break Scenario Assumes Failure of Feedwater Startup Control Valve in Open Position.Review of Pipe Break Documentation Conducted.Updated FSAR Change to Be submitted.W/891215 Ltr1989-12-15015 December 1989 LER 89-017-01:on 890810,new Analysis of Feedwater Line Break Scenario Assumes Failure of Feedwater Startup Control Valve in Open Position.Review of Pipe Break Documentation Conducted.Updated FSAR Change to Be submitted.W/891215 Ltr NRC-89-0256, LER 89-022-01:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse C71A-F15B Blew.On 890928, Reactor Bldg HVAC Isolated.Caused by Personnel Error. Procedures Will Be revised.W/891215 Ltr1989-12-15015 December 1989 LER 89-022-01:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse C71A-F15B Blew.On 890928, Reactor Bldg HVAC Isolated.Caused by Personnel Error. Procedures Will Be revised.W/891215 Ltr NRC-89-0258, LER 89-025-00:on 891115,low Level 2 Signal Unintentionally Induced During Reactor Pressure Vessel Hydrostatic Pressure Test.Caused by Personnel Error.Personnel Counseled on Notifying & Coordinating Instrument lineups.W/891215 Ltr1989-12-15015 December 1989 LER 89-025-00:on 891115,low Level 2 Signal Unintentionally Induced During Reactor Pressure Vessel Hydrostatic Pressure Test.Caused by Personnel Error.Personnel Counseled on Notifying & Coordinating Instrument lineups.W/891215 Ltr NRC-89-0251, LER 89-019-01:on 890819,discovered That Div I Recirculation Fan Not Rotating Which Resulted in Decrease in Control Room Air Pressure.Caused by Lack of Lubrication in Bearings. Lubrication Program Improvements evaluated.W/891130 Ltr1989-11-30030 November 1989 LER 89-019-01:on 890819,discovered That Div I Recirculation Fan Not Rotating Which Resulted in Decrease in Control Room Air Pressure.Caused by Lack of Lubrication in Bearings. Lubrication Program Improvements evaluated.W/891130 Ltr NRC-89-0249, LER 89-029-00:on 891023,half Scram Signal Received When Power Was Lost on Reactor Protection Sys Bus B,Resulting in Several ESFs Actuation.Caused by Location of Breaker Operating Switch in High Traffic area.W/891122 Ltr1989-11-22022 November 1989 LER 89-029-00:on 891023,half Scram Signal Received When Power Was Lost on Reactor Protection Sys Bus B,Resulting in Several ESFs Actuation.Caused by Location of Breaker Operating Switch in High Traffic area.W/891122 Ltr NRC-89-0246, LER 89-028-00:on 891020,eight safety-related Valves Failed Set Pressure Test.Cause Under Review.All Valves Removed for Testing Being Refurbished,Cleaned,Retested & Recertified to Be within Plant Accepted tolerances.W/891120 Ltr1989-11-20020 November 1989 LER 89-028-00:on 891020,eight safety-related Valves Failed Set Pressure Test.Cause Under Review.All Valves Removed for Testing Being Refurbished,Cleaned,Retested & Recertified to Be within Plant Accepted tolerances.W/891120 Ltr NRC-89-0244, LER 89-024-00:on 891019,recognized That Secondary Containment Dampers Not Tested as Required by Tech Spec 3.6.5.2.Caused by Operations Personnel Error.Event Critique to Be Included in Required Reading program.W/891120 Ltr1989-11-20020 November 1989 LER 89-024-00:on 891019,recognized That Secondary Containment Dampers Not Tested as Required by Tech Spec 3.6.5.2.Caused by Operations Personnel Error.Event Critique to Be Included in Required Reading program.W/891120 Ltr NRC-89-0194, LER 89-027-00:on 891015,reactor Bldg Hvac,Control Ctr HVAC & Drywell Floor & Equipment Drain Sumps Isolated & Standby Gas Treatment Sys & Noninterrruptalbe Control Air Compressors Started.Caused by Personnel error.W/891114 Ltr1989-11-14014 November 1989 LER 89-027-00:on 891015,reactor Bldg Hvac,Control Ctr HVAC & Drywell Floor & Equipment Drain Sumps Isolated & Standby Gas Treatment Sys & Noninterrruptalbe Control Air Compressors Started.Caused by Personnel error.W/891114 Ltr NRC-89-0193, LER 89-026-00:on 891010,control Ctr HVAC Shifted to Recirculation Mode of Operaton Due to Short Circuit.Caused by Failure of Lamp Filament When Being Tightened.Fuse & Lamp Replaced & Sys Returned to Normal operation.W/891109 Ltr1989-11-0909 November 1989 LER 89-026-00:on 891010,control Ctr HVAC Shifted to Recirculation Mode of Operaton Due to Short Circuit.Caused by Failure of Lamp Filament When Being Tightened.Fuse & Lamp Replaced & Sys Returned to Normal operation.W/891109 Ltr NRC-89-0192, LER 87-045-01:on 870908,fuse Removed Which Deenergized Dc Control Power to Bus 72C & Resulted in Loss of Power Supply to Swing Bus & LPCI Loop Selection Valves.Caused by Design Error.Undervoltage Relay Added & Training held.W/891106 Ltr1989-11-0606 November 1989 LER 87-045-01:on 870908,fuse Removed Which Deenergized Dc Control Power to Bus 72C & Resulted in Loss of Power Supply to Swing Bus & LPCI Loop Selection Valves.Caused by Design Error.Undervoltage Relay Added & Training held.W/891106 Ltr NRC-89-0190, LER 89-023-00:on 890924,personnel Inadvertently Caused Trip of Essential Safety Sys Buses 64B & 64C.Caused by Failure of Personnel Involved to Review Applicable Prints Prior to Performing Test.Event Reviewed w/personnel.W/891024 Ltr1989-10-24024 October 1989 LER 89-023-00:on 890924,personnel Inadvertently Caused Trip of Essential Safety Sys Buses 64B & 64C.Caused by Failure of Personnel Involved to Review Applicable Prints Prior to Performing Test.Event Reviewed w/personnel.W/891024 Ltr NRC-89-0189, LER 89-022-00:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse Blew.On 890928,reactor Bldg HVAC Isolated When Jumper Lifted Per Incorrect Work Plan Instruction.Caused by Personnel error.W/891023 Ltr1989-10-23023 October 1989 LER 89-022-00:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse Blew.On 890928,reactor Bldg HVAC Isolated When Jumper Lifted Per Incorrect Work Plan Instruction.Caused by Personnel error.W/891023 Ltr NRC-89-0186, LER 89-016-01:on 890711,Div 1 of RHR Svc Water Sys Declared Inoperable Due to Low Nitrogen Pressure for Cooling Tower Fan Brake.Caused by Leak in One Hose.Leaking Hose Replaced & Nitrogen Pressure restored.W/891006 Ltr1989-10-0606 October 1989 LER 89-016-01:on 890711,Div 1 of RHR Svc Water Sys Declared Inoperable Due to Low Nitrogen Pressure for Cooling Tower Fan Brake.Caused by Leak in One Hose.Leaking Hose Replaced & Nitrogen Pressure restored.W/891006 Ltr NRC-89-0185, LER 89-021-00:on 890906,local Leak Rate Testing of Containment Isolation Valves & Penetrations Exceeded Tech Spec Limit.Caused by Excessive Containment Isolation Valve Leakage Due to Degradation of valve.W/891006 Ltr1989-10-0606 October 1989 LER 89-021-00:on 890906,local Leak Rate Testing of Containment Isolation Valves & Penetrations Exceeded Tech Spec Limit.Caused by Excessive Containment Isolation Valve Leakage Due to Degradation of valve.W/891006 Ltr 1994-04-25
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MONTHYEARNRC-94-0025, LER 93-014-01:on 931225,turbine Generator Tripped When Mechanical Overspeed Device Was Activated.Caused by Severe Vibration.Corrective Action:Assessment of Structural Integrity of Pedestal Was conducted.W/940425 Ltr1994-04-25025 April 1994 LER 93-014-01:on 931225,turbine Generator Tripped When Mechanical Overspeed Device Was Activated.Caused by Severe Vibration.Corrective Action:Assessment of Structural Integrity of Pedestal Was conducted.W/940425 Ltr NRC-93-0058, LER 93-008-00:on 930518,discovered That Recorder T50-R802A Could Not Be Considered Operable Per TS 3.3.7.5.Caused by Personnel Error.Lessons Learned Will Be Incorporated Into Training Programs & Plant procedures.W/930618 Ltr1993-06-18018 June 1993 LER 93-008-00:on 930518,discovered That Recorder T50-R802A Could Not Be Considered Operable Per TS 3.3.7.5.Caused by Personnel Error.Lessons Learned Will Be Incorporated Into Training Programs & Plant procedures.W/930618 Ltr NRC-93-0055, LER 93-007-00:on 930420,reactor Tripped on Intermediate Range Monitor Upscale During Reactor Pressure & Feedwater Transient.Caused by Personnel Error.Affected Pressure Transmitters replaced.W/930520 Ltr1993-05-20020 May 1993 LER 93-007-00:on 930420,reactor Tripped on Intermediate Range Monitor Upscale During Reactor Pressure & Feedwater Transient.Caused by Personnel Error.Affected Pressure Transmitters replaced.W/930520 Ltr NRC-91-0058, LER 91-008-00:on 910424,reactor Bldg HVAC Tripped,Div I SGTS Auto Started & Div I Control Ctr HVAC Shifted to Recirculation Mode Due to Mispositioned Trip Output Logic switch.W/910524 Ltr1991-05-24024 May 1991 LER 91-008-00:on 910424,reactor Bldg HVAC Tripped,Div I SGTS Auto Started & Div I Control Ctr HVAC Shifted to Recirculation Mode Due to Mispositioned Trip Output Logic switch.W/910524 Ltr NRC-91-0069, LER 90-012-01:on 901016,HPIC Steam Line Flow Transmitter Failed Due to Short Circuit Across Capacitor Plates.Circuit Boards Replaced & Failure Analysis Performed by Rosemount,Inc.W/910524 Ltr1991-05-24024 May 1991 LER 90-012-01:on 901016,HPIC Steam Line Flow Transmitter Failed Due to Short Circuit Across Capacitor Plates.Circuit Boards Replaced & Failure Analysis Performed by Rosemount,Inc.W/910524 Ltr NRC-91-0055, LER 91-006-00:on 910410,balance of Plant Breaker Opened Causing Reactor Bldg HVAC Isolation.Caused by Component Failures.Nprds Search Conducted for Similiar Problems. W/910510 Ltr1991-05-10010 May 1991 LER 91-006-00:on 910410,balance of Plant Breaker Opened Causing Reactor Bldg HVAC Isolation.Caused by Component Failures.Nprds Search Conducted for Similiar Problems. W/910510 Ltr NRC-91-0004, LER 90-013-00:on 901228,determined That Inadequate Control Could Occur During Air Grab Sampling Process.Caused by Lack of Proper Administrative Controls in Sampling Procedure. Sample Suction added.W/910128 Ltr1991-01-28028 January 1991 LER 90-013-00:on 901228,determined That Inadequate Control Could Occur During Air Grab Sampling Process.Caused by Lack of Proper Administrative Controls in Sampling Procedure. Sample Suction added.W/910128 Ltr NRC-90-0144, LER 90-007-00:on 900829,control Ctr Ventilation Shifted to Recirculation Due to Blown Fuse.Caused by Design Deficiency in Div 1 & 2 Radiation Monitor Trip Circuitry.Design Change Implemented to Eliminate Trip Relay logic.W/900928 Ltr1990-09-28028 September 1990 LER 90-007-00:on 900829,control Ctr Ventilation Shifted to Recirculation Due to Blown Fuse.Caused by Design Deficiency in Div 1 & 2 Radiation Monitor Trip Circuitry.Design Change Implemented to Eliminate Trip Relay logic.W/900928 Ltr NRC-90-0107, LER 88-034-01:on 880831,RWCU Outboard Isolation Valve Closed,Causing RWCU Pumps to Trip.Caused by Loss of Continuity to Relay Due to Deposits Built Up on Surface of Contacts.Relay in Isolation Circuits replaced.W/900622 Ltr1990-06-22022 June 1990 LER 88-034-01:on 880831,RWCU Outboard Isolation Valve Closed,Causing RWCU Pumps to Trip.Caused by Loss of Continuity to Relay Due to Deposits Built Up on Surface of Contacts.Relay in Isolation Circuits replaced.W/900622 Ltr NRC-90-0087, LER 90-002-01:on 900202,determined That Area Radiation Surveillance Procedure 44.080.301 Listed Incorrect Values for Alarm Setpoints.Caused by Unavailable Setpoint Calculations.Procedure revised.W/900608 Ltr1990-06-0808 June 1990 LER 90-002-01:on 900202,determined That Area Radiation Surveillance Procedure 44.080.301 Listed Incorrect Values for Alarm Setpoints.Caused by Unavailable Setpoint Calculations.Procedure revised.W/900608 Ltr NRC-90-0075, LER 87-045-02:on 870908,operator Removed Fuse Which Deenergized Dc Control Power to Bus 72C,resulting in Loss of Power Supply to Swing Bus & to LPCI Loop Selection Valves. Caused by Design Flaw.Design Change initiated.W/900518 Ltr1990-05-18018 May 1990 LER 87-045-02:on 870908,operator Removed Fuse Which Deenergized Dc Control Power to Bus 72C,resulting in Loss of Power Supply to Swing Bus & to LPCI Loop Selection Valves. Caused by Design Flaw.Design Change initiated.W/900518 Ltr NRC-90-0073, LER 90-003-00:on 900410,Div I Reactor Protection Sys Power Supply Failure & Subsequent MSIV Closure.Caused by Coil Burn Up.Relays Replaced & MG Sets Returned to svc.W/900508 Ltr1990-05-0808 May 1990 LER 90-003-00:on 900410,Div I Reactor Protection Sys Power Supply Failure & Subsequent MSIV Closure.Caused by Coil Burn Up.Relays Replaced & MG Sets Returned to svc.W/900508 Ltr NRC-90-0048, LER 89-037-01:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed Prior to Expiration on 891125. Caused by Personnel Error.Procedure revised.W/900322 Ltr1990-03-22022 March 1990 LER 89-037-01:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed Prior to Expiration on 891125. Caused by Personnel Error.Procedure revised.W/900322 Ltr NRC-90-0027, LER 89-034-01:on 891208,two Members of Fire Watch Did Not Complete Assigned Hourly Rounds from 891002-1207 in Reactor & Auxiliary Bldgs.Both Individuals Terminated & Fire Stations Equipped W/Unique Bar code.W/900221 Ltr1990-02-21021 February 1990 LER 89-034-01:on 891208,two Members of Fire Watch Did Not Complete Assigned Hourly Rounds from 891002-1207 in Reactor & Auxiliary Bldgs.Both Individuals Terminated & Fire Stations Equipped W/Unique Bar code.W/900221 Ltr NRC-90-0021, LER 90-001-00:on 900108,annunciator 2D5 Alarmed for Div II ECCS Testability Logic/Power Failure.Caused by Blown Fuse. Fuse Installed During Course of Troubleshooting W/No Subsequent Problems noted.W/900207 Ltr1990-02-0707 February 1990 LER 90-001-00:on 900108,annunciator 2D5 Alarmed for Div II ECCS Testability Logic/Power Failure.Caused by Blown Fuse. Fuse Installed During Course of Troubleshooting W/No Subsequent Problems noted.W/900207 Ltr NRC-90-0019, LER 89-028-01:on 891028,eight Safety Relief Valves Failed Set Pressure Tolerance Test.Cause Under Review by Util & Generically by BWR Owners Group Safety Relief Valve Set Point Drift Committee.Valves Removed & cleaned.W/900131 Ltr1990-01-31031 January 1990 LER 89-028-01:on 891028,eight Safety Relief Valves Failed Set Pressure Tolerance Test.Cause Under Review by Util & Generically by BWR Owners Group Safety Relief Valve Set Point Drift Committee.Valves Removed & cleaned.W/900131 Ltr NRC-90-0018, LER 89-039-00:on 891226,Div I Emergency Equipment Cooling Water & Svc Water Sys Automatically Started Due to Partial Load Shed of Bus 72E.Caused by Personnel Error. Accountability Meeting Held on 900117.W/900125 Ltr1990-01-25025 January 1990 LER 89-039-00:on 891226,Div I Emergency Equipment Cooling Water & Svc Water Sys Automatically Started Due to Partial Load Shed of Bus 72E.Caused by Personnel Error. Accountability Meeting Held on 900117.W/900125 Ltr NRC-90-0008, LER 89-037-00:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed.Caused by Personnel Error. Critique of Event Being developed.W/900119 Ltr1990-01-19019 January 1990 LER 89-037-00:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed.Caused by Personnel Error. Critique of Event Being developed.W/900119 Ltr NRC-90-0007, LER 89-036-00:on 891218,control Room Operator Inadvertently Depressed Closed Push Buttons on Inboard MSIVs A,B & C & Reactor Scram Resulted.Caused by Operator Error.Operator Involved Was Removed from Licensed duties.W/900117 Ltr1990-01-17017 January 1990 LER 89-036-00:on 891218,control Room Operator Inadvertently Depressed Closed Push Buttons on Inboard MSIVs A,B & C & Reactor Scram Resulted.Caused by Operator Error.Operator Involved Was Removed from Licensed duties.W/900117 Ltr ML19354E0971990-01-12012 January 1990 LER 89-038-00:on 891223,reactor Scrammed When Fire Occurred in Vicinity of High Pressure Turbine.Caused by Oil Soaked Inlagging Pads & Ignited When Turbine Casing Heated Up to Oil Flashpoint.Insulation Pads replaced.W/900122 Ltr NRC-90-0005, LER 89-035-00:on 891210,steam Jet Air Ejectors Placed in Svc W/O Required Surveillance Completed & Required Grab Sample Not Started Until 891213.Caused by Personnel Error.Off Gas Sys Operating Procedure Will Be revised.W/900111 Ltr1990-01-11011 January 1990 LER 89-035-00:on 891210,steam Jet Air Ejectors Placed in Svc W/O Required Surveillance Completed & Required Grab Sample Not Started Until 891213.Caused by Personnel Error.Off Gas Sys Operating Procedure Will Be revised.W/900111 Ltr NRC-90-0004, LER 89-030-00:on 891026,Channel C Level 1 & 2 Replacement Transmitter Found to Be Installed Incorrectly & Condition Recognized on 891210,when Level 2 Trip Unit Was Reading Upscale.Caused by Personnel error.W/900109 Ltr1990-01-0909 January 1990 LER 89-030-00:on 891026,Channel C Level 1 & 2 Replacement Transmitter Found to Be Installed Incorrectly & Condition Recognized on 891210,when Level 2 Trip Unit Was Reading Upscale.Caused by Personnel error.W/900109 Ltr NRC-90-0002, LER 89-033-00:on 891207,volt-ohm Meter Connected to Incorrect Terminal,Causing Div II of Emergency Equipment Cooling Water Sys to Actuate.Caused by Personnel Error.Sys Secured & Channel Test Successfully completed.W/900108 Ltr1990-01-0808 January 1990 LER 89-033-00:on 891207,volt-ohm Meter Connected to Incorrect Terminal,Causing Div II of Emergency Equipment Cooling Water Sys to Actuate.Caused by Personnel Error.Sys Secured & Channel Test Successfully completed.W/900108 Ltr NRC-90-0003, LER 89-034-00:on 891208,review of Key Card Transactions Showed That Fire Watch Personnel Missed Assigned Hourly Fire Watch from 891020-1207.Fire Watch Person Discharged.Plan Re Improvement of Fire Watches developed.W/900108 Ltr1990-01-0808 January 1990 LER 89-034-00:on 891208,review of Key Card Transactions Showed That Fire Watch Personnel Missed Assigned Hourly Fire Watch from 891020-1207.Fire Watch Person Discharged.Plan Re Improvement of Fire Watches developed.W/900108 Ltr NRC-89-0261, LER 89-028-00:on 891129,ESF Actuations Occurred During Set Up for Surveillance.Caused by Blown Fuse.Blown Fuse Replaced & Affected Sys Returned to Normal Operation Following Completion of surveillance.W/891228 Ltr1989-12-28028 December 1989 LER 89-028-00:on 891129,ESF Actuations Occurred During Set Up for Surveillance.Caused by Blown Fuse.Blown Fuse Replaced & Affected Sys Returned to Normal Operation Following Completion of surveillance.W/891228 Ltr NRC-89-0260, LER 89-021-01:on 890906,35 of 237 Containment Isolation Valves Exceeded Administrative Allowable Leakage Rate When Tested.Caused by Normal Wear & Degradation During Specified Time Interval.Valves Cleaned & repaired.W/891221 Ltr1989-12-21021 December 1989 LER 89-021-01:on 890906,35 of 237 Containment Isolation Valves Exceeded Administrative Allowable Leakage Rate When Tested.Caused by Normal Wear & Degradation During Specified Time Interval.Valves Cleaned & repaired.W/891221 Ltr NRC-89-0255, LER 89-031-00:on 891120,both Div II Emergency Equipment Cooling Water (EECW) & Emergency Equipment Svc Water Sys Pumps Tripped Immediately.Caused by Inadequacies in Stated Procedures.Procedures revised.W/891220 Ltr1989-12-20020 December 1989 LER 89-031-00:on 891120,both Div II Emergency Equipment Cooling Water (EECW) & Emergency Equipment Svc Water Sys Pumps Tripped Immediately.Caused by Inadequacies in Stated Procedures.Procedures revised.W/891220 Ltr NRC-89-0259, LER 89-017-01:on 890810,new Analysis of Feedwater Line Break Scenario Assumes Failure of Feedwater Startup Control Valve in Open Position.Review of Pipe Break Documentation Conducted.Updated FSAR Change to Be submitted.W/891215 Ltr1989-12-15015 December 1989 LER 89-017-01:on 890810,new Analysis of Feedwater Line Break Scenario Assumes Failure of Feedwater Startup Control Valve in Open Position.Review of Pipe Break Documentation Conducted.Updated FSAR Change to Be submitted.W/891215 Ltr NRC-89-0256, LER 89-022-01:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse C71A-F15B Blew.On 890928, Reactor Bldg HVAC Isolated.Caused by Personnel Error. Procedures Will Be revised.W/891215 Ltr1989-12-15015 December 1989 LER 89-022-01:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse C71A-F15B Blew.On 890928, Reactor Bldg HVAC Isolated.Caused by Personnel Error. Procedures Will Be revised.W/891215 Ltr NRC-89-0258, LER 89-025-00:on 891115,low Level 2 Signal Unintentionally Induced During Reactor Pressure Vessel Hydrostatic Pressure Test.Caused by Personnel Error.Personnel Counseled on Notifying & Coordinating Instrument lineups.W/891215 Ltr1989-12-15015 December 1989 LER 89-025-00:on 891115,low Level 2 Signal Unintentionally Induced During Reactor Pressure Vessel Hydrostatic Pressure Test.Caused by Personnel Error.Personnel Counseled on Notifying & Coordinating Instrument lineups.W/891215 Ltr NRC-89-0251, LER 89-019-01:on 890819,discovered That Div I Recirculation Fan Not Rotating Which Resulted in Decrease in Control Room Air Pressure.Caused by Lack of Lubrication in Bearings. Lubrication Program Improvements evaluated.W/891130 Ltr1989-11-30030 November 1989 LER 89-019-01:on 890819,discovered That Div I Recirculation Fan Not Rotating Which Resulted in Decrease in Control Room Air Pressure.Caused by Lack of Lubrication in Bearings. Lubrication Program Improvements evaluated.W/891130 Ltr NRC-89-0249, LER 89-029-00:on 891023,half Scram Signal Received When Power Was Lost on Reactor Protection Sys Bus B,Resulting in Several ESFs Actuation.Caused by Location of Breaker Operating Switch in High Traffic area.W/891122 Ltr1989-11-22022 November 1989 LER 89-029-00:on 891023,half Scram Signal Received When Power Was Lost on Reactor Protection Sys Bus B,Resulting in Several ESFs Actuation.Caused by Location of Breaker Operating Switch in High Traffic area.W/891122 Ltr NRC-89-0246, LER 89-028-00:on 891020,eight safety-related Valves Failed Set Pressure Test.Cause Under Review.All Valves Removed for Testing Being Refurbished,Cleaned,Retested & Recertified to Be within Plant Accepted tolerances.W/891120 Ltr1989-11-20020 November 1989 LER 89-028-00:on 891020,eight safety-related Valves Failed Set Pressure Test.Cause Under Review.All Valves Removed for Testing Being Refurbished,Cleaned,Retested & Recertified to Be within Plant Accepted tolerances.W/891120 Ltr NRC-89-0244, LER 89-024-00:on 891019,recognized That Secondary Containment Dampers Not Tested as Required by Tech Spec 3.6.5.2.Caused by Operations Personnel Error.Event Critique to Be Included in Required Reading program.W/891120 Ltr1989-11-20020 November 1989 LER 89-024-00:on 891019,recognized That Secondary Containment Dampers Not Tested as Required by Tech Spec 3.6.5.2.Caused by Operations Personnel Error.Event Critique to Be Included in Required Reading program.W/891120 Ltr NRC-89-0194, LER 89-027-00:on 891015,reactor Bldg Hvac,Control Ctr HVAC & Drywell Floor & Equipment Drain Sumps Isolated & Standby Gas Treatment Sys & Noninterrruptalbe Control Air Compressors Started.Caused by Personnel error.W/891114 Ltr1989-11-14014 November 1989 LER 89-027-00:on 891015,reactor Bldg Hvac,Control Ctr HVAC & Drywell Floor & Equipment Drain Sumps Isolated & Standby Gas Treatment Sys & Noninterrruptalbe Control Air Compressors Started.Caused by Personnel error.W/891114 Ltr NRC-89-0193, LER 89-026-00:on 891010,control Ctr HVAC Shifted to Recirculation Mode of Operaton Due to Short Circuit.Caused by Failure of Lamp Filament When Being Tightened.Fuse & Lamp Replaced & Sys Returned to Normal operation.W/891109 Ltr1989-11-0909 November 1989 LER 89-026-00:on 891010,control Ctr HVAC Shifted to Recirculation Mode of Operaton Due to Short Circuit.Caused by Failure of Lamp Filament When Being Tightened.Fuse & Lamp Replaced & Sys Returned to Normal operation.W/891109 Ltr NRC-89-0192, LER 87-045-01:on 870908,fuse Removed Which Deenergized Dc Control Power to Bus 72C & Resulted in Loss of Power Supply to Swing Bus & LPCI Loop Selection Valves.Caused by Design Error.Undervoltage Relay Added & Training held.W/891106 Ltr1989-11-0606 November 1989 LER 87-045-01:on 870908,fuse Removed Which Deenergized Dc Control Power to Bus 72C & Resulted in Loss of Power Supply to Swing Bus & LPCI Loop Selection Valves.Caused by Design Error.Undervoltage Relay Added & Training held.W/891106 Ltr NRC-89-0190, LER 89-023-00:on 890924,personnel Inadvertently Caused Trip of Essential Safety Sys Buses 64B & 64C.Caused by Failure of Personnel Involved to Review Applicable Prints Prior to Performing Test.Event Reviewed w/personnel.W/891024 Ltr1989-10-24024 October 1989 LER 89-023-00:on 890924,personnel Inadvertently Caused Trip of Essential Safety Sys Buses 64B & 64C.Caused by Failure of Personnel Involved to Review Applicable Prints Prior to Performing Test.Event Reviewed w/personnel.W/891024 Ltr NRC-89-0189, LER 89-022-00:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse Blew.On 890928,reactor Bldg HVAC Isolated When Jumper Lifted Per Incorrect Work Plan Instruction.Caused by Personnel error.W/891023 Ltr1989-10-23023 October 1989 LER 89-022-00:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse Blew.On 890928,reactor Bldg HVAC Isolated When Jumper Lifted Per Incorrect Work Plan Instruction.Caused by Personnel error.W/891023 Ltr NRC-89-0186, LER 89-016-01:on 890711,Div 1 of RHR Svc Water Sys Declared Inoperable Due to Low Nitrogen Pressure for Cooling Tower Fan Brake.Caused by Leak in One Hose.Leaking Hose Replaced & Nitrogen Pressure restored.W/891006 Ltr1989-10-0606 October 1989 LER 89-016-01:on 890711,Div 1 of RHR Svc Water Sys Declared Inoperable Due to Low Nitrogen Pressure for Cooling Tower Fan Brake.Caused by Leak in One Hose.Leaking Hose Replaced & Nitrogen Pressure restored.W/891006 Ltr NRC-89-0185, LER 89-021-00:on 890906,local Leak Rate Testing of Containment Isolation Valves & Penetrations Exceeded Tech Spec Limit.Caused by Excessive Containment Isolation Valve Leakage Due to Degradation of valve.W/891006 Ltr1989-10-0606 October 1989 LER 89-021-00:on 890906,local Leak Rate Testing of Containment Isolation Valves & Penetrations Exceeded Tech Spec Limit.Caused by Excessive Containment Isolation Valve Leakage Due to Degradation of valve.W/891006 Ltr 1994-04-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0062, Monthly Operating Rept for May 1999 for Fermi 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fermi 2.With ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety NRC-99-0022, Monthly Operating Rept for Apr 1999 for Fermi 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fermi 2.With ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20205P9721999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fermi 2 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20204D0361999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fermi 2 ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 NRC-99-0005, Monthly Operating Rept for Dec 1998 for Fermi 2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fermi 2.With ML20207B7491998-12-31031 December 1998 1998 Annual Operating Rept for Fermi 2 ML20205Q9621998-12-31031 December 1998 Revised Monthly Operating Rept for Dec 1998 for Fermi 2 NRC-99-0021, 1998 Annual Financial Rept for Detroit Edison Co. with1998-12-31031 December 1998 1998 Annual Financial Rept for Detroit Edison Co. with NRC-98-0153, Monthly Operating Rept for Nov 1998 for Fermi 2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fermi 2.With NRC-98-0160, Monthly Operating Rept for Oct 1998 for Fermi 2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fermi 2.With ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode NRC-98-0139, Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With ML20154H8161998-09-30030 September 1998 Rev 0 to COLR Cycle 7 for Fermi 2 ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant NRC-98-0111, Monthly Operating Rept for Aug 1998 for Fermi 2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fermi 2.With ML20153B7921998-08-31031 August 1998 Rev 0 to Fermi 1 Sar ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 NRC-98-0109, Monthly Operating Rept for July 1998 for Fermi 21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Fermi 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 NRC-98-0097, Monthly Operating Rept for June 1998 for Fermi,Unit 21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Fermi,Unit 2 NRC-98-0127, Annual Rept for Period 970701-9806301998-06-30030 June 1998 Annual Rept for Period 970701-980630 NRC-98-0079, Monthly Operating Rept for May 1998 for Fermi 21998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Fermi 2 NRC-98-0076, Monthly Operating Rept for Apr 1998 for Fermi 21998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Fermi 2 NRC-98-0072, Monthly Operating Rept for Mar 1998 for Fermi 21998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Fermi 2 NRC-98-0050, Monthly Operating Rept for Feb 1998 for Fermi 21998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Fermi 2 NRC-98-0019, Monthly Operating Rept for Jan 1998 for Fermi 21998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Fermi 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval NRC-98-0015, Monthly Operating Rept for Dec 1997 for Fermi 21997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Fermi 2 ML20217N3821997-12-31031 December 1997 Annual Operating Rept for 970101-1231 NRC-98-0053, 1997 Annual Financial Rept for Detroit Edison Company1997-12-31031 December 1997 1997 Annual Financial Rept for Detroit Edison Company ML20205Q9601997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Fermi 2 NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility ML20197A9921997-12-15015 December 1997 Rev 0 to Efp,Unit 1 Fermi 1 Sar NRC-97-0131, Monthly Operating Rept for Nov 1997 for Fermi 21997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Fermi 2 ML20248H1151997-10-31031 October 1997 Rev 1 to Colr,Cycle 6 for Fermi 2 1999-09-30
[Table view] |
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NRC-89-0186 ;
U.. S. Nuclear Regulatory-Commission
-Attention - Document-Control Desk Washington. D.C. 20555 t
Reference:
Fermi 2 ;
NRC Docket No. 50-341 .
Facility Operating-License No. NPF-43 Transmittal of-Licensee Event Report ,
89-016-00 dated August 10, 1989 NRC-89-0136
Subject:
Licensee Event Report (LER) No. 89-016-01 Please find enclosed LER No. 89-016-01, dated October.6 1989, for a reportable event that occurredLon July 11 1989.. This report was revised to reflect the results of an evaluation of the necessity of the Residual Heat Removal Service Water Cooling Tower fan brakes in.various scenarios. A copy of this LER is also being sent to the Regional Administrator. USNRC Region III.
If you have any questions. please contact Patricia Anthony.at (313) 586-1617.
Sincerely, g/'
i
Enclosure:
NRC Forms 366 366A cc: A. B. Davis J. R. Eckert R. C. Knop W. G. Rogers J. F. Stang Wayne County Emergency Management Division .
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8910120179 891006 PDR ADOCK 05000341 S PDC
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LICENSEE EVENT REPORT'(LER) ' m a ' * '
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F hCILITY NAME tu DOCKET NUMSER Q1 FAGE G Fermi 2 oisIo10I0131411 ilorJ(g
'"" . Residual Heat-Removal Service Water Cooling Tower Fan Brakes Inoperable Due to Low Nitrogen Pressure EVENT DATE ISI LER NUMBER (6) REPORT DATE DI OTHER F AClilTIES INVOLVED 18)
MONTH DAY YEAR ' YEAR Oj L 7),% MONTH DAY YEAR C' LIT Y N AMES DOCAE T NUMBERIS)
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NAME TELEPHONE NUMBER _
Patricia Anthony, Compliance Engineer ' " ' ' ' '
3 l 1:3 5i 86i i -,l i611 i7 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE DESCRISED IN THl3 REPORT (1L M F C. REPORTA E M 8 C- REPORTA LE s ,
CAUSE SYST E M COMPONENT AUSE SYST E M COMPONENT E BtI lBiR'i K M i 01 851 Y i i i i t i i i l l I I I I I I I I I I I SUPPLEMElWTAL REPORT EXPECTED H4) MONTH DAY YEAR SUOMISSION YES (19 res, tempoon (K*ECTED $U614t$$10N DA TEI NO l l l AESTi. ACT Ibert to IM mecen, te., .porosimetruy rurwen songre space typewrotmo hoest (16)
On July 11 1989 Division I of the Residual Heat Removal Service. Water System (RHRSW) was declared inoperable due to low nitrogen pressure for one of the mechanical draft cooling 11 tower fan-brakes. The nitrogen supplies the motive force for the brakes. The brakes were installed to protect the fans from overspeeding in the event of a design basis tornado. 11 During the investigation and repair of the condition, it was L noted that control power to the brakes was being maintained in i
the AC supply position rather than the DC supply position as shown on the drawing.
Lack of nitrogen pressure would have prevented the brake from l fulfilling its design function in the event a tornado had occurred. A review of the original analysis and a more I realistic evaluation of the need for the mechanical fan brakes l
'has been conducted. The conclusions from this evaluation have Il reaffirmed the necessity of these brakes to protect the fan i from overspeed in the event of a design basis tornado. l The nitrogen supply was restored and a leaky hose replaced.
The system operating procedure was revised and the power supply properly aligned. As an enhancement, the design of the brake l system is being upgraded to QA1 status. This modification will 11 be completed during the First Refueling Outage s which is I currently underway. I
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Initial Plant-' Conditions:
OperationallCondition: . 1-~(Power Operation) ;
.. ' Reactor' Power: 100.Lpercent W . Reactor Pressure: 998 psig ,
, Reactor. Temperature: 519 degrees Fahrenheit c l b . Description of Occurrence:-
On July 1 1 .--. 1 9 8 9 ' a t 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />, the Residual Heat Removal Service Water' System [(RHRSW)(BI)] Mechanical ~ Draft Cooling Tower [(MDCT)(CWT)) Fan C. which provides cooling for the-
.RHRSW. was declared. inoperable due..to the lack of nitrogen l1 for one of the fan brakes. The b rakes pro' vide protection-for -
th'e safety-related' fans against.a postulated tornado.: one of the design' basis.natura1' phenomena. Nitrogen pressure supplies
- the-motive power for application'of the brakes.and, therefore.
is required for brake operation. A separate set of nitrogen bottles supply each fan independently. The plant entered the
~72 hour--Limiting Condition for Operation (LCO) 3.7.1.1.a.3.
A11eaking hose-in'the nitrogen system was replaced and nitrogen pressure was: restored. The LCO was exited at 0512 hours0.00593 days <br />0.142 hours <br />8.465608e-4 weeks <br />1.94816e-4 months <br /> on July '
12, 1989.
~During the investigation of the problem, it_was noted that the-_ power supply _for the brakes was aligned to the AC supply, per procedure, rather than the DC supply. The design-provides '
for control power from.a 125 volt DC power supply through an
, AC/DC inverter and selector switch. The selector switch can I connect to a balance of_ plant DC source or a class 1E 120 voit AC. source which is powered by the Emergency Diesel Generators.
If during a tornado the brakes were powered from the AC supply, the. brakes-would be de-energized f or a short period of time if offsite power was lost while the Emergency Diesel Generators l1 i are loading. In the unlikely event all offsite power is lost '
and the tornado passes over the tower, the brakes would be '
unavailable during the' period of time the Emergency Diesel Generators are loading. This could have allowed the fans ,
to overspeed and be damaged. Therefore, aligning the brakes to the DC power supply, which is contained in a structure which has a low probability of being damaged. was determined to be '
desirable. The system operating procedure involved has been ,
l revised and the power supply aligned to DC power. 11
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Additionally, the review identified some design anomalies.
Prior to licensing of the plant. the AC circuit was found to :;
-have an electronic interference problem which could potentially cause the brakes to be applied unnecessarily. The control circuit was modified to add auxiliary control relays. These new auxiliary relays were not QA1. Since the.reirys were not seismically qualified, they could be postulated to fail during a safe shutdown earthquake; leading to inadvertent application of the MDCT' fan brakes temporarily. However, even under worst postulated meteorological. conditions, there is ample time to release the brakes and restore the MDCT safety function following a seismic event. As an added precaution, operating procedures and operator training to accomplish this have been provided.
1 Additional anomolies include u,s e of unqualified valves, which' l1 will be dedicated by similarity analysis, the use of 130V DC l BOP power suoply and use of an unqualified DC inverter. From tornado design aspects, prcbability analysis shows that the design with these unqualified components is adequate and will perform its intended protection against a tornado event. Any failure of the power supply or inverter during an earthquake has no. impact on the seismic qualification of the MDCT design.
Therefore the present design is adequate for tornado protection and ample time exists for corrective action, should brakes be 11 applied following an e'arthquake. l Cause of Event:
The loss of nitrogen pressure was due to a leak in one of the -
hoses. There was a lack of awareness on the part of Detroit Edison of the necessity for maintaining the fan brakes in an operable status. Since this was not an identified limitation to operability, corrective actions were not always completed in a timely manner.
The line up of the power supply to the AC supply rather than the DC supply was specified in the system operating procedure. SOP 23.208 in revision 6 which was approved on January 14 1985.
Analysis of Event:
At Fermi 2 the RHR reservoirs provide the ultimate heat sink l function. The system includes two cooling fans for I each reservoir cooling tower. Both cooling tower fans are 11 required to be operable, per Technical Specification 3.7.1.5 l for each reservoir to be operable. The MDCT fans are required I under certain conditions to provide for heat rejection cooling uxCrorus a ***"""* *"
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mi ru mm ea. n . ens a ,eww ww n. numm 1 for the Residual Heat Removal complex water. Per Section 9.2.5.2.2 of the Fermi 2 Updated Final Safety Analysis Report, the fans are provided with a brake system to prevent '
overspeeding from the design. basis tornado. With the brake 'l I system inoperable, a design basis tornado could have damaged 11 j the fans such that they may not have been able to perform l their function. j A review of the original analysis and a more realistic l evaluation of the need for the mechanical fan brakes has been I conducted. This evaluation assessed the tornado wind and i pressure loads, air flow through the fans under the postulated l l loads, the aerodynamic response of the fans. and potential fan 11 f failure modes. The conclusions from this evaluation indicate i J that significant overspeeding of the cooling tower fans is a l potential concern under the high winds associated with a l tornado. Therefore, the origina1' decision to install protective I brakea was valid. I Per the Technical Specification definition, a component is I operable when it is capable of performing its specified I function and when all necessary attendant auxiliary equipment I that is required for the component to perform its function is I also capable of performing its support function. The RHR l cooling tower fan brakes are necessary to maintain 11 functionality of the fans during a design basis tornado. l The fans are capable of performing their function during all I other circumstances, including the Design Easis Accident. I without the brakes. Therefore, except during a design basis I tornado, the brakes are not necessary support equipment for 1 -
the fans. I Following a design-basis tornado, the ultimate heat sink is capable of-performing its safety function without the fans being operable for at least four hours. The operators could take several possible courses in order to provide alternate cooling. An example of one of these options would be to restore power and use the circulating water system and the main condenser to provide blowdown. In-any case, the fans would be able to perform their design function with the brakes inoperable under all conditions except for a design i basis tornado scenario. 11 The existing design for the MDCT fan brakes, when they are properly aligned to the BOP DC battery power source and when the nitrogen bottles are sufficiently charged, provides adequate tornado protection.
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s Corrective' Actions:
L -
The nitrogen-hose that'.was. leaking was replaced and Eitrogen ;
pressure restored in order-to return the system to sperable l
status. A revision'was made to SOP 23.208 in order to specify that.the:. power supply should be lined-up from the-DC supply.
A-review of the operability of the system was-performed. ll i It determined that the system is_. operable. As an added -l precaution, the abnormal operating procedure for earthquakes was.. revised to instruct'the operators to check <
- MDCT Ian' operation'following an earthquake. The revision
.provides direction on how to manually release the brake, if 1
'necessary. ;
-As_ discussed previously, an engineering review has confirmed 11 a- the necessity of the fan brakes to protect the fans from l' ,
'overspeed during a design basis tornado. As an enhancement. l the' current-design of the. brake system is being upgraded to l ,
QA11 status. -Engineering. Design Package 10518 will be l be: completed before restart from the First Refueling l- ',
10utage, which is currently underway. l A Design Basis Task Force effort was started in September of' 11 1989 to review . selected, systems and raise the consciousness l of plant ~ personnel to the licensing basis of the plant. 7 Additionally, the current corrective action program captures
. identified problems and tracks them until all necessary l
. actions.are completed. l1 Previous Similar Events:
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