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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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1 Northeast Rope Ferry Rd. (Route 156). Waterford, CT 06385 gsf Nuclear Energy Millstone Nuclear Power Station Northeast Nuclear Energy Company P.O. Box 128 Waterford, CF 06385-0128 (203)444 -4300 Fax (203) 444-4277 The Northeast Utilities System Donald B. Miller Jr.,
Senior Vice President - Millstone Re: 10CFR50.73(a)(2)(i)(B)
April 29, 1994 MP-94-292 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Reference:
Facility Operating Ucense No. DPR-65 Docket No. 50-336 Licensee Event Report 94-005-00 Gentlemen:
This letter forwards Licensee Event Report 94 -005-00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(i)(B).
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: Donald B. Miller, Jr.
Senior Vice President - Millstone Station f ,
BY:
ML hes 'i v &v H. rry F. p Director illstone Unit 1 DBM/cic
Attachment:
LER 94-005-00 cc: T. T. Martin, Region i Administrator P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1,2 and 3 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 7 f 9405090o58 940429 PDR #
ADOCK 0500o336 S PDR [I
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NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROtfED BY OMB NO. 3150-0104 (5-94
- EXPlRES: 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTTH THIS INFORMAftON COLLECTION REQUEST. 50 0 HRS FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER) = ES M , NFORMA nuet m %DG MI ION
. WASHINGTON. DC 20555 - 0001 AND TO THE PAPERWORK REDUCTION
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(S . . ~ -., o-a,am .- 25'Tiema FACIUTY NAME (1) DOCKET NUMBER (2) PAGE (3) 1 Millstone Nuclear Power Station Unit 2 05000336 1OF3 TITLE (4)
EBFS Surveillance Requirements Not Satisfied EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INv0LVED (8) !
j MONTH DAY YEAR YEAR SE NTIAL R S MONTH DAY YEAR FACluTY NAME DOCAET NUMBER ,
05000
{ * * "*"' """""""
0*' '9
" 94 04 01 94 94 - 005 - 00 05000 OPERATING THIS REPORT IS BEING SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR i: (Check One Or more) (11) b 20 402(b) 20 405lc) 50 73:a)2(M 73 71(b) 4 i POWER 20 40$ca)(1)0) 50 36(c)(1) 50 73(a)(2)M 73 71tc) 20 405:a)(1101) 50 36(c)2 50 73;a)(2)MQ OTHER 20 405ta)0)ps) X 60 78'a)(2)(i) 50 73(a>mus)<A) (S .cis m Aoa fl
- b.o.o* and m T.iracext, NRC Fonn 366A) 20 405(a)p)M 50 73ta)(2)(a) 50 73(a)(2)MI)(B)
- 20 405ta)d)M 50 73(a)(2)fhti 50 73<a)2(x)
. LICENSEE CONTACT FOR THIS LER (12)
NAME TFLEPHONE NUMBER (Mclude A es Codel j William J. Temple, Site Licensing (203) 437- 5904 i
j COMPLETE ONE IJ 4E FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
REPORTABLE REPORTABtf CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS CAUSE SYSTEM COMPONENT MANUFACTURCR TO NfEDS 4
1 i
SUPPLEMENTAL REPORT EXPECTED (14) "O" "
EXPECTED I YES NO SUBMISSION Of yn compete EXPECTED SUBMISSION DATE) X DATE (15) l i
ABSTRACT fumit to 1400 spacu i . . apommm iy is smy.-apaced iype-men ines) ps) 4 At approximately 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, on April 1,1994, it was determined that both facilities of the Enclosure Building !
j Filtration System (EBFS) had never been properly tested in accordance with Technical Specification
, Surveillance 4.6.5.1.a. Technical Specification Surveillance 4.6.5.1.a requires that the EBFS system be i demonstrated OPERABLE, in part, "by verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the system I heaters on." The existing surveillance procedure performs this test with the system operating in Auto, however, i
the heaters only energize when the moisture control switch senses a relative humidity greater than 70% )
Consequently, the heaters would not be energized for the required 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run if the relative humidity j was less than 70%
1
' This condition resulted in both trains of EBFS being considered inoperable and the plant being outside the a Umiting Condition for Operation (LCO) for the EBFS system. The plant entered Technical Specification Action
] Statement 3.0.3 and Surveillance 4.0.3. A bypass / jumper was processed to jumper out the moisture control switch and to energize the heaters continuously. The 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run was then performed satisfactorily for both trains of the EBFS system.
l The root cause of this event was program failure / personnel error resulting in procedure deficiencies. The failure to
, account for the actual system operating configuration during development of the surveillance procedure resulted I in the failure to incorporate into the surveillance procedure, a method to ensure that the system heaters operate continuously for the required 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run.
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NRC Form 366 (5-92)
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NRc Forrn 366A U.S, NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 3150-0104 (5-92) EXPIRES: 5/31/95 LICENSEE EVENT REPORT (LER) 'EEEN c E"is'" "'IEs 7mE cTENis"REiEi
, TEXT CONTINUATION "VE *EN$'ri eR .'"'j"'EcI"E EoIf"Av' N"u^uYs"sE
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WASIBNGTON. DC 20503 FACRJTY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (31 YEAR H N E Millstone Nuclear Power Station Unit 2 05000336 94 - 005 - 00 02 OF 03 TEXT m more space a requeed. use addinonal copies of NRC Form 366Al (17)
- 1. Descriction of Event At approximately 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on April 1,1994, while in Mode 1, at 99.8% power, the plant was notified by the NRC Resident inspector, that a problem existed with the surveillance procedure for the Enclosure Building Filtration System (EBFS). The inspector questioned whether compliance with the Technical Specification requirement for running the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the system heaters energized was being satisfied. A subsequent review of the EBFS design drawings indicated that the system heaters would only be energized when the moisture control switch contacts close. The surveillance procedure performs this test with the system operating in Auto, however, in this operating mode the heaters only energize when the moisture control switch senses a relative humidity greater than 70% Consequently, the heaters would not be energized for the required 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run if the relative humidity was less than 70% Based on this,it was determined that both facilities of the Enclosure Building Filtration System (EBFS) had never been properly tested in accordance with Technical Specification surveillance 4.6.5.1.a.
Technical Specification surveillance 4.6.5.1.a requires that the EBFS system be demonstrated OPERABLE, in part, "by verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the system heaters on."
This condition resulted in both trains of EBFS being declared inoperable and the plant being outside the Limiting Condition for Operation (LCO) for the EBFS system. The plant entered Technical Specification Action Statement 3.0.3 and Surveillance 4.0.3. Because the current design of the EBFS system does not allow for continuous energization of the system heaters, a bypass / jumper was processed to jumper out the moisture control switch and to energize the heaters continuously. The 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run was then performed satisfactorily for both trains of EBFS. There was no automatic or manually initiated safety system actuations as a result of this event.
- 11. Cause of Event The root cause of this event was program failure / personnel error resulting in procedure deficiencies. The failure to account for the actual system operating configuration during development of the surveillance procedure resulted in the failure to incorporate into the surveillance procedure a method to ensure that the system heaters operate continuously for the required 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run. This event was classified as a program error (procedural deficiencies / lack of detail), because the surveillance procedure did not require or provide a method to ensure that the system heaters remained energized during the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run, and also as personnel error (inattention to detail), because the operation of the system heaters in conjunction with the moisture control switch was not recognized or accounted for during the development of the surveillance procedure.
Ill. Analy11LOMv9nt Based on the event investigation, a determination was made that the surveillance procedure for the performance of Technical Specification 4.6.5.1.a was inadequate in that it did not fully test the EBFS system by verifying that each train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the system heaters energized, and that consequently, both facilities of EBFS had never been properly tested in accordance with the requirements of this surveillance. This is reportable under the criteria of 50.73(a)(2)(i)(B), any operation or condition prohibited by the plant's Technical Specifications. The surveillance procedure operates the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, however, due to the system design configuration, the heaters were considered energized as an automatic function, cycling on as the moisture control switch sensed a relative humidity greater than 70% This design condition has existed from original construction.
NRC Form 366A (S-92)
\
l
. i )
NRC Form 366A u.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 3150-0104 (5-92) EXPIRES: 5/3'i/95
^
LICENSEE EVENT REPORT (LER) EEEJk" Su"isI"Ef&"i' 'ros"# CE$s"E"AR?M l TEXT CONTINUATION E '8,u"E7IMj"'UCE ^ReGEro"Ry' EEsE P 5 0 CE OF W GE NT AND DG WASHINGTON, DC 20503 FACUTY NAME (1) DOCKET NUMBER (2) LER NUMBER 16) PAGE (3)
WAR > MB NU BF Millstone Nuclear Power Station Unit 2 05000336 94 - 005 - 00 03 OF 03 TEXT p mare epace m reqwat use addmonai copies ol NRC Ferm 366A) (1 F)
There were no safety consequences as a result of this event. This conclusion is based on the fact that the system remained available to perform its intended post-accident ESF function and no degradation of the system or its components existed. The subsequent surveillance performed verified that the system heaters l were functional and that the system was OPERABLE. At no time were any safety systems out of service due to this event. Additionally, while the system heaters are designed to maintain and control the relative
, humidity of 70% to ensure the effectiveness of the activated carbon absorber section of the EBFS system, l the effectiveness of the activated carbon absorber section of the EBFS system is tested at a 95% relative l humidity (value required without credit taken for safety grade heaters), in accordance with the testing l criteria specified in Regulatory Guide 1.52, and would have retained its effectiveness even without heater j operation.
IV. Corrective Action l
Following the event discovery on April 1,1994, immediate corrective action was to declare both trains of l EBFS inoperable. A temporary electrical jumper was then installed across the EBFS moisture control l switch to ensure that the heaters would be continuously energized when EBFS was running during the surveillance. The surveillance was then repeated for the required 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> run. The surveillance was j completed satisfactorily for both trains of EBFS.
To prevent recurrence, the surveillance procedure is being revised to include steps to require installation of a temporary electrical jumper across the moisture switch each time this surveillance is performed to ensure that the system heaters remain energized for the entire 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance run. Additionally, as a long term corrective action, a design change is being evaluated to consider the installation of a permanent moisture control switch key lock bypass switch.
V. AdditionalInformation There were failed components associated with this event.
Similar LERs - None.
Ells Codes Enclosure Building Filtration System - BH NRC Form 366A (S-92)
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