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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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Text
1 NORTHEAST UTILITIES o--a" Sans" Benc=a*==*
3 vesf e$.Yi$$bn Y s itN. rYcomp$n[ P.O. Box 270
( ' '
oEas [d$:$~[e vihcNpany Nonneast Noear Energy Company HARTFORD. CONNECTICUT OS141-0270 (203)SE5-5000 l May 7, 1993 MP-93-374 Re: 10CFR50.73(a)(2)(vii)
U.S. Nuclear Regulatory Commission Document Control Desk Washington. D.C. 20555 t
Reference:
Facility Operating License No. NPF-49 Docket No. 50-423 Licensee Event Report 93-002-01 Gentlemen:
This letter forwards Licensee Event Report 93-002-01 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(v:.i).
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
/
Stephe ENeace e
Vice President - Millstone Station SES/RJM:ljs
Attachment:
LER 93-002-01 cc: T. T. Martin, Region 1 Administrator P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos.1, 2 and 3 V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 120cn /
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8 9305140059 930507 PDR ADDCK 05000423 S PDR
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NAC Fo m 350 US NUCLE AR AEGJLATORY COMfASSION APPROVED OMB NC 3150-01Cd (6-89) EXPIRE S: 4J30'S2
[ Estimated b.roen per response to compiy with this if1 formation Cohe tron reasest: Sk 0 hrs Forwarc
- comments rega-ain; baroen estimate to the Reco'es LICENSEE EVENT REPORT (LER) ano Reports unnagement Branen io-53cn u S Nuc ear Repsatory Commission. WasNngton DC 23555. and to tese Paperwo n ReNedon Protect (3150-0Ku). Ott ce of Management anc Bsopet. Washinglen DC 2D503 F ACUTv NAME (1) DOCMI T NUMbtR (2J W *
- Afillstone Nuclear Power Station Umt 3 of sI of 01014 l 213 1lOFl 0l 4 I;TLk 14 }
Common A1 ode Failure of Control Room Emelope Pressurization Sgstem EVENT C ATE (5; LER NUMBFA 461 l REPOAT DATE (7 p OTef A F ACtLrTIES INVOL VED (81 F ACUTY NAME S voth DAY YEAR YEAR "Y MONTH DAY YE A:,
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0l2 ol7 9 3 9 l3 0l0(2 0l 1 0l 5 0l7 9l3 o; sj oj oj o; l l l OPE R ATING TH:S REPOAT :S BEING SUBM:TTED PVASVANT TO THE REQUIREVENTS OF 10 cFR l' IChe
- one or mo-e of tne fonowingM11)
E 1 20 402tbl 2c 402ic) 50 73(a):2)(w) 73,7'(b)
- powign 20 405(a)11 Hr) 50 35tc)(16 50.73taH2)(v) 73 71(c) f,$ 1l0l0 20 435
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Text, NRC Fo.m 366A) 2D 4LaH1Hiv) 50.73 !a H2H u) 50.73(aH2Hvm)(B) l 20 405(a)111 riv, 50 73taH2) hii) E.O. 73 :a H2 H x1 LCENSEE CONT ACT FOR TH S LER M21 NAME TELEPHONE NUMBER AREA CODE Robert J. AlcDonald. Engineer, Ext. 4742 2 0l3 4l 4l 7l-l 1l 7l 9l 1 COMPLETE ONE LINE FOR E ACH COMPONENT FAtLUAE DESCRIBED IN TH;S REPOAT (131 4 CAUSE SYSTEM COMDONENT NN[ I ! CAUSE Sv5TEfd COMPONENT $N[ eppYo U
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l l I I I I I I II I I I I l l II I I I I I III I I I SUPD EMENT AL REPORT EXPECTED n43 MONTH DAY YEAA SUBMJSSiON YES af yes. comp!ete EXPECTED SUBMISSION DATE) ^
NO l l l ABSTRACT (Lime 11c 94D0 spaces, . e., ap;>roxamatory f.fteen singie-space type *ntten bnes) (15)
On February 7,1993, at 1938 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.37409e-4 months <br /> with the plant in Afode I at 1009 power the A Train Control Room Pressunration System failed its 16 month pressurization surveillance test. On February 6th the B Train had imtially failed its surveillance test. An imestigation revealed two potential common mode failures and both trams were declared inoperable pending further invesupation.
a
- The first potential common mode failure is freezing of the pressure regulating vahe caused by moisture in the 4 air banks. The second common mode failure is pressure oscillations unthin the control room envelope which cause the differential pressure to period >cally fall below the .125 in wg acceptance enteria for brief periods of time.
The immediate correctne act on was to place the Control Room in filtered recirculation in accordance with i Technical Specification 3.7.8.b.1. The B Train surveillance was satisfactorily performed after a throttle vahe was opened further. The air banks were purged and refilled with dry air to reduce the dewpoint.
l e
NRc Form 360 (6-69)
,- -- - - - -- . ~
NRc to m 3664 t, 5, NJOLg Aq AggggaTogy coyy;334py APPAoVED eMB No 3150-01Da 16-6rd E XPIRE S 4 /3e $2 Estimatec burcen pe response to comply wim tNs pCENSEE EVENT REPORT (LER) ' *'
- c**:t o ' **$ 610 ""5 ""**'c c"om"m"ents're; arcing'buroen e' stimate to the Aeso os TEXT CONTINUATION a,o senyts uar.apement s.a,=n m43n u s. Nacien.
Regu*atory commission Wannin; ton. DO 20sss- and to
! we Pape wvA Aeouction %ect i31K4%. Othce ct unnagement ano Buopet Wasmneton. DO 20Sc3 acm v Naut m occwri Nuustwa um ouuna o F^as m N N VEAR "wsm e mapi Millstone Nuclear Power Stauon !
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0l 5l 0l 0l 0l4 l2 l3 9l3 0l 0l2 0l0 0l 2 0l4 TEYT Of r o-e space 4 rease: ae aco<tio ai NRc Form 366A si (17)
- 1. Deermtion of Event On February 7,1993, at 1936 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.36648e-4 months <br /> with the plant in Mode 1 at 100cc power (2250 psia and 557 l degrees Fahrenheit), the A Trair2 Control Room Envelope Pressurization System failed the 16 month l prenurizauon suneiilance test. On February 6,1993, the B Train had imtial!y failed and then passed the same surveillance test. On February 11, 1993, both trams were declared inoperable based on a potennal common mode failure of the system.
As immediate correcthe action the controi room envelope was placed m fihered recirculation in ;
accordance with Technical Spec:fication 3.7.S.b.1.
i Oscillations m the control buildmg envelope pressure on each train resuhed in differential pressures !
dropping slightly below the acceptance critena dunng retests. These d:ps occurred on a cyclic basis 5 to S !
times over the one hour duration of the test and resuhed in differential pressures slightly below the accertance criteria for penods of thiny seconds to two minutes.
After the air banks were refilled with known dry air, the same oscillations in control room pressure occurred.
- 11. Caute of Event The root cause of the initial B bank failure was thought to be moisture m the bottled air system which condensed and froze at the pressure regulating valve (3HVC-PCV6SB), during system discharge. Further mvestigation determined that although thi potential exists for introducing moisture into the system, it probably did not factor into the failure of the surveillance tests on either train.
The root cause of the pressure oscillations was equipment failure, specifically misoperation of another l
component. The pressure oscillations were determined to be caused by temperature changes within the control room envelope which were the result of hunting of the B train chilled water valve control loop in the air conditiomng system. The loop response to slight changes in control room temperature was a rapid and gross repositioning of the valve. The result was dramatic oscillation of the chilled water valve.
The control room pressure oscillauons mirrored the chilled water valve movement, as the valve opened the pressure decreased and as the valve closed the pressure increased.
l 111. Analvcic of Event This event is bemg reported in accordance with 10CFR50.73(a)(2)(vii) as an event where a single cause or condition caused two independent trains to become inoperable in a single system designed to mitigate the consequences of an accident. Pressure oscillations caused the control buildmg envelope differential pressure to penodically drop below the acceptance cnteria of .125 in wg. The dips were temporary and the control room pressure remains positive relative to outside.
On Febntary 7,1993 the A Train failed the surveillance test and was declared inoperable. LCO 3.7.6.a was entered for one train of Control Room Envelope Pressurizauon inoperable. On February 11, 1993, after an investigauon determined a potential common mode failure the B Train was also declared inoperable. The control building envelope was placed m the filtered recirculauon mode in accordance with Technical Specification LCO 3.7.B.b.1.
Each train of the Control Room Envelope Pressurization System is designed to pressurize the control room emelope to .125 in up or greater for one hour in the event of a Control Building Isolation (CBI) signal. After one hour the Emergency Filtration System is staned and provides filtered air under a slight positive pressure to the control building envelope.
The Safety Significance of this event is low because fihered intake was always atailable and the control room pressure remained positive in all tests of the pressurization system.
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NAc F.o m 36EA U S. NUOLEAR REGU; AToRV CoMMS SioN APPROVED OMB NO. 3'5r-0104 6 (bFC EXPAES. 4 '30 $2 i Estimatec beoen per resoonse to comoty eth this
- "**"c *:'**** 60 0 "' F"**'8
. LICENSEE EVENT REPORT (LER) co nments reg"a cin; o"scen" estimate to the Recoecs TEXT CONTINUATION .no seoons uanagement stan=n a-53m. U S Nuc esar
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- more soace is rease: a5e acomonat Nac Form 36E A s; (1D IV. Corrective Amnn The immediate correcure action after an investigation determined a potential common mode failure was '
to ceclare both trams of Control Room Fnvelope Pressurizauon System inoperable, enter LCO 3.7.5.b.1 '
and place the Control Building Emergency Filtration System mto operation m the fihered recirculation mode. !
a Samples of the air in the air bottles of both trains tested at dew points around minus 40 degrees !
i Fahrenheit at atmospheric pressure, which corresponds to approximately 70 degrees Fahrenheit at -
l 2250 psig. Excess moisture could potenually enter the system due to improper blowing down of the condensate traps or from purifying cartridges which have exceeded their useful life. The system design i does not include drying capabilities other than the moisture removal capaeny of the compressors. .
l j
The air banks were purged with dry air after the compressor punfier cartridges were replaced. The air l banks were charged wnh air which tested at better than minus 60 degrees Fahrenheit dew point. An j
, mspection was performed on one of the lower air bottles for the presence of moisture or corrosion l caused by the presence of moisture. The inspection determmed that no moisture was present in the l bottle and that only two small areas of surface discoloration were present. l Dunng testmp to determine the catise of the oscillations, the A Train pressure regulating valve !
f 3HVC*PCV66A) failed in the open position. The valve was disassembled and n was determmed that a ,
- dowel pm in the disc and stem assembly had failed. The vahe was replaced, tested and returned to l service.
j Once the B Tram chilled water control loop was identified as the cause, the loop was tuned to respond l
- in a more gradual manner to temperatures off of setpomt. The A train was renfied to respond i appropriately to temperature changes. Subsequent pressurization tests showed very stable readings for ;
control room pressure and chilled water valve position for each train of Control Building air conditioning.
Action to Prevent Recurrence The chilled water valve controller tuning will be checked during periodic calibration of the loops. The surveillance procedure has been revised to include a prerequisne step to notify Engineering prior to ,
performing this surveillance test. This will allow for comprehensive trending of system performance. i I
Target Rock, the pressure control vahe manufacturer was contacted in regards to the failure mode of the valve. No preventative maintenance is scheduled on the valve as a result of this failure due to the i infrequency of similar failures. An NPRDS search did not identify any similar failures.
l The potential for introducing moicture into the system was discovered during this investigation.
1 Dewpoints obtained during and after charging evolutions in March and April 1993 hase consistently been in the -60 to -80 degree Fahrenhen range. Dewpoint samples will be obtained during charging of the system and periodically at the bottles through the summer of 1993. An evaluation will then be performed to determine long term correctise action such as installing an air receiver with drainage capabihties or installmg a dew point analyzer.
V. Additional Information a
l Licensee Event Reports submitted which discuss related events are as follows. ,
i LER Number Title 92-004 Control Room Pressurization Valves Closed Due to improper Verification 1 f7-005 Control Room Pressurization Surveillance Failure Caused By
- Mispositioned Throttle Valve Due to Personnel Error garm ass 1
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I T AC gorm 36EA u S. NUCLEAR AEGULAToRY OOMM:S S!ON ADPROVED oMB NO 375D-0104 l (6-09; ** E APiRE $ 4 /3C /02 j l
Estimatee bu-pen per response to compiy with thrs i
""o"'*t o" co'*o'* '*od 6 C n'5 F o' **'o j -
- LICENSEE EVENT REPORT (LER) CDmmertts teQBr0mg'DurDen"estinale 10 the AeCDrCB
, TEXT CONTINUATION ,,e ne3o,t ua,.peme,t Branen t;-53m. u s. tweae !
I Repu: story Oomm'sson. Wasmngton. DC 20555. anc to i tw Faoerwork Recucten Prcre:1 (3150-01D41. C%ce of !
l t/anagement anc Buopet Wasnmpton. DC 20503.
FAOLr*Y NAVE f1j DDOWET NJMTdA , , t rm N3Mgrm 4, PAGE(3, ;
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Millstone Nuclear Power Station -
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- TEXT 01 more space is rea.wed. use and tenai NRc Form 350A s) (17)
LER 3-92-004 documents an event where one train of the Control Room Envelope Pressurization system was isolated by the closure of two manual valves. The mispositioning of the valves was discovered dunng the performance of the monthly vahe hneup suneillance. The root cause was improper self verification i of valve posmon after a charging evolution. Correctise action was a program to stress the importance of self verification.
{
LER 3-57-005 documents an event where the A Train of the Control Room Envelope Pressurization l system fatled the pressuriranon surveillance test because the throttle vahe downstream of the pressure !
control vahe was opened too far. The root cause was personnel error and procedure deficiencies.
Correcure action was to place a tag on the throttle valve for each train which specifies the required ,
procedurally controlled position of the valve. The incident was also reviewed by all operating personnel. !
Ells CODES {
f Svnems Comnoner tc l l l l Control Room - VI Pressure Control Valve - PCV l
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1 i
FF40 Form 3b6 15-bO)
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