Turbine bypass valve: Difference between revisions

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Revision as of 07:40, 14 March 2018

 SiteStart dateTitle
05000000/LER-1986-038-02, :on 861209,reactor Scram Occurred Due to Low Condenser Vacuum.Caused by Personnel Error.Discussions W/Operating Personnel Involved Will Be Held.Procedure Qgp 1-1 to Be RevisedQuad Cities
05000000		23 December 1986
on 861209,reactor Scram Occurred Due to Low Condenser Vacuum.Caused by Personnel Error.Discussions W/Operating Personnel Involved Will Be Held.Procedure Qgp 1-1 to Be Revised
05000155/LER-1988-002, :on 880205,plant Operators Manually Tripped Reactor in Response to Loss of Recirculation Flow.Caused by Personnel Error.Equipment Testing Performed to Insure That No Malfunctions Occurred or Damage PresentBig Rock Point7 March 1988
on 880205,plant Operators Manually Tripped Reactor in Response to Loss of Recirculation Flow.Caused by Personnel Error.Equipment Testing Performed to Insure That No Malfunctions Occurred or Damage Present
05000155/LER-1988-008-01, :on 881028,load Rejection Occurred Due to Loss of Transmission Line.Caused by Lightning Rod Which Broke Off During High Winds.Control Rod Drive Motor Generator Set RepairedBig Rock Point23 November 1988
on 881028,load Rejection Occurred Due to Loss of Transmission Line.Caused by Lightning Rod Which Broke Off During High Winds.Control Rod Drive Motor Generator Set Repaired
05000155/LER-1989-009-01, :on 891027 & 31,turbine Bypass Valve Would Not Open When Given Open Signal.Caused by Characteristics of Garlock Style 938 Which Hardens When Subj to Heat & Pressure.Valves Repacked Using Carbon SpacersBig Rock Point9 January 1990
on 891027 & 31,turbine Bypass Valve Would Not Open When Given Open Signal.Caused by Characteristics of Garlock Style 938 Which Hardens When Subj to Heat & Pressure.Valves Repacked Using Carbon Spacers
05000155/LER-1996-010-01, :on 960916,automatic Reactor Scram Occurred During Startup Due to High Reactor Pressure.Fabrication Process Will Be Evaluated & CorrectedBig Rock Point15 October 1996
on 960916,automatic Reactor Scram Occurred During Startup Due to High Reactor Pressure.Fabrication Process Will Be Evaluated & Corrected
05000155/LER-1998-001-01, :on 980714,during Facility Decommissioning, Found Liquid Poision Tank Discharge Pipe Severed.Caused by Corrosion.Staff Reviewed Current Decommissioning Surveillance Testing on safety-related SSCsBig Rock Point6 August 1998
on 980714,during Facility Decommissioning, Found Liquid Poision Tank Discharge Pipe Severed.Caused by Corrosion.Staff Reviewed Current Decommissioning Surveillance Testing on safety-related SSCs
05000219/LER-1981-021, Forwards LER 81-021/03L-0.Detailed Event Analysis EnclOyster Creek1 July 1981Forwards LER 81-021/03L-0.Detailed Event Analysis Encl
05000219/LER-1985-015, :on 850708,scram Occurred on Low Condenser Vacuum.Caused by Cracked Drain Pump 1-1 Casing & Tube Leak in Steam Packing Exhauster.Drain Pump 1-1 Replaced & Drain Pump 1-2 & Tube Leak RepairedOyster Creek8 August 1985
on 850708,scram Occurred on Low Condenser Vacuum.Caused by Cracked Drain Pump 1-1 Casing & Tube Leak in Steam Packing Exhauster.Drain Pump 1-1 Replaced & Drain Pump 1-2 & Tube Leak Repaired
05000219/LER-1986-032, :on 861224,reactor Trip Occurred Due to High Neutron Flux Condition.Caused by Personnel Error & Configuration W/Respect to Feedwater Control Sys.Event Reviewed W/Each Oncoming ShiftOyster Creek23 January 1987
on 861224,reactor Trip Occurred Due to High Neutron Flux Condition.Caused by Personnel Error & Configuration W/Respect to Feedwater Control Sys.Event Reviewed W/Each Oncoming Shift
05000219/LER-1986-034, ,on 861229,manual Scram Due to Inability to Maintain Condenser Vacuum Occurred.Caused by Expansion Joint Failure in Vacuum.Procedure Limit of Saturation Temp Reduced to Prevent RecurrenceOyster Creek30 January 1987,on 861229,manual Scram Due to Inability to Maintain Condenser Vacuum Occurred.Caused by Expansion Joint Failure in Vacuum.Procedure Limit of Saturation Temp Reduced to Prevent Recurrence
05000219/LER-1987-005, :on 870116,high Flux Reactor Scram Occurred Due to Increased Recirculation Flow.Caused by Starting of Pump W/Discharge Valve Partially Open.Second Scram Occurred Due to Calibr Error.Valves ReadjustedOyster Creek27 February 1987
on 870116,high Flux Reactor Scram Occurred Due to Increased Recirculation Flow.Caused by Starting of Pump W/Discharge Valve Partially Open.Second Scram Occurred Due to Calibr Error.Valves Readjusted
05000219/LER-1987-011, :on 870214,anticipatory Reactor Scram Occurred Due to High Reactor Water Level Turbine Trip.Caused by Inadvertent Disconnection of Feedwater a Flow Signal Wire by Technician.Procedures RevisedOyster Creek20 March 1987
on 870214,anticipatory Reactor Scram Occurred Due to High Reactor Water Level Turbine Trip.Caused by Inadvertent Disconnection of Feedwater a Flow Signal Wire by Technician.Procedures Revised
05000219/LER-1987-011, :on 870214,reactor Scram Occurred as Result of High Reactor Water Level Turbine Trip.Caused by Faulty Wire Installation During Plant Const or Maint.Terminations in Control Room Inspected & TightenedOyster Creek4 May 1987
on 870214,reactor Scram Occurred as Result of High Reactor Water Level Turbine Trip.Caused by Faulty Wire Installation During Plant Const or Maint.Terminations in Control Room Inspected & Tightened
05000219/LER-1990-010, :on 900718,electromatic Relief Valve High Pressure Relief Setpoints Discovered to Exceed Tech Spec Limit.Caused by Setpoint Repeatability & Instrument Drift. Pressure Switches Adjusted to Be within LimitOyster Creek20 August 1990
on 900718,electromatic Relief Valve High Pressure Relief Setpoints Discovered to Exceed Tech Spec Limit.Caused by Setpoint Repeatability & Instrument Drift. Pressure Switches Adjusted to Be within Limit
05000219/LER-1992-006, :on 920510,EMRV Pressure Sensor Surveillance, as Found Trip Setpoint for High Pressure Relief Function Above TS Limit.Caused by Instrument Setpoint Repeatability. Pressure Switch Immediately AdjustedOyster Creek3 June 1992
on 920510,EMRV Pressure Sensor Surveillance, as Found Trip Setpoint for High Pressure Relief Function Above TS Limit.Caused by Instrument Setpoint Repeatability. Pressure Switch Immediately Adjusted
05000219/LER-1994-007, :on 940531,reactor Scram Occurred Due to Modification Work in Switchyard.Placing Modification on Hold Pending Engineering Review & Strengthening Procedural Controls Over Switchyard WorkOyster Creek30 June 1994
on 940531,reactor Scram Occurred Due to Modification Work in Switchyard.Placing Modification on Hold Pending Engineering Review & Strengthening Procedural Controls Over Switchyard Work
05000219/LER-1994-008, :on 940419,setpoints for High Pressure Relief Function on Two EMRVs Were Above That Specified in Tss. Caused by Setpoint Repeatability & Instrument Drift.Pressure Switches Were Adjusted within TS LimitsOyster Creek19 July 1994
on 940419,setpoints for High Pressure Relief Function on Two EMRVs Were Above That Specified in Tss. Caused by Setpoint Repeatability & Instrument Drift.Pressure Switches Were Adjusted within TS Limits
05000219/LER-1995-005, :on 950825,identified non-conservative Instrument Setpoint for Anticipatory Scram Bypass Pressure Switches Due to Original Plant Design.Revised Plant Operation ProceduresOyster Creek21 September 1995
on 950825,identified non-conservative Instrument Setpoint for Anticipatory Scram Bypass Pressure Switches Due to Original Plant Design.Revised Plant Operation Procedures
05000219/LER-1995-008, :on 951218,reactor Scram Occurred on High RPV Pressure Due to Main Generator Runback.Repaired Faulty Temp Control ValveOyster Creek18 January 1996
on 951218,reactor Scram Occurred on High RPV Pressure Due to Main Generator Runback.Repaired Faulty Temp Control Valve
05000219/LER-1996-005, :on 960430,reactor Scram Occurred on Low Water Level Due to Personnel Error.Discussion of Event Issued to Operators & Interim Guidance Issued to Operators on Reactor Water Level ControlOyster Creek11 June 1996
on 960430,reactor Scram Occurred on Low Water Level Due to Personnel Error.Discussion of Event Issued to Operators & Interim Guidance Issued to Operators on Reactor Water Level Control
05000219/LER-2013-004Oyster Creek14 December 2013Manual SCRAM due to rise in Reactor Pressure during Turbine Valve Testing
05000219/LER-2014-006Oyster CreekReactor SCRAM due to Decreasing Reactor Water Level
05000219/LER-2016-004Oyster CreekTechnical Specification Violation Due to Main Steam Safety Valve Setpoint Discovered Out of Tolerance
05000219/LER-2017-003Oyster Creek3 July 2017
31 August 2017		Automatic Scram while Suberitical due to Low Reactor Level
LER 17-003-00 for Oyster Creek Regarding Automatic Scram while Subcritical due to Low Reactor Level
05000220/LER-1985-022, :on 851107,turbine Bypass Valve 12-H Inadvertently Closed,Causing Decrease in Reactor Water Level & Subsequent Scram & Initiation of HPCI Mode of Feedwater. Valve to Be InspectedNine Mile Point6 December 1985
on 851107,turbine Bypass Valve 12-H Inadvertently Closed,Causing Decrease in Reactor Water Level & Subsequent Scram & Initiation of HPCI Mode of Feedwater. Valve to Be Inspected
05000220/LER-1985-023, :on 851108,during Preparations for Main Turbine Startup,High Temp in Main Turbine Exhaust Hood Caused Turbine Trip & Actuation of HPCI Mode of Feedwater FlowNine Mile Point6 December 1985
on 851108,during Preparations for Main Turbine Startup,High Temp in Main Turbine Exhaust Hood Caused Turbine Trip & Actuation of HPCI Mode of Feedwater Flow
05000220/LER-1999-004-01, :on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.WithNine Mile Point23 August 1999
on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With
05000220/LER-2003-002
05000220/LER-2004-00430 August 2004
05000220/LER-2005-0017 March 2005Automatic Reactor Scram due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch
05000220/LER-2005-00318 August 2005Automatic Reactor Scram during Surveillance Testing due to Inadvertently De-energizing 4160 VAC Power Board 11
05000220/LER-2008-002Docket Number23 October 2008Manual Reactor Scram Due to Loss of Reactor Pressure Control
05000220/LER-2009-002Docket NumberHigh Pressure Coolant Injection System Initiation Following a Manual Turbine Trip Due to High Turbine Bearing Vibrations
05000220/LER-2009-003Docket Number5 October 2009Manual Scram and High Pressure Coolant Injection Following a Loss of Feedwater Level Control Due to Firmware Deficiency
05000220/LER-2011-001Nine Mile Point2 May 2011Turbine Trip Due to Oil Pressure Fluctuations to the Turbine Master Trip Solenoid
05000220/LER-2012-001Nine Mile PointAutomatic Reactor Scram due to Electronic Pressure Regulator Failure
05000220/LER-2012-002Nine Mile PointAutomatic Reactor Scram due to Automatic Generator Protective Trip
05000220/LER-2012-004Nine Mile PointAutomatic Reactor Scram Due to a Generator Load Reject
05000220/LER-2012-005Nine Mile PointFeedwater Level Control Failure, HPCI initiation and Reactor Scram
05000220/LER-2012-006Nine Mile PointTechnical Specification Required Shutdown Due to Containment Leakage
05000220/LER-2015-004Nine Mile Point4 September 2015Automatic Reactor Scram Due to Main Steam Isolation Valve Closure
05000220/LER-2017-002Nine Mile Point18 May 2017Manual Reactor Scram Due to Pressure Oscillations
LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 1 Regarding Manual Reactor Scram Due to Pressure Oscillations
05000220/LER-2017-003Nine Mile Point6 September 2017
2 November 2017		Automatic Reactor Scram due to Reactor Vessel Low Water Level
LER 17-003-00 for Nine Mile Point, Unit 1, Regarding Automatic Reactor Scram due to Reactor Vessel Low Water Level
05000237/LER-2004-002Docket Number24 April 2004Dresden Nuclear Power Station Unit 2 05000237 1 of 5
05000237/LER-2005-002Dresden24 March 2005Unit 2 Group 1 Isolation and Resulting Scram
05000245/LER-1981-038, Forwards LER 81-038/03L-1.Detailed Event Analysis EnclMillstone13 January 1982Forwards LER 81-038/03L-1.Detailed Event Analysis Encl
05000245/LER-1990-018-01, :on 901212,discovered That Condenser Vacuum Switches Out of Tolerance Due to Instrument Drift.Barksdale Condenser Low Vacuum Scram Pressure Switches Replaced W/ Static O-Ring Pressure SwitchesMillstone15 September 1994
on 901212,discovered That Condenser Vacuum Switches Out of Tolerance Due to Instrument Drift.Barksdale Condenser Low Vacuum Scram Pressure Switches Replaced W/ Static O-Ring Pressure Switches
05000245/LER-1993-010-01, :on 930917,determined Unit 1 Has No Automatic Reactor Recirculation Pump Runback Circuitry in Place.Caused by Incorrect Analysis Assumption in Original Plant Accident analysis.Re-analysis PerformedMillstone18 October 1993
on 930917,determined Unit 1 Has No Automatic Reactor Recirculation Pump Runback Circuitry in Place.Caused by Incorrect Analysis Assumption in Original Plant Accident analysis.Re-analysis Performed
05000245/LER-1997-007-01, :on 970131,flow-biased High Flux Reactor Scram Credited in Establishing Not Single Failure Proof.Cause of Event Still Under Investigation.Rept Will Be Supplemented by 970331,w/cause of EventMillstone3 March 1997
on 970131,flow-biased High Flux Reactor Scram Credited in Establishing Not Single Failure Proof.Cause of Event Still Under Investigation.Rept Will Be Supplemented by 970331,w/cause of Event
05000245/LER-1997-034-01, :on 970812,Unit 1 Switchgear Failed During Unit 2 High Energy Line Break.Caused by Incorrect Assumption by HELB Analysis Performed by A&E.No Immediate Corrective Actions RequiredMillstone11 September 1997
on 970812,Unit 1 Switchgear Failed During Unit 2 High Energy Line Break.Caused by Incorrect Assumption by HELB Analysis Performed by A&E.No Immediate Corrective Actions Required
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