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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
[Table view] |
Text
. 1 NORTHEAST imLITIES an-e =ce saen sueet. B-an conme=uem 3 N s N Y[a$ Ia' N t I [.e : cI[r>Un7 P.O. BOX 270
( 'y' t)$asISt NorveasteEb5c Nac,er Ene a companyvce$$cany HAATFORD. CONNECTICUT 06141-0270 (203 } 6E5-5000 April 30, 1993 MP-93-353 Re: 10CFR50.73(a)(2)(i)(B)
U.S. Nuclear Reculatorv Commission Document Control Desk Washington. D.C. 20555 '
Reference:
Facility Operating License No. DPR-65 Docket No. 50-336 ;
Licensee Event Report 91-002-01 l Gentlemen: .
e This letter forwards updated Licensee Event Report 91-002-01. l Very truly yours, t
NORTHEAST NUCLEAR ENERGY COMPANY
.M -
Stephebl . Scace mee i Vice President - Millstone Station -
SES KDD:dlr
Attachment:
LER 91-002-01 cc: T. T. Martin. Recion 1 Administrator
- P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos.1, 2 and 3 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 0 l}$
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Regulatory Comm:ssiors Wasningtos DO 2D555. anc to e the Paperwo-k Redaction Moje:1 (3153-0104L Ofbce of i Marnagement an: Bu@et. Vwastungton DC 20503 l
F ACUTY NAME p g DoWT NUM68 42) Wr* l i Millstone Nuclear Power Station l' nit 2 of 5] Dl o] ol3 l3 l6 1 l Od 0l 7 l T Tt.E it a Revised Interpretation of Electncal Distribution Technical Specification Requirements i r
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urEusEE ;ONT Aci FoA T+s tER re, yyg TELEPMONE NUMBER f
- w. A com i Keith D. Deslandes. Electrical Engmeer. Ext. 5521 2l0l3 4l4l7l~l1l7l9l1 l cOmE E oNE LNE FOR E AO% COMPONENT F AILURE DESCRSED N THtE REPORT !131 l 4
CAUSE SYSTEM COMPONENT cAUSE SYSTEM COMPONEN' 4
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SUR E VEN* Am REPORT EXPECTED dai MMD M W AR c PEc7r0 SUBM'SEION vES !!* Ws comove EXPECTEO SUBMSS'ON DATE! NO ! l l [
ABSTRACTt e tt: 14D0 soaces te . ap;remmatey Mteen see-space tweemer knest M6) f On January 15,1991 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> with the plant at 1003 power and normal operation. the plant uas notified ;
of the results of an Engmeering Evaluation that had determmed that c>peration of the four sital 120 voh !
Ahernating Current (AC) buses on their abernate sources is unsatisfactory. The requirements for the four vital j AC buses are desenbed in Technical Specification Section 3.S.2.1. l 6
This is being reported as an operation or condition prohibited by the plant's Technical Specificanon at this time i because of a rensed mierpretation of Technical Specihcation requirements. Previous interpretanon of the ,
requirements of Section 3.5.2.1 was that n required the vital 120 voh buses be energized to be considered operable. Followmg the review of the Engmeering Evaluation, the determination was made that since the I ahernate sources of power for the utal 120 veh AC buces are non-vital, then operation of the unit with these j busses powered from ahernate sources for a period of ume longer than allowed by the action statement ,
(8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) would make the busses moperable. j To avoid a recurrence, >pecific wntten instructions have been issued to inform the plant operating staff of the l revised mterpretation of Secuon 3.8.2.1 and of the requirements to enter the action statement if any of the four '
vital CO volt AC buses are powered from their ahernate sources. j In add: tion, the potential for similar conditions in other sections was reviewed. The review determined that f Section 3.S.2.3 which addresses Direct Current (DC) Distnbution and operation of the vital DC Batteries, Busses j and Battery Chargers, was also being interpreted non-conservauvely. This was due to the potential for using the j spare (swing) Battery Charger to power the vital facility 2 DC bus, even though this swing Charger is itself l powered from a vital facihty 14S0 voh AC bus. This specification does not address ahernate sources. ahhough l the swing Charger can be ahgned to power enher facihty DC bus. -i i
Changes to Section 3.S.2.1 of the Technical Specificauons, and modifications to the AC feed to the swing !
Charger are planned to provide the long term conecthe action for both conditions identified. I f
Similar Events: None geformas6 )
__________._______._______________Q
NRC Fom SMA 1.c S. NUCLEAR REGULAioRY coMMis$:oN APPRevEo OMS No. 340.-01Da i64M ExpAEs 4 30 g Esttmalec barcen te fesDonse to comDiv w'th tNs
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I. Decenntmn of Event j On January 15,1%1. at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> with the plant at 1009 power and normal operation, the plant was i' notihed of the resuht of an Engineering Esaluauon that had determmed that operation of the four utal 120 voh Ahernaung Current (AC) buses on their ahernate sources is unsatisfactory for meeting the requirements of Technical Specificanons. The required ahgnment of these four utal 120 voh AC buses is Jescribed m Technical Specification Section 3.5.2.1 ;
This is bemg reported as an operation or condnion prchibited by the plant's Technical Specification at t this ume because of a rensed mterpretation of Technical Specif canon requnements. Prenous i mterpretation of the requirements of Section 3.6.2.1 was that it required the sital 120 voh buses be energized to be considered operable. Followmg the review of the Engmeermg Evaluauon. the
- determinanon was made that smce the ahernate sources of power for the ntal 120 volt AC buses are i non-ntah then operation of the urut with these busses pouered from ahernate sources for a penod of time longer than alloued by the action statement (5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) would make the busses inoperable.
r To avoid a recurrence, specific uTitten instructions have been issued to inform the plant operating staff of the rensed mierpretation of Section 3.S.2.1 and of the requirements to enter the acuon statement if any ,
of the four nial 120 soh AC buses are powered from their alternate (ources.
In addinon, the potemia? Gr similar conditions in other sections was renewed. The review determmed that Secuon 3.5.2.3 whicn addresses Direct Current (DC) Distribut on and operation of the utal DC Battenes, Busses and Bauery Chargers, was a!so bemp mterpreted non-conservatnely. This was due to the potential for usmg the spare (swing) Battery Charger to power the vital facihty 2 DC bus, esen '
though this swing Charger is itself powered from a vital facihty 1480 voh AC bus. This specification does not address ahernate sources, althougB the swing Charger can be ahgned to power enher facilny DC bus though the use of a " Kirk Key" interlock. This could resuh in a loss of all Charger support due to a smgle failure, loss of the faci!ity 1 vhal 450 voh AC bus.
]L Cause of Esem The root cause of the mismterpretation of LCO 3.8.2.1 (A. C. Distnbution) is the failure to update the Technical Specihcations to reflect existing elecincal configuranons. The LCO in question was written when the 120 volt vna! AC system was comprised of four primary Inverters and two regulating transformers which were used as ahernate sources of power. The regulaung transformers were fed from vital 450 voh AC busses which can be fed from the emergency diesel generators. Thus the wording of the LCO. "a nial 120 veh bus shall be operaNe and supplied from a source of power other than the ;
diesel generator" corresponds to the original plant design (regulating transformers). Please refer to Figure 1.
The design of the ntal 120 voh AC sptem was changed in 1975 by replacing the regulating transformers, ,
as ahernate sources for facihty 1 and 2. with Inverters which are powered from the Turbme Battery.
Howeser, the Techrucal Specif cations LCO was not changed to incorporate the Turbine Battery as an I
.ahernate source of power. Thus, the interpretation was made that Inverters 5 and 6 were a primary source of power. Please refer to Figure 2.
Operating procedure OP 2345B does not allow 1merters 5 and 6 to supply the utal 120 voh AC bus as the same ume, since n was recognized that both Inverters 5 and 6 are supphed from the same source ;
(Turbme Battery) and hs failure would affect both facilities.
The root cause of the misinterpretation of LCO 3.S.2.3 (D.C. Distribution) is the failure to update the
~f echnical Specifications to reflect the potential for using the " Swing" Battery Charger to supply the Vnal facihty 2 D.C. bus. Since the " Swing" Charger is powered from the facihty 1 Vital 450 Voh A.C. bus, this abgnment could give the potential for a loss of all charger support on a facSty 1 Vital 450 Voh A.C. bus failure. Please refer to Figure 3.
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LICENSEE EVENT REPORT (LER) "'*""*""c":'*"'*"5'""
r TEXT CONTINUATION Comments
.,e neports tepa' ding DJ-Oen uar,.gement es, tem e1 0h m-54 8981C'the heOor U 5 Ncsar kegalatory Commiss#on. AasNngton De 20555 and to t*e Papewo a Aeoact on P creet (31sD-0104L Office of Management and 6a0 pet. WashsnptDo DC 2DSC3.
F AcUTV NAf6 OJ DOCKET NUVDER !?) tFAN erow. PAGE(3i YEAR NN
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emon Millstone Nuclear Power Station Urut *' - -
OF ol5{o{olol3l3l6 9l1 0l0l2 0l1 0l 3 0l7 TEXT m mye spac is rewee ss. Sonow me r m ase a A s; on UI Anah m of Etent The Technical Specihcation LCO interpretauon error is being reported, in recognition of the historical noncomphance based on our new mterpretation. pursuant to the requirements of paragraph 50.73 (a)(2)(iHB), which requires the reporting of any operauon prohibited by the plant's Technical Specihcanons.
During the operaung history of Millstone Unit 2 there was at least one time uhere Invener 5 (alternate power source for utal bus VA--10) was used to tupply the utal bus for extended penods of time. The Technical Specificati on LCO 3.5.2.1 was not entered dunng this period which requires the pnmary source of power to be repaired and supplying the utal 120 soh AC bus wnhm 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or commence a shutdown.
In considermg the safety consequences of this event, the engineenng evaluauon considered each electncal hne-up of the utal 120 veh AC system. Each conhguranon was evaluated for single failure concurrent with a Loss of Normal Power (LNPL Each elecincal conhgurauon, except for one, would have generated a reactor tnp concurrent with an automauc safeguards actuation signah The exception was the -
electrical conhguration where Inveners 5 and 6, which have a common supply (Turbine Battery), were supphng vital busses VA-10 and VA-20 respectisely, due to failures of imerters 1 and 2, and the Turbine Battery failed. The loss of power would cause a Reactor inp. The Engineered Safety Actuation System (ESAS) would lose the abihty to automatically stan safety equipment which mcludes the abihty to stan and load the Emergency Diesel Generators automatically. due to the loss of 120 voh AC power to both actuauon cabmets. In addition the Pressure Operated Rebei Yahes (PORV's) would open depressurizmg the primary system.
Historical records have shown that invener 5 and imener 6 hase never supplied the vital busses at the same time and is in fact prohibited by Operating Procedure OP 2345B. Therefore, the electrical configuration which could cause the disabhng of the automatic features of the ESAS, was never used as an operational electrical hne-up.
The D.C. distnbuuon system has been aligned where the facility I and swing Battery Chargers were supphng the two Battery busses. The Technical Specification LCO 3.8.2.3 was not entered during these periods, which requires the facihty 2 Battery Charger to be returned to service m 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or commence a shutdown. Houerer, during most mstances, the facihty 2 Battery Charger was available and could have been abpned immediately. If all Battery Charger support was lost the Battery busses have the capabihty of maintaming normal and emergency DC loads for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> without Charger support.
It should also be noted that . Millstone Unit 2 has never experienced a failure of a vital 460 volt AC bus, cable or a load center ciremt breaker.
There were no detrimental equipment effects resulting from the mcorrect interpretation of the Technical Specification LCO's.
IV. Corrective Action immediate corrective action was taken to estabbsh night orders which direct all operatmg shifts to enter the action statement for LCO 3.8.2.1 whenever an alternate source of power is suppling a vital 120 voh AC bus, and to enter the action statement for LCO 3.8.2.3 If the swing Battery Charper is suppling the facility 2 Battery bus.
A Technical Specification change request to revise the ume hmits for most backup power supp!y conf gurations within the action statement of LCO 3.S.2.1, will be submnted.
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to ine -ewas TEXT CONTINUATION ane sewis vanagem.,t eran:n x3ct u s N.ma-Reps ator y Comm' sten WasNncton Oc ?DSE5 anc to the Pape wo'* Aecu*:bo" Prcye:t l315Mcit 4 6 C'Oce of Management and bacpet We sNngton DC 205':3 F AOr JTv NAVE p DOC *IT tJJMEE P (2; trc.y w en e PAGE ;3 7
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Durmg the 1092 refuel outage fSteam Generator replacement), the complete Irnerter system was replaced wnh state of the art inserters. The replacemem of the Inverters should further improve the rehabihty of the nial 120 veh AC system Also. durmg the 1992 refuel outage. the "B" Battery Charger was teplaced unh one wh:ch has tuo independent sections. Each section can supph 400 amps and can operate mdependently or together, shanng the load. without a battery connected.
i The mstalianon of the new A" ar.d "C" (su mp; Bauery Chargers is scheduled to be completed during l the 1%4 refuel outage. The mstalianon was deferred to 1094 due to material and nme constramis.
Only one neu Bauer) Charger was aradable in ume f or mstallation. and the "B" ;,osnion was the best chose, since a single secuan fa: lure would force the unn imo shutdown. The old Bauery Chargers were tuo 400 amp unas connected together. and could not operate independently, or unhout a bauery connected. Two 400 amp unns capable of independent operanon. and which can meet all charging ,
requuemems, wdl pronde mcreated rehabiht) .
The newly de signed Bauer) Chargers from Cybrex provide a tuo section Charger umt. Each section can be fuuy mdependent of the other. h can also be shown that one single secuon is capable of providmg all DC bus reqwrements so for all charger features, except loss of 450 vehs AC, the two section unit creates an msta!!ed spare for each of the three Charger umit The addnian of an citernate 450 volt AC feed to the swing "C" Battery Charger was reneued and found to be extremely expentise to implement.
wnh s ery latie mcrease m rehabiht) or safety. Therefore, this concept has been abandoned.
Operator traming has been updated to reflect the dif ferem interpretanon of LCO 3.5.2.1 (A.C. ,
D:stnbution) and LCO 3.E.2.3 (D.C. Dstnbunon). Operators base also been tramed on the hmited use ,
of the swmg Battery Charger.
I Operatmg procedure OP 2345B has been changed to reflect the reused interpretation of the utal 120 soh AC sy stem.
V. Ad9inrM information .
Simdar LER's: none ,
Ell 5 Code idenuf ert -
- 1. ES AS - JE-XC-C560
- 2. Battery Chargers - EJ-BYC-P319
- 3. Inveners - EF-L JX- 5250 I 4. Bat:ery Buues - EJ-BU-GO52
- 5. 4160 sah vital busses - EB-BU-GOE2
- 6. 4E0 and 120 soh vnal busses - ED-BU-GO52 7 450 soh vnal breakers - ED-52-GOS2 l
1
- 8. 480 soh vital cab!c - ED-CBI -A35 5 l l
- 9. Regulating Transformers - EL-XFMR-5244 '
- 10. Turbme Bauerv - EJ-BTRY-C173 i
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'f N40 Form 366A APPROVE D OMB NO. 315D-Ot04 '
U.S. NJCLEAR REGJLAloAY CoMMSSm
$6-89) ExDiAE S. 4 OD '92 ;
Estimates buroen re response to compiy with this m' *2 *a * ' *:2 * *5 60 D "*- F **' c LICENSEE EVENT REPORT (LER) com""ents m regarding"na" roe"n e' stimate m sne"Reco os i TEXT CONTINUATION and Reports Manape nent e,anen ip-sach u s nacien- !
Fiegssto y Commissen, Washington. DC 20%5. and to i the Parwrw&k Recaction P p;ect (315D-0104L oftece of - t Management and Baopet. Wesmnpton. DC 20503. 5 F ACU'Y NAME p ; DOCKET NUMBER 12) ( Fm NUM4f m p F' AGE (31 -
VEAR . SED ENTEL fEMN MadBER BGJhE7t Millstone Nuclear Power Sunon ,
Unit " OF 0l 5l 0l 0l 0l3 l3 ls 9l1 0 l 0l 2 0l1 0l 5 0l7 TEXT of mee sca=e is rea, ee. use eationa NA: emm atu si n7 ;
i Pouer for VR11 Power for VR21 is from Diesel is from Diesel Generator Bus Generator Bas i wJJJJ ~'t_1 1_1_1_1 f _
VR11 1 - VR21 l I T I Th l JT'T {TA ESA5 Static VA {
Sensor g,3tje Aj j ~
f Switch Cabmet (SC) Switch N7 g j 30 l Nf' l 120VAC L
l i ,20VAC 1
g 3 r l 3 RPS
- VA30 & VA40 provides E INV pouer to one sensor INV !
3 Channe! C cabmet of the ESAS, a Channel D !
and one channel of '
the RPS L ; -l 125VDC 125VDC l l
i 125VDC *) El 125VDC i) E2 l
})
Batter)
Bus j Battery Bus i
9 -
125VDC l r 3 125VDC ;
r m t INV RPS 1 Channel A L > I-}'V RPS {
ESAS Channel B ,I l 120VAC L J ,
Staue Switch N{ l VA
'"~~
^T -1 2 ^*'uati n Cabinet (AC) 31, tic se v3 p SC ;
Switch A<J 20 p AC .
7111117
I I VR11 Power to one sensor . -t 12 3 3 3 7 1 gy 3 77 7 cabmet and one actuauon -
cabmet of the ESAS, i I -} -
l They also provide power _a 1 1 1 1 1 t, j prom Diesel to one channel of the RPS. t ,
Generator Bus From Diesel l Generator Bus l t
Ficure 1 - Pre 1975 Desien i gagum u A
P
o
, i NAC Form 366A US NUCLEAR 4EGJLATO4v COMM S, SON APPROVED OMB NO 3'5D-0104 46-89) E api;E S 4 '30 $2
. Esti~.ateo du'oen per response to comply eth tres
- t *' *' +c' *" 'easest 5e e n s rom 'a LICENSEE EVENT REPORT (LER) c""om n ims re;a em; pa oen estmate io in. meco os TEXT CONTINUATION .no neao ts Managemem e a,en (p-530,. u s. wae..r Repsistory Comm ssion. WesNepon DC 20555 anc to ,
i've P ape wo h Reduction Project (3 55-01041, Othee of i Managempat anc Bacoct W asNngtom DC 20503 '
F AC!JTv NAME M . DOC +2T NJVBL A 42 ) ( F R NUVM A + F 1 F AGE f31 I N N '
VEAA "msm e e ;
Mi!! stone Nuclear Power Station Umt -
0l5l0l0l0l3l3l6 9l1 0l 0l2 0l1 0l 6 OF 0l7 ,
Tex m r,ve spee. es rewec use amena. re,: vo m mA 5 ; MD Power for VR21 -
Power for VR11 is from Diesel !
2s from Diesel Generator Bus !
Generator Bus
~LU_U M W
VR21 i ,
VR11 1
/YrYYri. ESAS ESAS Sensor Static ^4 - 1 VA Cabmet (SC) Stauc ^d VA - SC Swnch /l 30 Switch g( 40 120VAC VA30 & VA40 prondes r 3 power to one sensor l 120VAC <
F ' '
cabmet of the ESA5. RPS 3gy RPS and one channel of INg, 3 Channel C the RPS Channel D 4
L ' L j 125VDC i 2 25VDC o
J l 125VDC El J 125voc a2 '
l Battery Batterv Bus Bus
~
4) 125VDC
i y ' power to one sensor cabinet and one actuation 125VDC INV cabinet of the ESAS. r ,
3 They also prowde power to one channel of the RPS. INV L > 2 120VAC ESAS ( s ESAS Stati'- S.' VA Sensor Cabmet (SC) I 120VAC _ SC '
- Actuauon Cabmet (AC) ': 3,a ^ VA Swnch Ae 10 20 - AC l
RPS r 3 F T Channel A RPS Channel B INV INV 5 6 TURBINE ( ;
L s z:- BATTERY Ficure 2 - Existinc Desien
.ua rym u (6-b9)
,,. . _ - . _ . ~ _ _ _ _ _
i NAO Form 36EA U.S. NUCLE AR RE SULATORY COMM:SSION APPROVED OM5 NO 3150-0104 (6-69)
, Estimatec turcen per response to comp!y with this i
'n'o "*'
- co' e:m reavest 50 D hrs. Forward j LICENSEE EVENT REPORT (LER) com"ments"repa'roing tween osurnate to tne newes - ..
TEXT CONTINUATION a,e r,eoorts manancment eranon ip-s3oi, u s Nucear !
Aeg4atory Coaimession, Washington. DO 20555. ano to the Paperwork Aecuction Proiset (3tSD-0104). Offee o' - '
f/ae,agement and Bucget. Wasnington. DC 20503. .
FACUTY NAME Di DDOKET NUMBER (2) t rp N#4pra ,63 PAGE (3) .,
vg4g sexwns. mwmos !
umsm ~
suam ,;
Millst i y" ,one Nuclear Power Station - -
0l 5l 0l 0l 0l3 l3 l6 9l1 0l 0l 2 0l1 0l 7 OF Uj7 j TEXT tte mo<e space is .-eau' e:: use ao$tional NRC Fo*m 36EA 6J D7)
L
.t i
I
.I i 9
i, I
El E2 f 480 Veh AC f) 4F0 Volt AC
"* U"5
]) , .) !
A" AC I
/ 7- r 3 AC }
A r 3
oc ,5g.mg J Banerv P.anen .B" i Charter Charger b"4 C'har'g er t j ,.
w > -
L ) 'I DC DC '
DC . l NO(N ) NC(NO) !
i i.)125 WC Al Kirk-Ke v
- )IM T -
Banery InterlocN Bauery Bus Bus }
i i
?
l I
t i
1 i
f s
fiTUTC _1 I
+
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6 I
NRC Form St>6 15-69)
. _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ __ ._.. _. , . , -