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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20024J3301994-10-0707 October 1994 LER 94-011-00:on 940908,manual Reactor Trip Initiated Due to MSIV Failure During part-stroke Test.Solenoid Valve & Number of Pins Replaced & MSIVs Tested satisfactorily.W/941007 Ltr ML20024J3291994-10-0303 October 1994 LER 94-027-00:on 940903,determined That Channel B Linear Range Nuclear Instrument Inoperable as Result of Connector J6 Being Disconnected from Jack.Connector J6 Reinstalled.W/ 941003 Ltr ML20029E5291994-05-13013 May 1994 LER 94-007-00:on 940414,determined That Valve Stroke Time Acceptance Criterion Exceeded System Response Time.Caused by Programmatic Error During Initial Startup.Corrective Action: Stroke Time Acceptance Has Been reduced.W/940513 Ltr ML20029E1361994-05-11011 May 1994 LER 94-007-00:on 940412,CRAC & Ebfs Were Inoperable Due to Previous Charcoal Testing Performed to Industry Std Different than Ts.Corrective Actions:Ts Changed to Reflect Newest Charcoal Testing procedure.W/940511 Ltr ML20029D8491994-05-0202 May 1994 LER 94-006-00:on 940407,plant Did Not Meet Requirements of LCO 3.7.6.1 Re Two Independent Control Room Emergency Ventilation Sys.Caused by Inadequate Work Organization. Corrective Action:Revised OP 2315A.W/940502 Ltr ML20029D6221994-04-29029 April 1994 LER 94-005-00:on 940401,determined That Both Facilities of Ebfs Had Never Been Tested in Accordance W/Ts.Caused by Program Failure/Personnel Error.Corrective Action: Surveillance Was Completed satisfactorily.W/940429 Ltr ML20029D2531994-04-28028 April 1994 LER 94-008-00:on 940329,discovered That Data in OPS Form 2604P-2,was Recorded Incorrectly.Caused by Program Failure, Procedure Deficiencies & Technical Error.Corrective Action: Recalculated ESF Equipment Circuit response.W/940428 Ltr ML20046C7771993-08-0606 August 1993 LER 93-010-00:on 930707,reactor Trip Input to Turbine Trip Portion of ESFAS Declared Inoperable Due to Inadequate Surveillance Testing.Test to Verify Operability Written & performed.W/930806 Ltr ML20046C2161993-08-0303 August 1993 LER 93-017-00:on 930701,possible Inoperability of Power Operated Relief Valve Blocking Valves Caused by Original Design Basis.Changed Designs & Performed tests.W/930803 Ltr ML20046B0311993-07-23023 July 1993 LER 93-012-01:on 930524,turbine & Reactor Tripped During Mussel Cook (Thermal Backwash) Due to Lack of Heat Removal Capabilities from Main Generator Stator Water Cooling Sys. Installed Thermoconductivity filler.W/930723 Ltr ML20045H8991993-07-15015 July 1993 LER 93-009-00:on 930617,determined That Suppl Leak Collection & Release Sys May Have Been Inoperable During Certain Weather Periods in Past.Caused by Failure to Account for Chimney Effect.Suppl Will Be sent.W/930715 Ltr ML20045H4021993-07-0909 July 1993 LER 93-007-00:on 930611,plant Mgt Discovered Reduction in EDG Fuel Oil Storage Capacity Per SER & Fsar,Constituting Event Outside Design Basis of Plant.Caused by Inadequate Design Interface.Temporary Tanker utilized.W/930709 Ltr ML20045H8921993-07-0909 July 1993 LER 93-005-01:on 930311,discovered That Automatic RPS Actuation Occurred on 930222 & Not Immediately Reported to Nrc.Caused by Personnel Error.Memo Sent to All Licensed Operators/Personnel Re Reporting requirements.W/930709 Ltr ML20045H8571993-07-0909 July 1993 LER 93-008-00:on 930614,one Channel of Electrical Environmentally Qualified Temp Monitor for Main Steam Valve Bldg Found Indicating Improperly.Caused by Personnel Error. Manual Logging of Temp initiated.W/930709 Ltr ML20045F5891993-07-0202 July 1993 LER 93-013-00:on 930603,noted That Main Turbine Generator EHC Sys Caused an Increase in Pressurizer Pressure,Resulting in Reactor Trip,Due to Closing of Intercept & Cv.Operators Performed EOP & Sys Performed as expected.W/930702 Ltr ML20045F6881993-07-0202 July 1993 LER 93-004-02:on 930222,reactor Trips on SG Low Water Level Occurred.Caused by Automatic Trip of MFW Pump B on Low Suction Pressure Due to High FW Flow Rates.Classroom Training on Main & Afwc Received by Licensed Operators ML20045D9041993-06-23023 June 1993 LER 93-012-00:on 930524,reactor Trip Occurred Due to Turbine Trip & Malfunction Caused Feedwater Regulating Valve a to Stay Approx 56% Open.Caused by Lack of Heat Removal Capabilities.Hand Wheels secured.W/930623 Ltr ML20045D8601993-06-21021 June 1993 LER 93-006-00:on 930525,two HPSI Discharge Check Valves Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Personnel Error.Test Written & Performed to Demonstrate Valve operability.W/930621 Ltr ML20045D9031993-06-21021 June 1993 LER 92-003-01:on 920207,discovered Potential Barrier Breach Via Direct Openings Around Main Feedwater Bypass Line Penetrations.On 920130,plant Entered Mode 4 W/O Encl Bldg Integrity.Erosion/Corrosion Exam Procedure Modified ML20045D3091993-06-18018 June 1993 LER 93-005-00:on 930520,cold Over Pressure Protection Sys Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Mgt Deficiency.Overlap Task Force Will Continue to Review Procedures Associated W/Reactor trip.W/930618 Ltr ML20045A4491993-06-0404 June 1993 LER 93-009-00:on 930506,inlet & Outlet skid-mounted Isolation Valves to Radiation Monitor Found Shut.Caused by Procedure Noncompliance by I&C Personnel.Personnel Will Review & Edit Radiation procedures.W/930604 Ltr ML20045A2321993-06-0101 June 1993 LER 93-008-00:on 930505,determined That Electrical Starter for Both Charging Pumps Inoperable.Caused by Program Failure.Administrative Controls Have Been Established to Ensure Minimum TS requirements.W/930601 Ltr ML20044C9191993-05-0707 May 1993 LER 93-002-01:on 930206 & 07,Train a & Train B CR Pressurization Sys Failed 18-month Surveillance Test, Respectively.Caused by Moisture in Air Banks & Pressure Oscillations.Air Banks purged.W/930507 Ltr ML20044C9331993-04-30030 April 1993 LER 91-002-01:on 910118,engineering Evaluation Determined That Operation of Four Vital 120-volt Ac Buses,On Alternate Sources,Unsatisfactory.Caused by Failure to Update TS to Reflect Configuration.Inverter Sys replaced.W/930430 Ltr ML19346B2411992-08-20020 August 1992 LER 92-018-00:on 920722,both RHR Trains Rendered Inoperable Due to Procedure Deficiency.Both Trains of RHR Restored to Operable Condition & Surveillance Procedures for Both Trains revised.W/920820 Ltr ML20024H3241991-05-24024 May 1991 LER 91-001-01:on 910110,electro-hydraulic Control Sys Failure Occurred,Causing Reactor Trip.Caused by Turbine Trip.Both EHC Pump Discharge Filters Changed Out & Pump B Replaced W/Spare pump.W/910524 Ltr ML20029C1281991-03-18018 March 1991 LER 91-004-00:on 910216,unexpected Trip of 'B' Steam Generator Feed Pump & Subsequent Manual Reactor Trip Occurred.Cause Unknown.Monitoring Capability Added to Sgfp Circuitry & Design Change made.W/910318 Ltr ML20029B6001991-03-0707 March 1991 LER 91-004-00:on 910205,leakage Found During Local Leak Rate Testing for Four Containment Isolation Valves.Caused by Improper Valve Seating.Valve Removed from Svc & Sent to Mfg for overhaul.W/910307 Ltr ML20029B6031991-03-0404 March 1991 LER 91-002-00:on 910202,setpoint Drift Identified During Testing of Main Steam Safety Valves.Caused by Inadequate Design.Nine out-of-tolerance Valves Reset within Specified +1% Tolerance ML20029B5981991-03-0404 March 1991 LER 91-003-00:on 910203 & 16,spurious Control Bldg Isolation Signals Received from Train a Control Bldg Ventilation Inlet Radiation Monitor.Caused by Equipment Malfunction.Detector replaced.W/910304 Ltr ML20029A6501991-02-19019 February 1991 LER 91-001-00:on 910117,discovered That Source Check Surveillance Procedure to Verify Operability of Beta Scintillation Radiation Detectors Did Not Meet TS Requirements.Surveillance Procedure revised.W/910219 Ltr ML20028H4261990-12-27027 December 1990 LER 89-005-01:on 890330,intermittent Connection While Sliding Module Into Position Caused Automatic Test Insertion Circuit to Send Signals Greater than Normal Pulse Thus Allowing Three SIAS Modules to actuate.W/901227 Ltr ML20028H4391990-12-27027 December 1990 LER 90-015-01:on 900919,inadvertent Isolation of Containment Isolation Valves Occurred.On 900920,inadvertent Actuation of Sias,Containment Isolation Actuation Sys & Encl Bldg Filtration Sys occurred.W/901227 Ltr ML20028H4271990-12-27027 December 1990 LER 90-021-00:on 901127,LCO Paragraph 3.0.3 Entered.Caused by Poor Communications.Mgt Reviewed Event & Events Leading Up to Incident & Concluded That Increased Awareness W/ Respect to Sys Status Must Be pursued.W/901227 Ltr ML20028H4401990-12-24024 December 1990 LER 90-019-00:on 900606,automatic Reactor Trip from Negative Flux Rate Signal Occurred Due to Dropped Control Rod.Caused by Broken Connection in Gripper Coil Power Cable.Connector Replaced & Power Loop checked.W/901224 Ltr ML20028G9421990-09-26026 September 1990 LER 90-012-00:on 900827,automatic Reactor Trip Occurred During Bypass Switch Operations.Caused by Operator Error. Procedure Sp 2601D Revised to Incorporate Separate Section on Performing calibrs.W/900926 Ltr ML20028G9111990-09-18018 September 1990 LER 89-008-01:on 891002,determined That Plant Failed to Perform Functional Check of Control Board Annunciators During Channel Functional Tests.Caused by Personnel Error. Procedures Revised Re Annuciator testing.W/900918 Ltr ML20044B0441990-07-10010 July 1990 LER 90-007-00:on 900611,discovered That Surveillance Procedure 2609E Re Encl Bldg Filtration Sys Testing - Refueling Not Performed Prior to Entering Mode 4.Caused by Personnel Error.Missed Surveillance performed.W/900710 Ltr ML20044A1581990-06-18018 June 1990 LER 90-017-00:on 900518,loss of Both Trains of HPSI Occurred.Caused by Cognitive Failure by Licensed Operator. Personnel Counseled on Causes of Event & Importance of Recognizing When Event reportable.W/900618 Ltr ML20043H2021990-06-15015 June 1990 LER 90-005-00:on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973.W/900615 Ltr ML20043G1031990-06-12012 June 1990 LER 90-016-00:on 900513,steam Generator B lo-lo Signal Generated Reactor Trip Signal,Causing Automatic Start of motor-driven Auxiliary Feedwater Pumps a & B.Caused by Inadequate Guidance.Procedure revised.W/900612 Ltr ML20043G3921990-06-11011 June 1990 LER 90-014-00:on 900519,manual Reactor Trip Initiated as Result of Anticipated Turbine Trip Due to Condenser Vacuum. Caused by Design Deficiency in That Traveling Screen Capacity Inadequate.Traveling Screen modified.W/900611 Ltr ML20043F7021990-06-11011 June 1990 LER 90-015-00:on 900512,feedwater Isolation Occurred While Opening Msivs.Caused by MSIV 2 Opening Faster than Other Msivs,Resulting in Swell in Steam Generator 2.Steam Generator Level Restored to normal.W/900611 Ltr ML20043F8261990-06-0707 June 1990 LER 90-006-00:on 900508,reactor Manually Tripped When Decreasing Levels Noted in Steam Generator 1 & Feedwater Regulating Valve Indicated Full Open.Caused by Valve Stem Separating from Plug.Feedwater Flow restored.W/900607 Ltr ML20043D4711990-05-30030 May 1990 LER 85-002-01:on 850302 & 25,unplanned Actuation of Containment Purge Valve Isolation Occurred.Caused by Personnel Error.Caution Signs Placed on Radiation Monitors & Reset Button on Monitor Made inaccessible.W/900530 Ltr ML20043A7841990-05-16016 May 1990 LER 90-013-00:on 900416,manual Reactor Trip Initiated Due to Imminent Loss of Condenser Vaccum.Caused by Inadequate Administrative Guidance When Debris Collected on Trash Rack. Severe Weather Procedure revised.W/900516 Ltr ML20042G7201990-05-0707 May 1990 LER 90-012-00:on 900406,review of Steam Generator Blowdown Monitor High Radiation Alarm Setpoint Revealed That Setpoint Was Nonconservative.Caused by Administrative Deficiency. Correct Setpoint installed.W/900507 Ltr ML20042E6751990-04-20020 April 1990 LER 90-002-00:on 900322,Tech Spec Action Statement 3.3.3.10 Not Entered for Out of Svc Stack Gas & Particulate Radiation Monitor.No Particulate Radiation Increases Detected.Caused by Personnel error.W/900420 Ltr ML20042E1621990-04-0909 April 1990 LER 90-009-00:on 900309,automatic Turbine Trip W/Subsequent Reactor Trip Occurred Due to High Stator Cooling Water Temp. Caused by Failure of Mechanical Linkage on Fisher & Portor Controller.Controller Replaced w/spare.W/900409 Ltr ML17223A7901990-04-0202 April 1990 LER 89-009-01:on 891025,radiation Monitor RM 8262 Inlet Valve (2-AC-82) Found Closed.Caused by Personnel Error. Isolation Valve Opened,Sample Flow Restored & Radiation Monitor Restored to Operable status.W/900402 Ltr 1994-05-02
[Table view] Category:RO)
MONTHYEARML20024J3301994-10-0707 October 1994 LER 94-011-00:on 940908,manual Reactor Trip Initiated Due to MSIV Failure During part-stroke Test.Solenoid Valve & Number of Pins Replaced & MSIVs Tested satisfactorily.W/941007 Ltr ML20024J3291994-10-0303 October 1994 LER 94-027-00:on 940903,determined That Channel B Linear Range Nuclear Instrument Inoperable as Result of Connector J6 Being Disconnected from Jack.Connector J6 Reinstalled.W/ 941003 Ltr ML20029E5291994-05-13013 May 1994 LER 94-007-00:on 940414,determined That Valve Stroke Time Acceptance Criterion Exceeded System Response Time.Caused by Programmatic Error During Initial Startup.Corrective Action: Stroke Time Acceptance Has Been reduced.W/940513 Ltr ML20029E1361994-05-11011 May 1994 LER 94-007-00:on 940412,CRAC & Ebfs Were Inoperable Due to Previous Charcoal Testing Performed to Industry Std Different than Ts.Corrective Actions:Ts Changed to Reflect Newest Charcoal Testing procedure.W/940511 Ltr ML20029D8491994-05-0202 May 1994 LER 94-006-00:on 940407,plant Did Not Meet Requirements of LCO 3.7.6.1 Re Two Independent Control Room Emergency Ventilation Sys.Caused by Inadequate Work Organization. Corrective Action:Revised OP 2315A.W/940502 Ltr ML20029D6221994-04-29029 April 1994 LER 94-005-00:on 940401,determined That Both Facilities of Ebfs Had Never Been Tested in Accordance W/Ts.Caused by Program Failure/Personnel Error.Corrective Action: Surveillance Was Completed satisfactorily.W/940429 Ltr ML20029D2531994-04-28028 April 1994 LER 94-008-00:on 940329,discovered That Data in OPS Form 2604P-2,was Recorded Incorrectly.Caused by Program Failure, Procedure Deficiencies & Technical Error.Corrective Action: Recalculated ESF Equipment Circuit response.W/940428 Ltr ML20046C7771993-08-0606 August 1993 LER 93-010-00:on 930707,reactor Trip Input to Turbine Trip Portion of ESFAS Declared Inoperable Due to Inadequate Surveillance Testing.Test to Verify Operability Written & performed.W/930806 Ltr ML20046C2161993-08-0303 August 1993 LER 93-017-00:on 930701,possible Inoperability of Power Operated Relief Valve Blocking Valves Caused by Original Design Basis.Changed Designs & Performed tests.W/930803 Ltr ML20046B0311993-07-23023 July 1993 LER 93-012-01:on 930524,turbine & Reactor Tripped During Mussel Cook (Thermal Backwash) Due to Lack of Heat Removal Capabilities from Main Generator Stator Water Cooling Sys. Installed Thermoconductivity filler.W/930723 Ltr ML20045H8991993-07-15015 July 1993 LER 93-009-00:on 930617,determined That Suppl Leak Collection & Release Sys May Have Been Inoperable During Certain Weather Periods in Past.Caused by Failure to Account for Chimney Effect.Suppl Will Be sent.W/930715 Ltr ML20045H4021993-07-0909 July 1993 LER 93-007-00:on 930611,plant Mgt Discovered Reduction in EDG Fuel Oil Storage Capacity Per SER & Fsar,Constituting Event Outside Design Basis of Plant.Caused by Inadequate Design Interface.Temporary Tanker utilized.W/930709 Ltr ML20045H8921993-07-0909 July 1993 LER 93-005-01:on 930311,discovered That Automatic RPS Actuation Occurred on 930222 & Not Immediately Reported to Nrc.Caused by Personnel Error.Memo Sent to All Licensed Operators/Personnel Re Reporting requirements.W/930709 Ltr ML20045H8571993-07-0909 July 1993 LER 93-008-00:on 930614,one Channel of Electrical Environmentally Qualified Temp Monitor for Main Steam Valve Bldg Found Indicating Improperly.Caused by Personnel Error. Manual Logging of Temp initiated.W/930709 Ltr ML20045F5891993-07-0202 July 1993 LER 93-013-00:on 930603,noted That Main Turbine Generator EHC Sys Caused an Increase in Pressurizer Pressure,Resulting in Reactor Trip,Due to Closing of Intercept & Cv.Operators Performed EOP & Sys Performed as expected.W/930702 Ltr ML20045F6881993-07-0202 July 1993 LER 93-004-02:on 930222,reactor Trips on SG Low Water Level Occurred.Caused by Automatic Trip of MFW Pump B on Low Suction Pressure Due to High FW Flow Rates.Classroom Training on Main & Afwc Received by Licensed Operators ML20045D9041993-06-23023 June 1993 LER 93-012-00:on 930524,reactor Trip Occurred Due to Turbine Trip & Malfunction Caused Feedwater Regulating Valve a to Stay Approx 56% Open.Caused by Lack of Heat Removal Capabilities.Hand Wheels secured.W/930623 Ltr ML20045D8601993-06-21021 June 1993 LER 93-006-00:on 930525,two HPSI Discharge Check Valves Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Personnel Error.Test Written & Performed to Demonstrate Valve operability.W/930621 Ltr ML20045D9031993-06-21021 June 1993 LER 92-003-01:on 920207,discovered Potential Barrier Breach Via Direct Openings Around Main Feedwater Bypass Line Penetrations.On 920130,plant Entered Mode 4 W/O Encl Bldg Integrity.Erosion/Corrosion Exam Procedure Modified ML20045D3091993-06-18018 June 1993 LER 93-005-00:on 930520,cold Over Pressure Protection Sys Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Mgt Deficiency.Overlap Task Force Will Continue to Review Procedures Associated W/Reactor trip.W/930618 Ltr ML20045A4491993-06-0404 June 1993 LER 93-009-00:on 930506,inlet & Outlet skid-mounted Isolation Valves to Radiation Monitor Found Shut.Caused by Procedure Noncompliance by I&C Personnel.Personnel Will Review & Edit Radiation procedures.W/930604 Ltr ML20045A2321993-06-0101 June 1993 LER 93-008-00:on 930505,determined That Electrical Starter for Both Charging Pumps Inoperable.Caused by Program Failure.Administrative Controls Have Been Established to Ensure Minimum TS requirements.W/930601 Ltr ML20044C9191993-05-0707 May 1993 LER 93-002-01:on 930206 & 07,Train a & Train B CR Pressurization Sys Failed 18-month Surveillance Test, Respectively.Caused by Moisture in Air Banks & Pressure Oscillations.Air Banks purged.W/930507 Ltr ML20044C9331993-04-30030 April 1993 LER 91-002-01:on 910118,engineering Evaluation Determined That Operation of Four Vital 120-volt Ac Buses,On Alternate Sources,Unsatisfactory.Caused by Failure to Update TS to Reflect Configuration.Inverter Sys replaced.W/930430 Ltr ML19346B2411992-08-20020 August 1992 LER 92-018-00:on 920722,both RHR Trains Rendered Inoperable Due to Procedure Deficiency.Both Trains of RHR Restored to Operable Condition & Surveillance Procedures for Both Trains revised.W/920820 Ltr ML20024H3241991-05-24024 May 1991 LER 91-001-01:on 910110,electro-hydraulic Control Sys Failure Occurred,Causing Reactor Trip.Caused by Turbine Trip.Both EHC Pump Discharge Filters Changed Out & Pump B Replaced W/Spare pump.W/910524 Ltr ML20029C1281991-03-18018 March 1991 LER 91-004-00:on 910216,unexpected Trip of 'B' Steam Generator Feed Pump & Subsequent Manual Reactor Trip Occurred.Cause Unknown.Monitoring Capability Added to Sgfp Circuitry & Design Change made.W/910318 Ltr ML20029B6001991-03-0707 March 1991 LER 91-004-00:on 910205,leakage Found During Local Leak Rate Testing for Four Containment Isolation Valves.Caused by Improper Valve Seating.Valve Removed from Svc & Sent to Mfg for overhaul.W/910307 Ltr ML20029B6031991-03-0404 March 1991 LER 91-002-00:on 910202,setpoint Drift Identified During Testing of Main Steam Safety Valves.Caused by Inadequate Design.Nine out-of-tolerance Valves Reset within Specified +1% Tolerance ML20029B5981991-03-0404 March 1991 LER 91-003-00:on 910203 & 16,spurious Control Bldg Isolation Signals Received from Train a Control Bldg Ventilation Inlet Radiation Monitor.Caused by Equipment Malfunction.Detector replaced.W/910304 Ltr ML20029A6501991-02-19019 February 1991 LER 91-001-00:on 910117,discovered That Source Check Surveillance Procedure to Verify Operability of Beta Scintillation Radiation Detectors Did Not Meet TS Requirements.Surveillance Procedure revised.W/910219 Ltr ML20028H4261990-12-27027 December 1990 LER 89-005-01:on 890330,intermittent Connection While Sliding Module Into Position Caused Automatic Test Insertion Circuit to Send Signals Greater than Normal Pulse Thus Allowing Three SIAS Modules to actuate.W/901227 Ltr ML20028H4391990-12-27027 December 1990 LER 90-015-01:on 900919,inadvertent Isolation of Containment Isolation Valves Occurred.On 900920,inadvertent Actuation of Sias,Containment Isolation Actuation Sys & Encl Bldg Filtration Sys occurred.W/901227 Ltr ML20028H4271990-12-27027 December 1990 LER 90-021-00:on 901127,LCO Paragraph 3.0.3 Entered.Caused by Poor Communications.Mgt Reviewed Event & Events Leading Up to Incident & Concluded That Increased Awareness W/ Respect to Sys Status Must Be pursued.W/901227 Ltr ML20028H4401990-12-24024 December 1990 LER 90-019-00:on 900606,automatic Reactor Trip from Negative Flux Rate Signal Occurred Due to Dropped Control Rod.Caused by Broken Connection in Gripper Coil Power Cable.Connector Replaced & Power Loop checked.W/901224 Ltr ML20028G9421990-09-26026 September 1990 LER 90-012-00:on 900827,automatic Reactor Trip Occurred During Bypass Switch Operations.Caused by Operator Error. Procedure Sp 2601D Revised to Incorporate Separate Section on Performing calibrs.W/900926 Ltr ML20028G9111990-09-18018 September 1990 LER 89-008-01:on 891002,determined That Plant Failed to Perform Functional Check of Control Board Annunciators During Channel Functional Tests.Caused by Personnel Error. Procedures Revised Re Annuciator testing.W/900918 Ltr ML20044B0441990-07-10010 July 1990 LER 90-007-00:on 900611,discovered That Surveillance Procedure 2609E Re Encl Bldg Filtration Sys Testing - Refueling Not Performed Prior to Entering Mode 4.Caused by Personnel Error.Missed Surveillance performed.W/900710 Ltr ML20044A1581990-06-18018 June 1990 LER 90-017-00:on 900518,loss of Both Trains of HPSI Occurred.Caused by Cognitive Failure by Licensed Operator. Personnel Counseled on Causes of Event & Importance of Recognizing When Event reportable.W/900618 Ltr ML20043H2021990-06-15015 June 1990 LER 90-005-00:on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973.W/900615 Ltr ML20043G1031990-06-12012 June 1990 LER 90-016-00:on 900513,steam Generator B lo-lo Signal Generated Reactor Trip Signal,Causing Automatic Start of motor-driven Auxiliary Feedwater Pumps a & B.Caused by Inadequate Guidance.Procedure revised.W/900612 Ltr ML20043G3921990-06-11011 June 1990 LER 90-014-00:on 900519,manual Reactor Trip Initiated as Result of Anticipated Turbine Trip Due to Condenser Vacuum. Caused by Design Deficiency in That Traveling Screen Capacity Inadequate.Traveling Screen modified.W/900611 Ltr ML20043F7021990-06-11011 June 1990 LER 90-015-00:on 900512,feedwater Isolation Occurred While Opening Msivs.Caused by MSIV 2 Opening Faster than Other Msivs,Resulting in Swell in Steam Generator 2.Steam Generator Level Restored to normal.W/900611 Ltr ML20043F8261990-06-0707 June 1990 LER 90-006-00:on 900508,reactor Manually Tripped When Decreasing Levels Noted in Steam Generator 1 & Feedwater Regulating Valve Indicated Full Open.Caused by Valve Stem Separating from Plug.Feedwater Flow restored.W/900607 Ltr ML20043D4711990-05-30030 May 1990 LER 85-002-01:on 850302 & 25,unplanned Actuation of Containment Purge Valve Isolation Occurred.Caused by Personnel Error.Caution Signs Placed on Radiation Monitors & Reset Button on Monitor Made inaccessible.W/900530 Ltr ML20043A7841990-05-16016 May 1990 LER 90-013-00:on 900416,manual Reactor Trip Initiated Due to Imminent Loss of Condenser Vaccum.Caused by Inadequate Administrative Guidance When Debris Collected on Trash Rack. Severe Weather Procedure revised.W/900516 Ltr ML20042G7201990-05-0707 May 1990 LER 90-012-00:on 900406,review of Steam Generator Blowdown Monitor High Radiation Alarm Setpoint Revealed That Setpoint Was Nonconservative.Caused by Administrative Deficiency. Correct Setpoint installed.W/900507 Ltr ML20042E6751990-04-20020 April 1990 LER 90-002-00:on 900322,Tech Spec Action Statement 3.3.3.10 Not Entered for Out of Svc Stack Gas & Particulate Radiation Monitor.No Particulate Radiation Increases Detected.Caused by Personnel error.W/900420 Ltr ML20042E1621990-04-0909 April 1990 LER 90-009-00:on 900309,automatic Turbine Trip W/Subsequent Reactor Trip Occurred Due to High Stator Cooling Water Temp. Caused by Failure of Mechanical Linkage on Fisher & Portor Controller.Controller Replaced w/spare.W/900409 Ltr ML17223A7901990-04-0202 April 1990 LER 89-009-01:on 891025,radiation Monitor RM 8262 Inlet Valve (2-AC-82) Found Closed.Caused by Personnel Error. Isolation Valve Opened,Sample Flow Restored & Radiation Monitor Restored to Operable status.W/900402 Ltr 1994-05-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
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wYsI."mY[aSIMnNieNcompen7 N asY E n N Ni E .'N any P.O. BOX 270 HARTFORD. CONNECT 10VT 06414-0270 tervoast Neien* Enre, company (203)666-6000 February 14, 1990 MP-90-169 Re: 10CFR50.7?ia)(2)(i) 3 U.S. Nuclear Regulaiory Commission Document Control Desk Washington, D.C. 20555
Reference:
Facility Operating License No. NPF-49 Docket No 50-4.3 Liceissee Event Report 90-003-00 Gentlemen:
This letter forwards Licensee Event Report 90-003-00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(i), any condition prohibited by the plant's Technical Specifications.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: Stephen E. Scace Direct , Millstone Stat' n BY: Harry \ .H ne. \
v Millstone U(nl rvices Direc SES/PAF:tp
Attachment:
LER 90-003-00 cc: W. T. Russell, Region 1 Administrator W. J. Raymond, Senior Resident Ins >ector. Millstone Unit Nos.1, 2 and 3 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 hk
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~~~)vrs m v.s. comm.i. Exatetto suevitsion o.tri Tl no E DI l l l Aes,n Act mmn i 1 00. .c.s . .. .n. . , ,,,i.., .,ng.. e. iyn.w.ni.n i,n.s > o.3 On January 15, 1990, at approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, at 100G power (Mode 1), the Shift Supervisor (SS) discovered that the proper hre watches had not been estabhshed prior to removing the Deluge Systems for the "A" and "B" Train Reserve Station Semce Transformers (RSST) from service. This dehciency was found during a review of completed Automated Work Order (AWO) packages by the Shift Supervisor, immediate corrective action was to restore the deluge systems to operable status.
The root cause of the event was personnel error. The designated senior licensed operator (SRO),
responsible for reviewing and authorizing AWOs, failed to document the need for a hre watch patrol at the
- A" and *D" RSSTs. The hre watch patrol documentation was required at the time of AWO autMnzation. The Day SS failed to realire that a fire watch patrol had not been established at the
and "B" RSST dunnp his review of the hre watch log. +
As action to prevent recurrence, the Operations Department Supervisor has counseled the personnel invohed on attention to detail when removing hre detection systems from service. Procedural piidance to assist in determining the compensatory actions for removing Fire Detection and/or Suppression systems from ,
service, will be provided by April 15,1990.
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F ACUTY NAME (1) DoRET N.A4th m t rt4 yunt o efa 6*GI IN vt Ast P!** N Millstone Nuclear Power Station Umt 3 0l f,l 0l 0l 0l4 l2 l3 4l0 0l 0l 3 0l0 0l 2 OF 0 j .3 un of mo.. spec. .. rea,- c. use .umi.onai une to*m m A s, o n l, beWTfNiuf! f)I E \ Pfit On January 15, 1990, at approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, at 1009 power (Mode 1), the Shift Supervisor ,
dncovered that the proper fire watches had not been established prior to removmp the *A* and
- D" Train Reserve Stauon Services Transformer (RSST) Delure Systems from service. This dehtiency was found during a review of completed Automated Work Order (AWO) packages. :
The unit staff failed to fulfill the requirements of Techtlical Specification 3.7.12.1, " Spray and/or Sprmkler Systems," before exiting the associated Limiung Condiuon for Operanon (LCO). The duration of the esent was approximately 8 hourk.
On January 14, 1990, at approximately 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br />, the Fire Protection Console was declared ,
moperable upon indication of control system circuitry malfunction. Fire watch patrols were establahed in accordaner ulth the requirements of the Technical Specifications for all applicable local hre rone panels. On January 1$,1990, at approximately 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, the senior hcensed operator (SRO) designated for the review and authonzation of AWO packages, reviewed un AWO
- to perform repairs on the Fire Protection Console. The Delure Systems for the "A" and *B* train RSSTs were to be taken out of service, as one of the prerequisites for the planned repairs. Fire watch requirements were discussed between the designated SRO, the Day Shift Supervisor and the Millstone Station Fire Marshall to ensure proper bre watch patrols were invoked. Upon establishing fire watch requirements, the design;ned SRO authorired the AWO ternovmp the Deluge Systems for the " A" and "B* RSSTs trom service, but failed to piepare the documentation required to estabbsh the necessary hre watch patrols. The Day Shift supervisor reviewed the hie ?
watch log at approximately 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, but did not notice that fire watch patrols had not been established at either the *A* or "B" RSST, On January it3,1990, at approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, the on-coming shift supervisor, during his review of cernpleted AWOs discovered the fire watch patrol dehciency invoh1ng the *A* and *B" RSST Deluge System. As immediate corrective action, the Delupe Systems for the *A* and *B" Train RSSTs were returned to service, since repairs to the Fire Protection Console had been completed.
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- 11. Cnuse of Event The root cause of the event was personnel error. The designated SRO failed to prepare i documentation to establish a hre watch patrol at the " A" and
- B" RSST. The hre watch patrol '
documentation was required at the time of AWO authorization. The Day Shift Supervisor failed to realire that a hre watch patrol had not been estabbshed at the *A* and "B" RSSTs dunng his review of the hre watch log.
N4C Form 366A (6-$0)
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- UCENSEE EVENT REPORT (LER) '"jg,*g',*',,';g5l,,6Ml;'g,7tg,e.,, t TEXT CONTINUATION .no n.wi. u.n.p..nons tr.nen m.taan v s Nse .r tnWIM.m.ni vmp no em a n p.iU2fE$r'e'EEZ'EsMPoM ninoton oc roso3 o
F Act.fTY NAME t t) DOctET NJMisER G1 iFo y M rp ,ti } 6 AGE 0:
vtAn agutem. pqtm Alilktone Nuclear Power Station Urut 3 0lt,)0l0l0l4 2l3 9l0 0l0l3 0l0 0l 3 OF 0 l .1 nx,m ..-.... ..e ... - ~ac + m m A., m .
Ill. Atahsis of Eient .i e
This event is reportable under the requirements of 10CFR50.73(a)(2)(i), as a condition prohibited by the plant's Techmcal Specifications. Technical Specification 3.7,12d.,
- Spray and/or Spnnkler Systems," requires that fire watch patrols be estabbshed wnhm an hour, uheneser the Deluge ,
Systems for the
Fire suppression for the affected areas consists of (butomatic) heat actuated Deluge Systems. The ,
h secor:dary suppression system for the affected crea consists of the unit Fire Bntade. With the Delure System out of servae, fue suppression capabihties become degraded. Due to equipment location, the traffic of plant personnel in the affected area, and rouune inspections of the affected area, adequate warning of a hre was available to Operation department personnel All hydrant hose houses were operable for the duration of this event.
In the event of a hre in the affected area, a redundant source of off-8ite power was available (via the Normal Station Service Transformers (NSSTs)) throughout this event. The NSSTs are physically removed from the RSST, thereby precluding the compromise of both sources of off-site pour m the event of a fire in one area. Addiuonally, both the "A* and "B" Train Emergency Diesel Generators were operable throughout this evem, and therefore available to supply safeterslated plant loads in the event of a loss of off-site power, IV. Corrective Action immediate corrective action was to restore the deluge system for the "A" and *B" RSST to operable status. As action to prevent recurrence, the Operations department supervisor has counseled the personnel involved in this event, on attention to detail when removmg fire detection systems from service, in order to assist shift supervisory personnel in determining the compensatory actions required prior to removmg a Fire Detection and/or Suppression system from service, an Operations department procedure will be developed specifying the required actions to be taken.
The anticipated completion date for this procedure is April 15, 1990.
V. Additional Information LER 67-029, " Failure to Post Fire Watches Due to Operator Error " discusses an event in which fire watches were not properly instructed as to the boundanes of the patrol for areas where the Fire Suppression System was removed from service. The corrective actions / actions to prevent recurrence were to incorporate guidance in the procedure for deactivation of CO2 to clearly state the requirements of fire watches in multi-level areas, to require verification of a posted fire watch for AWOs performing work in areas harmg CO2 fire suppression, and to centralize the reFponsibihty of fire watches under the control of the Operations Department.
LER 8F-025. " Failure to Post Firewatch with Degraded Fire Protection Due to Procedural
' Deficiency," discusses an event in which an hourly fire watch was not established in the A Train
) 4160 VAC Smtchgear Room after fire detection had been degraded. The root cause of the event was personnel error, wherein a non-heensed operator inadvenently bumped a switch adjacent to the one being tested, in addition, the surveillance procedure did not explicitly hst the fire panel alarms expected during the test. The correctise action / action to prevent recurrence was to modify appbcable procedures to ensure proper local zone panel operation, prior to, and post testing, and to include the appropriate alarm response.
Nec Form 366A (6-60)
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LICENSEE EVENT REPORT (LER) '",'ol,"ga *ge'g,' Jy5l,,6&ff,5g ,',",,j'
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LER 68-027 *Mislocated Fire Wateb Due to Personnel Error," discusses an event in which are houri) fire watch was posted in the southern area vice the south HYAC area of the Engineered Safety Features Building, due to miscommunication between plant personnel. A memo was issued by the Operations Department Supervisor to all Shih Supervisors emphasizing the need for verifymg communicated information and the need to utihre all applicable procedures. A clear description of l fire detection tone locations was to be mcorporated into the applicable procedure by February 26, 1989.
LER 89-004, " Inoperable Fire Detection Due to Operator Error," discusses events where automatic fire detection in areas of the Containment buildmg and the Diesel Generator fuel oil vault had been unavailable due to miscommunication and an inadequate alarm evaluation. As corrective e actions / actions to prevent recurrence, all on-shift personnel would be briefed of the need for i prompt evaluation and response to all fire system alarms. In addition, a Task Force of personnel from the Engineering, Operations, and Instrurnentation and Controls departments, was formed to evaiuate Fire Protection and Detection system performance and to evaluate the human factors aspects of information provided to plant operating personnel. 1 Th: corrective actions in LERs67-029, 88-02$ and 88-027 were directed toward correcting specific deficiencies. The corrective actions in LER 89-004 were directed towards improving the performance of the Fire Protection and Detection system trom an operations and human factors -
aspect. The corrective actions / actions to prevent recurrence for the aforementioned events would not have prevented the event discussed in this LER. The reason being that personnel in this event were aware of the need to estabhsh fire watch requirements in the subject areas, but failed to ensure that the tequired compensatory actions were implemented due to a cognitive failure. The proposed corrective action will reduce the likelihood of the recurrence of a similar event by proceduralising the required compensatory actions for degraded fire detection and suppression systems.
Ells Codes '
Systems Fire Detectica System - IC Fire Protection System - KP I Comnonents Inter-Tie Transformers (RSSTs) - XFMR 1
i NRC Form 366A (6-691