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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D6571994-05-0606 May 1994 LER 94-005-00:on 940407,chain Locking Mechanism on CP Suction Isolation Valve,Was Found Broken.Caused by Personnel Error.Corrective Action:New Chain Placed on Valve Handwheel & Chain Locking Mechanism intacted.W/940506 Ltr ML20029D8031994-05-0404 May 1994 LER 94-003-00:on 940404,two Flow Orifices Were Improperly Installed.Caused by Improper Installation of All Accessible Flow Orifices.Personnel Performed Procedure Ost 1.6.4 Correcting Improperly Installed orifices.W/940504 Ltr ML20046B5481993-07-30030 July 1993 LER 93-012-00:on 930702,discovered That Hydrogen Analyzer Inoperable During Quarterly Performance of Calibration Procedure.Test Personnel Contributed to Cause of Event.Test & Calibration Procedures Will Be revised.W/930730 Ltr ML20045J1201993-07-19019 July 1993 LER 93-011-00:on 930619,ESF Actuation Letdown Isolation Occurred While Synchronizing Main Unit Generator.Caused by Cooldown of RCS Due to Steam Demand.Plant Stabilized within Three Minutes & Pressurizer Level restored.W/930719 Ltr ML20045G4591993-07-0808 July 1993 LER 93-010-00:on 930614,determined That TS Surveillance on SI Accumulator Samples Missed Due to Draining & Refilling Accumulators Several Times During Outage.Accumulators a & C Immediately sampled.W/930708 Ltr ML20045F4711993-07-0202 July 1993 LER 93-009-00:on 930607,high Radiation Area Barrier Was Unlocked Due to Personnel Error.Comprehensive Confirmation Survey Performed,Personnel Interviewed & Task Force Formed. W/930702 Ltr ML20044F1541993-05-21021 May 1993 LER 93-007-00:on 930423,discoverd That Original Piping Did Not Conform to Design Code Requirement.Caused by Design Deficiency.Headers Fitted W/Code Approved End Caps & Tested & Now Conform to Design requirements.W/930521 Ltr ML20044F1521993-05-21021 May 1993 LER 93-008-00:on 930423,leakage Detected Through Two Check Valves in Chlorine Injection Line.Caused by Failure to Include Valves in ASME Section XI Testing Program.Check Valves Added to ASME Testing program.W/930521 Ltr ML20044D5251993-05-14014 May 1993 LER 93-006-00:on 930415,two Operators Entered Posted Area W/O Radiation Monitoring Device & Entered Locked High Radiation Area & Left Barrier Open.Caused by Personnel Error in Judgement.Operators counseled.W/930514 Ltr ML20024H1191991-05-15015 May 1991 LER 91-012-00:on 910415,excessive Max Operating Pressure Differential for Selected Solenoid Operated Valves Noted. Caused by Design Deficiencies.Equipment Mod Initiated to Replace Solenoid valve.W/910515 Ltr ML20029B2541991-03-0404 March 1991 LER 91-005-00:on 910131,steam Leakage in Auxiliary Feedwater Pumproom Caused ESF Actuation.Caused by Personnel Error. Control Room Operator Closed Steam Supply Isolation Valve to Stop Steam Leaking & Event Will Be reviewed.W/910304 Ltr ML17286B2651991-02-14014 February 1991 LER 90-006-01:on 900605,containment Isolation Valves Exceeded Stroke Time Limit,Per Tech Spec 3.6.3.1.Caused by Deficient Surveillance Program.Surveillance Procedures Revised to Include Stroke Time requirements.W/910214 Ltr ML20028H7391991-01-23023 January 1991 LER 90-007-01:on 900622,containment Entry Performed to Determine If Flanges Installed,Per Info Notice 90-019. Flanges Immediately Removed.Caused by Procedural Deficiency. Transfer Canal Draining Procedures revised.W/910123 Ltr ML20024F7441990-12-14014 December 1990 LER 90-021-00:on 901113,ESF Actuation & Feedwater Isolation Occurred During MSIV Stroke Testing.Caused by Operator Error.Feedwater Isolation Signal Reset & Isolation Valves reopened.W/901214 Ltr ML20024F7431990-12-14014 December 1990 LER 90-023-00:on 901114,ESF Actuation & Feedwater Isolation Occurred in Response to Opening Condenser Steam Dump Valve. Caused by Operation of Steam Dump Sys in Steam Pressure Control Mode.Signal reset.W/901214 Ltr ML17285B4731990-07-18018 July 1990 LER 90-007-00:on 900622,refueling Cavity Drain Flanges Found to Be Installed During Operation.Caused by Deficiency in Transfer Canal Draining Procedure.Procedure Revised to Verify Removal of Flanges After Canal drained.W/900717 Ltr ML20043G5771990-06-15015 June 1990 LER 89-017-02:on 891218,atmospheric Steam Relief Valve C Opened to Lower MSIV C.Caused by Swell Phenomena Experienced After Opening MSIV C.Feedwater Isolation Signal Reset. W/900615 Ltr ML20043B5171990-05-23023 May 1990 LER 90-004-00:on 900423,inadvertent ESF Actuation Occurred During Safeguards Protection Sys Testing.Caused by Personnel Closing Breaker Before Resetting Safety Injection Sys Signal.Signal reset.W/900523 Ltr ML20043B5201990-05-23023 May 1990 LER 90-005-00:on 900423,inadvertent ESF Actuation Occurred During Quench Spray Flow Switch Calibr.Caused by Error in Procedure Resulting in Installation of Two Leads on Same Terminal.Discharge Valves opened.W/900523 Ltr ML20043A4991990-05-16016 May 1990 LER 88-005-01:on 880219,startup Feedwater Pump Started, Causing Current Surge That Actuated Overcurrent Relay for Emergency Response Facility Transformer 3B.Caused by Faulty Transformer Relay.Relay replaced.W/900516 Ltr ML20012E6681990-03-29029 March 1990 LER 90-006-00:on 900227,plant Operation in Excess of Licensing Basis.Caused by Failure of Computer to Synchronize File Addresses in Task 3D.Heat Balance Calculations Reverified Using Data from Plant Variable Computer ML20012C4141990-03-14014 March 1990 LER 90-002-00:on 900117,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.On 900119, Discovered That Channel Returned to Svc W/O Completing Required Time Response Testing on transmitter.W/900314 Ltr ML20012C7271990-03-14014 March 1990 LER 90-002-00:on 900217,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.Caused by Failure to Complete Tech Spec Required post-maint Test. Post-maint Test Procedure revised.W/900314 Ltr ML20012C0631990-03-0808 March 1990 LER 90-005-01:on 900209,defect Found in Casing of Limitorque Model HBC-1 Gear Operators,Causing Valve Motion to Cease Prematurely in Open Direction.Caused by Excess Matl on Housings.Also Reported Per Part 21.W/900308 Ltr ML20012C0651990-03-0808 March 1990 LER 90-003-01:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Line Lacked Automatic,Remote Manual or Locked Shut Containment Isolation Valve.Request for Exemption Submitted to NRC.W/900308 Ltr ML20011F2761990-02-23023 February 1990 LER 90-004-00:on 900124:discovered That Control Rod Positions Not Recorded on Operator Logs on 890425 When Control Rod Insertion Limit Monitor & Deviation Alarm Out of Svc.Cause Not Stated.Personnel counseled.W/900223 Ltr ML20006F2041990-02-20020 February 1990 LER 90-002-00:on 900114,120-volt Ac Inverter for Vital Bus 3 Experienced Blown Dc Input Fuse When Inverter Bypassed & Aligned to 480-volt Ac Emergency Power.Caused by Mgt Action. Administrative Guidance issued.W/900220 Ltr ML20011E6341990-02-14014 February 1990 LER 90-005-00:on 900209,six Limitorque Corp Gear Operators, Model HBC-1,found to Contain Defect in Casting of Limit Stop Housing.Housings Machined to Remove Excess Matl.Item Reportable Per Part 21.W/900214 Ltr ML17223A7461990-02-0909 February 1990 LER 90-003-00:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Lines Lacked Automatic,Remote Manual or Locked Shut Isolation Valve. Exemption Request from GDC 57 initiated.W/900209 Ltr ML20011E2501990-02-0606 February 1990 LER 90-001-00:on 900107,high Radiation Alarm Received on Steam Generator Blowdown (SGBD) Sample Radiation Monitor, Causing SGBD Sys Isolation.Caused by Crud Particles Swept Into Monitor.Monitor Purged & Returned to svc.W/890206 Ltr ML20006B4031990-01-26026 January 1990 LER 89-018-01:on 891227,reactor Trip Occurred Following Initial Startup from Refueling Outage.Caused by Trip of 480 Volt Ac Feeder Breaker to Rod Drive Motor Generator Sets. Installed Spare Breaker tested.W/900126 Ltr ML20006A8711990-01-23023 January 1990 LER 89-019-00:on 891227,discovered That Manual Reactor Trip Operating Surveillance Test Not Performed within Required Frequency Prior to Previous Reactor start-up on 891224. Caused by Inadequate start-up procedures.W/900123 Ltr ML20006A8901990-01-23023 January 1990 LER 89-014-01:on 891101,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism.Caused by Weld Latching Mechanism Plate Interfering W/Locking Action of Door.Mechanism Modified & Latch removed.W/900123 Ltr ML20006A8721990-01-23023 January 1990 LER 89-009-01:on 890413,temporary Protection Covers Found on Five Temp Elements During Test of High Energy Line Break Temp Elements.Caused by Deficiency in Surveillance Program. Covers Immediately Removed from Temp elements.W/900123 Ltr ML20006A8691990-01-23023 January 1990 LER 89-017-01:on 891218,feedwater Isolation ESF Actuation, Caused by Swell Phenomena Experienced After Opening of C Msiv.Feedwater Isolation Signal Reset & Restored to Prefeedwater Isolation conditions.W/900118 Ltr ML19354E1551990-01-17017 January 1990 LER 89-017-00:on 891218,feedwater Isolation Occurred Due to Erroneous Level Transmitter Root Valve Position Indication. Operations Personnel Reset Feedwater Isolation Signal. W/900117 Ltr ML19354E1071990-01-16016 January 1990 LER 89-016-00:on 891215 & 16,erratic Level Transmitter Behavior Caused Steam Generator B hi-hi Level Feedwater Isolation.Caused by Inner Plugs Remaining Partially Inserted After Valves Opened.Plugs Freed from seats.W/900116 Ltr ML20005F8901990-01-12012 January 1990 LER 89-015-01:on 891213,operator Incorrectly Restored Solid State Protection Sys Generating Low Steamline Pressure Safety Injection Signal.Caused by Operator Error.Plant Restored to pre-safety Injection condition.W/900112 Ltr ML19332F5051989-12-12012 December 1989 LER 89-013-00:on 891112,4 Kv Bus 1A Power Supply Breaker Tripped on Phase overcurrent,de-energizing Emergency Bus 1A. Caused by Incorrect Tap Setting on Overcurrrent Relay.Relay Taps Reset & Breaker replaced.W/891211 Ltr ML20005D6631989-12-0606 December 1989 LER 89-027-00:on 891106,Train a Svc Water Pump Seal Water Supply Automatically Transferred to Backup Supply Due to Low Pressure.Caused by Seal Water Normal Supply Inadvertently Isolating While de-energizing.Manual revised.W/891206 Ltr ML19332E4931989-12-0101 December 1989 LER 89-014-00:on 891108,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism on North Door to East Valve Trench Area.Caused by Welded Latching Mechanism. Locking Mechanism modified.W/891201 Ltr ML19332D2321989-11-20020 November 1989 LER 89-026-00:on 891020,automatic Start of Auxiliary Feedwater Pumps Caused Steam Generator Blowdown Isolation. Caused by Inadequate Communications & Radiation Monitor Setpoint.Setpoint adjusted.W/891120 Ltr ML19325F1821989-11-0808 November 1989 LER 89-012-00:on 891010,in-core Instrumentation Guide Thimble Tubes Identified W/Degradation in Excess of 60% Wall Thickness.Caused by Mechanical Wear of Thimbles Against Reactor Vessel Internals.Tubes isolated.W/891108 Ltr ML19327B8701989-10-31031 October 1989 LER 89-014-01:on 890506,supply Breaker to 480 Volt Essential Bus J Opened & Alternate Bus J Supply Breaker Did Not Close. Caused by Spurious Trip Due to Broken Circuit.Reset Button Returned to Normal Position & Breaker closed.W/891031 Ltr ML19324C3741989-10-30030 October 1989 LER 88-002-01:on 880127,radiation Monitors for Control Room Deenergized,Resulting in Actuation of Control Room Emergency Bottled Air Pressurization Sys.Cause Not Determined.Pressure Transmitter to Be replaced.W/891030 Ltr ML19327B1851989-10-20020 October 1989 LER 89-011-00:on 890920,engineering Determined That Rupture Restraint Gaps Were Opened to Greater than Original Design Analysis.Caused by Alignment Performed During Hot Functional Testing.Design Change Mod to Be performed.W/891020 Ltr ML19325C6321989-10-10010 October 1989 LER 89-025-00:on 890910,high Temps on Steam Generators B & C Auxiliary Feedwater Lines Identified.Caused by Improper Seating of Auxiliary Feedwater Check Valves.Procedure Initiated to Verify & Correct condition.W/891010 Ltr ML19325C8851989-09-0909 September 1989 LER 89-010-00:on 890907,UL Test Results Indicated That Horizontally Mounted Prototype Fire Dampers Failed to Comply W/Requirements of Ul Std 555-1968.Caused by Discrepancies Between as-fabricated & Required specs.W/891009 Ltr ML18041A1891989-04-21021 April 1989 LER 89-005-00:on 890322,safety Injection Occurred Due to Low Pressurizer Pressure.Caused by Deficiencies in Safety Accumulator Check Valve Surveillance Test.Refueling Outage Calibr Procedures pre-reviewed by operators.W/890421 Ltr ML18041A1881989-03-14014 March 1989 LER 89-003-00:on 890212,noticed Erratic Operation of Main Feedwater Regulating Valve C & Turbine Trip/Reactor Trip Occurred Due to High Water Level in Steam Generator C.Caused by Valve Vibration & Hydraulic forces.W/890314 Ltr 1994-05-06
[Table view] Category:RO)
MONTHYEARML20029D6571994-05-0606 May 1994 LER 94-005-00:on 940407,chain Locking Mechanism on CP Suction Isolation Valve,Was Found Broken.Caused by Personnel Error.Corrective Action:New Chain Placed on Valve Handwheel & Chain Locking Mechanism intacted.W/940506 Ltr ML20029D8031994-05-0404 May 1994 LER 94-003-00:on 940404,two Flow Orifices Were Improperly Installed.Caused by Improper Installation of All Accessible Flow Orifices.Personnel Performed Procedure Ost 1.6.4 Correcting Improperly Installed orifices.W/940504 Ltr ML20046B5481993-07-30030 July 1993 LER 93-012-00:on 930702,discovered That Hydrogen Analyzer Inoperable During Quarterly Performance of Calibration Procedure.Test Personnel Contributed to Cause of Event.Test & Calibration Procedures Will Be revised.W/930730 Ltr ML20045J1201993-07-19019 July 1993 LER 93-011-00:on 930619,ESF Actuation Letdown Isolation Occurred While Synchronizing Main Unit Generator.Caused by Cooldown of RCS Due to Steam Demand.Plant Stabilized within Three Minutes & Pressurizer Level restored.W/930719 Ltr ML20045G4591993-07-0808 July 1993 LER 93-010-00:on 930614,determined That TS Surveillance on SI Accumulator Samples Missed Due to Draining & Refilling Accumulators Several Times During Outage.Accumulators a & C Immediately sampled.W/930708 Ltr ML20045F4711993-07-0202 July 1993 LER 93-009-00:on 930607,high Radiation Area Barrier Was Unlocked Due to Personnel Error.Comprehensive Confirmation Survey Performed,Personnel Interviewed & Task Force Formed. W/930702 Ltr ML20044F1541993-05-21021 May 1993 LER 93-007-00:on 930423,discoverd That Original Piping Did Not Conform to Design Code Requirement.Caused by Design Deficiency.Headers Fitted W/Code Approved End Caps & Tested & Now Conform to Design requirements.W/930521 Ltr ML20044F1521993-05-21021 May 1993 LER 93-008-00:on 930423,leakage Detected Through Two Check Valves in Chlorine Injection Line.Caused by Failure to Include Valves in ASME Section XI Testing Program.Check Valves Added to ASME Testing program.W/930521 Ltr ML20044D5251993-05-14014 May 1993 LER 93-006-00:on 930415,two Operators Entered Posted Area W/O Radiation Monitoring Device & Entered Locked High Radiation Area & Left Barrier Open.Caused by Personnel Error in Judgement.Operators counseled.W/930514 Ltr ML20024H1191991-05-15015 May 1991 LER 91-012-00:on 910415,excessive Max Operating Pressure Differential for Selected Solenoid Operated Valves Noted. Caused by Design Deficiencies.Equipment Mod Initiated to Replace Solenoid valve.W/910515 Ltr ML20029B2541991-03-0404 March 1991 LER 91-005-00:on 910131,steam Leakage in Auxiliary Feedwater Pumproom Caused ESF Actuation.Caused by Personnel Error. Control Room Operator Closed Steam Supply Isolation Valve to Stop Steam Leaking & Event Will Be reviewed.W/910304 Ltr ML17286B2651991-02-14014 February 1991 LER 90-006-01:on 900605,containment Isolation Valves Exceeded Stroke Time Limit,Per Tech Spec 3.6.3.1.Caused by Deficient Surveillance Program.Surveillance Procedures Revised to Include Stroke Time requirements.W/910214 Ltr ML20028H7391991-01-23023 January 1991 LER 90-007-01:on 900622,containment Entry Performed to Determine If Flanges Installed,Per Info Notice 90-019. Flanges Immediately Removed.Caused by Procedural Deficiency. Transfer Canal Draining Procedures revised.W/910123 Ltr ML20024F7441990-12-14014 December 1990 LER 90-021-00:on 901113,ESF Actuation & Feedwater Isolation Occurred During MSIV Stroke Testing.Caused by Operator Error.Feedwater Isolation Signal Reset & Isolation Valves reopened.W/901214 Ltr ML20024F7431990-12-14014 December 1990 LER 90-023-00:on 901114,ESF Actuation & Feedwater Isolation Occurred in Response to Opening Condenser Steam Dump Valve. Caused by Operation of Steam Dump Sys in Steam Pressure Control Mode.Signal reset.W/901214 Ltr ML17285B4731990-07-18018 July 1990 LER 90-007-00:on 900622,refueling Cavity Drain Flanges Found to Be Installed During Operation.Caused by Deficiency in Transfer Canal Draining Procedure.Procedure Revised to Verify Removal of Flanges After Canal drained.W/900717 Ltr ML20043G5771990-06-15015 June 1990 LER 89-017-02:on 891218,atmospheric Steam Relief Valve C Opened to Lower MSIV C.Caused by Swell Phenomena Experienced After Opening MSIV C.Feedwater Isolation Signal Reset. W/900615 Ltr ML20043B5171990-05-23023 May 1990 LER 90-004-00:on 900423,inadvertent ESF Actuation Occurred During Safeguards Protection Sys Testing.Caused by Personnel Closing Breaker Before Resetting Safety Injection Sys Signal.Signal reset.W/900523 Ltr ML20043B5201990-05-23023 May 1990 LER 90-005-00:on 900423,inadvertent ESF Actuation Occurred During Quench Spray Flow Switch Calibr.Caused by Error in Procedure Resulting in Installation of Two Leads on Same Terminal.Discharge Valves opened.W/900523 Ltr ML20043A4991990-05-16016 May 1990 LER 88-005-01:on 880219,startup Feedwater Pump Started, Causing Current Surge That Actuated Overcurrent Relay for Emergency Response Facility Transformer 3B.Caused by Faulty Transformer Relay.Relay replaced.W/900516 Ltr ML20012E6681990-03-29029 March 1990 LER 90-006-00:on 900227,plant Operation in Excess of Licensing Basis.Caused by Failure of Computer to Synchronize File Addresses in Task 3D.Heat Balance Calculations Reverified Using Data from Plant Variable Computer ML20012C4141990-03-14014 March 1990 LER 90-002-00:on 900117,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.On 900119, Discovered That Channel Returned to Svc W/O Completing Required Time Response Testing on transmitter.W/900314 Ltr ML20012C7271990-03-14014 March 1990 LER 90-002-00:on 900217,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.Caused by Failure to Complete Tech Spec Required post-maint Test. Post-maint Test Procedure revised.W/900314 Ltr ML20012C0631990-03-0808 March 1990 LER 90-005-01:on 900209,defect Found in Casing of Limitorque Model HBC-1 Gear Operators,Causing Valve Motion to Cease Prematurely in Open Direction.Caused by Excess Matl on Housings.Also Reported Per Part 21.W/900308 Ltr ML20012C0651990-03-0808 March 1990 LER 90-003-01:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Line Lacked Automatic,Remote Manual or Locked Shut Containment Isolation Valve.Request for Exemption Submitted to NRC.W/900308 Ltr ML20011F2761990-02-23023 February 1990 LER 90-004-00:on 900124:discovered That Control Rod Positions Not Recorded on Operator Logs on 890425 When Control Rod Insertion Limit Monitor & Deviation Alarm Out of Svc.Cause Not Stated.Personnel counseled.W/900223 Ltr ML20006F2041990-02-20020 February 1990 LER 90-002-00:on 900114,120-volt Ac Inverter for Vital Bus 3 Experienced Blown Dc Input Fuse When Inverter Bypassed & Aligned to 480-volt Ac Emergency Power.Caused by Mgt Action. Administrative Guidance issued.W/900220 Ltr ML20011E6341990-02-14014 February 1990 LER 90-005-00:on 900209,six Limitorque Corp Gear Operators, Model HBC-1,found to Contain Defect in Casting of Limit Stop Housing.Housings Machined to Remove Excess Matl.Item Reportable Per Part 21.W/900214 Ltr ML17223A7461990-02-0909 February 1990 LER 90-003-00:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Lines Lacked Automatic,Remote Manual or Locked Shut Isolation Valve. Exemption Request from GDC 57 initiated.W/900209 Ltr ML20011E2501990-02-0606 February 1990 LER 90-001-00:on 900107,high Radiation Alarm Received on Steam Generator Blowdown (SGBD) Sample Radiation Monitor, Causing SGBD Sys Isolation.Caused by Crud Particles Swept Into Monitor.Monitor Purged & Returned to svc.W/890206 Ltr ML20006B4031990-01-26026 January 1990 LER 89-018-01:on 891227,reactor Trip Occurred Following Initial Startup from Refueling Outage.Caused by Trip of 480 Volt Ac Feeder Breaker to Rod Drive Motor Generator Sets. Installed Spare Breaker tested.W/900126 Ltr ML20006A8711990-01-23023 January 1990 LER 89-019-00:on 891227,discovered That Manual Reactor Trip Operating Surveillance Test Not Performed within Required Frequency Prior to Previous Reactor start-up on 891224. Caused by Inadequate start-up procedures.W/900123 Ltr ML20006A8901990-01-23023 January 1990 LER 89-014-01:on 891101,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism.Caused by Weld Latching Mechanism Plate Interfering W/Locking Action of Door.Mechanism Modified & Latch removed.W/900123 Ltr ML20006A8721990-01-23023 January 1990 LER 89-009-01:on 890413,temporary Protection Covers Found on Five Temp Elements During Test of High Energy Line Break Temp Elements.Caused by Deficiency in Surveillance Program. Covers Immediately Removed from Temp elements.W/900123 Ltr ML20006A8691990-01-23023 January 1990 LER 89-017-01:on 891218,feedwater Isolation ESF Actuation, Caused by Swell Phenomena Experienced After Opening of C Msiv.Feedwater Isolation Signal Reset & Restored to Prefeedwater Isolation conditions.W/900118 Ltr ML19354E1551990-01-17017 January 1990 LER 89-017-00:on 891218,feedwater Isolation Occurred Due to Erroneous Level Transmitter Root Valve Position Indication. Operations Personnel Reset Feedwater Isolation Signal. W/900117 Ltr ML19354E1071990-01-16016 January 1990 LER 89-016-00:on 891215 & 16,erratic Level Transmitter Behavior Caused Steam Generator B hi-hi Level Feedwater Isolation.Caused by Inner Plugs Remaining Partially Inserted After Valves Opened.Plugs Freed from seats.W/900116 Ltr ML20005F8901990-01-12012 January 1990 LER 89-015-01:on 891213,operator Incorrectly Restored Solid State Protection Sys Generating Low Steamline Pressure Safety Injection Signal.Caused by Operator Error.Plant Restored to pre-safety Injection condition.W/900112 Ltr ML19332F5051989-12-12012 December 1989 LER 89-013-00:on 891112,4 Kv Bus 1A Power Supply Breaker Tripped on Phase overcurrent,de-energizing Emergency Bus 1A. Caused by Incorrect Tap Setting on Overcurrrent Relay.Relay Taps Reset & Breaker replaced.W/891211 Ltr ML20005D6631989-12-0606 December 1989 LER 89-027-00:on 891106,Train a Svc Water Pump Seal Water Supply Automatically Transferred to Backup Supply Due to Low Pressure.Caused by Seal Water Normal Supply Inadvertently Isolating While de-energizing.Manual revised.W/891206 Ltr ML19332E4931989-12-0101 December 1989 LER 89-014-00:on 891108,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism on North Door to East Valve Trench Area.Caused by Welded Latching Mechanism. Locking Mechanism modified.W/891201 Ltr ML19332D2321989-11-20020 November 1989 LER 89-026-00:on 891020,automatic Start of Auxiliary Feedwater Pumps Caused Steam Generator Blowdown Isolation. Caused by Inadequate Communications & Radiation Monitor Setpoint.Setpoint adjusted.W/891120 Ltr ML19325F1821989-11-0808 November 1989 LER 89-012-00:on 891010,in-core Instrumentation Guide Thimble Tubes Identified W/Degradation in Excess of 60% Wall Thickness.Caused by Mechanical Wear of Thimbles Against Reactor Vessel Internals.Tubes isolated.W/891108 Ltr ML19327B8701989-10-31031 October 1989 LER 89-014-01:on 890506,supply Breaker to 480 Volt Essential Bus J Opened & Alternate Bus J Supply Breaker Did Not Close. Caused by Spurious Trip Due to Broken Circuit.Reset Button Returned to Normal Position & Breaker closed.W/891031 Ltr ML19324C3741989-10-30030 October 1989 LER 88-002-01:on 880127,radiation Monitors for Control Room Deenergized,Resulting in Actuation of Control Room Emergency Bottled Air Pressurization Sys.Cause Not Determined.Pressure Transmitter to Be replaced.W/891030 Ltr ML19327B1851989-10-20020 October 1989 LER 89-011-00:on 890920,engineering Determined That Rupture Restraint Gaps Were Opened to Greater than Original Design Analysis.Caused by Alignment Performed During Hot Functional Testing.Design Change Mod to Be performed.W/891020 Ltr ML19325C6321989-10-10010 October 1989 LER 89-025-00:on 890910,high Temps on Steam Generators B & C Auxiliary Feedwater Lines Identified.Caused by Improper Seating of Auxiliary Feedwater Check Valves.Procedure Initiated to Verify & Correct condition.W/891010 Ltr ML19325C8851989-09-0909 September 1989 LER 89-010-00:on 890907,UL Test Results Indicated That Horizontally Mounted Prototype Fire Dampers Failed to Comply W/Requirements of Ul Std 555-1968.Caused by Discrepancies Between as-fabricated & Required specs.W/891009 Ltr ML18041A1891989-04-21021 April 1989 LER 89-005-00:on 890322,safety Injection Occurred Due to Low Pressurizer Pressure.Caused by Deficiencies in Safety Accumulator Check Valve Surveillance Test.Refueling Outage Calibr Procedures pre-reviewed by operators.W/890421 Ltr ML18041A1881989-03-14014 March 1989 LER 89-003-00:on 890212,noticed Erratic Operation of Main Feedwater Regulating Valve C & Turbine Trip/Reactor Trip Occurred Due to High Water Level in Steam Generator C.Caused by Valve Vibration & Hydraulic forces.W/890314 Ltr 1994-05-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
[Table view] |
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March 4, 1991 ND3MNO:3110-Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License _No. DPR-66 LER 91-005-00 United-States: Nuclear Regulatory Commission-Document control' Desk Washingtoni._DC_ 20565
- Gentlemen 1 In - accordance with Appendix A, Beaver Valley Technical Specifications, the following Licensee -Event Report 'is
-submitted:
LER 91-005, 10 CFR 50.73.a.2.1v, "ESF Actuation-Steam Generator Blowdown Isolation".-
Very truly yours,
[. [. @ 6
-T. P. Noonan General Manager Nuclear-_ Operations JGT/sl
- Attachment kfogggCk -
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_=--
March 4,.1991' '
. ND7MNot3110. u
.jLPage two- j 1
acc: Mr.-T. T.-Martin,nRegional Administrator :l t United ~ States-Nuclear Regulatory Commission-
-Region-1 m 475LAllendale Road- 1 King of Prussia, PA::19406 C. A. Rcteck,10hio Edison 76.S.-. Main Street
' Akron,10H 44308-Mr. A. .DeAgazio,: BVPS Licensing Project Manager United States Nuclear Regulatory Commission
> ._ W ashington,;DC 20555 -j i
J. Beall,1 Nuclear Regulatory Commission, !
BVPS Senior-Resident-Inspector LarrylBeck _.
Cleveland Electric 6200 Oak Tr( e Blvd.
Independence,. Ohio. 44101 L INPO Records Center. -1 Suite:1500 i 1100 Circle 75 Parkway. 1
-: Atlanta, GA 30339-G.-E.-Muckle, Factory 1 Mutual Engineering 1680 Anderson Drive #BLD10-Pittsburgh,1PA 15220-2773 '
Mr./ Richard Janati ,
Department of. Environmental Resources
'P.=0. Box 2063' 16th Floor, Fulton Building =
g -- Harrisburg ,1 PA 17120 4 l Director,--Safety Eval'uation & Control-
,VirginiaEElectric &. Power Co._ <
iP.O.-Box 26666 =
One' James; River Plaza Richmond,'VA- '23261- t W 'Hartley_
. Management Analysis Company
, ;112671 High' Bluff' Drive '
San Diego, CA 92130-2025'
-: J . ' M . Riddle
_NUS Operating-Service-Corporation Park' West.II:
Cliff Mine' Road-Pittsburgh, PA 15275
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I h C PW 3#6 U.S NUCttAR f;t0VLATORY COMMtsslON APPROvtD OM9 NO 3120604
, E kP tR E $ dI30/92 ttflMAf(O $tiRDth PER RISPON%E TO COMPLY WTH THI$
. / LICENSEE EVENT REPORT (LER) $I.L"T^r'iUEAR'st?.'U"o"#E#luAYt TEU NicN"oS I OEft Ai5'v'EEE'IFO!"' . IL'$'o"UlE E'EEOS a%'o""i "'!E'!"r'OEJRGe"'
P ACitlTY hAMt Hi Doca ti huMetR (21 FAGE G Beavor Valley Power Station Unit 1 o 15 l 0 I o l o 131 3 l 4 1 lor l 0 l 4 vita iA, ESF Actuation - Steam Generator Blowdown isolation !
(VENT DAf t (61 tta huhestR tai ALPORT DAf t I?> Of MER 7 ACitif tts INvolvlO its MONT H DAY YtAR YEAR II0 4
- MONTH DAY # ACittiv N AMet LOCKi t hvW5t hest g 'n q, VSAR N/A oisgogogo; ; g 0l1 3l1 9' 1 9J1~~ 0l 0l 5 0l 0 0l 3 0l4 9l1 o isto to ioi 1 i OPE # ATING THis REPORT is susMITTtD PURSUANT TO THE PLQUIREMINTS OF 10 C9R k (Cneck one er e=ses of fa#de*=o,1 (111 MOO 4 m 3 20 402thi 20 400lel Xi son H H,o I 1>m powt4 20 406teHilui 90 StieHit 60 786 ell 2Het 73 71let
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20 406taH1 Hvl 60 73 aH21 teen le 73teH2Hal LICEN5it CONT ACT FOR ims Lin ital NAMI itttPHONE huYetR l Amt A C004 T.P. Noonan, General Manager Nuclear Ooorations 4l1l2 614i31- i,1 l 2i51 8 COMPLEf t ONE teht FOR 4 ACH COMPONENT F AltuRt DttCRisto tN THit PEPORT H3i CAUS$ COM*0NENT- C. RiPonT CoupoNt N T M katoRfAsti
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SUPettMENT AL REPORT EXPECf tD H4 wCNTH DAY lVtA9 Sv8W$$ TON
~~~} vis 1:< m a.w. asecreo svenssion os re "i] No l l l uetRACT m ,ue m .. .,. .~, , u .,.,,. <, -,- . e n e i On 1/31/91 at 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, blowdown from all steam generators isolated when blowdown containment isolation valves TV-BD-100A,B,'C and blowdown sampling- containment isolation valves. TV-SS-117A,B,C- closed. Steam, leaking past the seat of the normally closed steam supply trip valve, TV-MS-105A, to the steam-driven auxiliary feedwater pump caused the pump to develop a discharge pressure sufficient to cause automatic blowdown isolation. Steam supply to the pump was isolated by closing the upstream steam supply isolation valve (MOV-MS-105). The, diaphragm of- TV-MS-105A was rerlaced by Instrument & Control (I&C) technicians. The cause 4 this event was personnel error. The air supply to TV-MS-105A was set at 30 psi versus the required 50 psi. TV-MS-105A had insufficient air pressure to completely close'against full secondary steam-pressure. I&C personnel increased the air pressure to maintain the valve closed. This event will be reviewed by all I&C supervisors and technicians. There were no safety implications to the public as a result of this event. TV-BD-100A,B,C and TV-SS-117A,B,C are containment isolation valves which actuated to their required safety related positions.
NZ Form 364 (649)
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LICENSEE EVENT REPORT (LER) 'Jls'o'.'M/MM%"'40U .#'IM ,*J,*.'."'s TEXT CONTINUATION !?""#,'o'."4 ^."faiMf'.M!lcO,'!2u'? "U "f!
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7 C4LITV 4Aut til . DOCK t Y .sVMht m 1,1 ggg gygggy ggi pAgg g33 T" g[a eYa Beaver Valley Power Station Unit 1 o p } o Io l0 l3 l0 '4 9l1 1 g0l0l5 -
0]O 0l2 OF 0 14 TEXT W sies emere e recured, saa smooner Mtc Fame 3sEnt (171 DESCRIPTION OF EVENT
'On 1/30/91, Unit 1 was in Hot Standby (Operational Mode 3),
preparing _ for station startup. At 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, the primary auxiliary building- operator reported a steam leak in the auxiliary feedwater pump room. Steam was observed leaking from
.the actuator of TV-MS-105A, one of two normally closed trip valves which supply steam to the steam-driven auxiliary feedwater pump (FW-P-2). Steam was also leaking past the seat of TV-MS-105A causing FW-P-2 to rotate slowly. Steam supply to
-_FW-P-2 was isolated when a control room operator closed the steam supply isolation valve (MOV-MS-105). Steam isolation requires into Technical Specification 3.7.1.2, which requires FW-P-2 entry ~ to be returned to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Maintenance was requested to replace the diaphragm of TV-MS-105A._ Diaphragm replacement was completed on 1/31/91.
=The I&C s'upervisor noted that only 9 psi was required to stroke the valve' _ closed yet the air regulator was set at 65 psi. The I&C supervisor felt that this was excessive and may have contributed to the failure of this diaphragm since it had been replaced just one week earlier. The I&C supervisor instructed the_ technicians .to set the air. pressure at 30 psi. The valve stroked . full open and full closed properly. Operations prepared to perform the post-maintenance valve stroke-test.
As MOV-MS-105 was opened, the local operator obscrved'the FW-P-2 turbine rolling. . At - 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, blowdown from all steam
_ generators isolated when blowdown isclation' valves TV-BD-100A,B,C and blowdown sampling isointion valves TV-SS-117A,B,C closed. This automatic- actuation to maintain steam- generator inventory occurs by design whenever the discharge -pressure of any of the three auxiliary feedwater pumps
-reaches 500 ;psig . When the operating crew realized that TV-MS-105A was leaking by, even though it displayed a closed-indication, _ MOV-MS-105 was closed . to stop the leak.
Subsequently, I&C technicians increased the air pressure to 55
-psi and TV-MS-105A remained completely closed against steam pressure when MOV-MS-105 was opened. A satisfactory valve stroko ' test was .then performed on TV-MS-105A as part of post-maintenance testing.
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_ LICENSEE EVENT REPORT (l.ER) "'!
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u '" 0Mf2 Oi,'i 07 MANAGE MINT AND SVDQti,W ASHINQlON,DC 3060) f ActL41Y HAM 4 Hi DOCK t1 NUMet R 42' t 4 R NUMt f R (4) PACS (3' "aa "RT.I ;*#in
- Boavor Valloy Power Station Unit 1
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O lo 0l 3 0F 0 14 rm y .. w wet uw nn CAUSE OF EVENT The- cause of the event was personnel error. While processing the- Maintenance Work Request (MWR) written to replace the diaphragm of TV-MS-105A, I&C supervisors did not find this particular valve in the specifications table of the Corrective
-Maintenance Procedure used for a large number of air-operated
-valves. . The--I&C supervisor reviewing the MWR instructe- (on the
-MWR) the technicians- - to set the regulator air pressure to the value found prior to-maintenance.
The I&C work party supervisor suspected that too high of an air set pressure 'on TV-MS-105A may have been responsible for premature- failure of the diaphragm that- had recently been replaced. He instructed the technicians to set the air pressure i.
at 30 ' psi. He did not _ refer to- the correct table in the Corrective _ Maintenance Procedure (CMP) which listed the air set
. pressure.for this valve at 50 psi.
i' When- MOV-MS-105 was opened, TV-MS-105A had insufficient air pressure to remain completely closed against full secondary steam- pressure. Steam leaked past-the seat of TV-MS-105A to the turbine of the steam-driven auxiliary feedwater pump causing it to . develop a discharge-pressure sufficient to trigger automatic closing of! blowdown isolation valves TV-BD-100A,B,C and blowdown
-sample line containment isolation valves TV-SS-117A,B,C.
CORRECTIVE ACTIONS The -following corrective actions have been or'will be taken as a result of this event:
- 1. The control room operator closed steam' supply isolation valve MOV-MS-105 to stop steam leaking past TV-MS-105A.
- 2. I&C personnel -increased the air regulator pressure setting of TV-MS-105A (to approximately 55 psi) to maintain the
' valve closed against steam pressure.
3.- This event will. be reviewed by all I&C supervisors and technicians,
- 4. Instrument and Control supervision is performing an
- . evaluation to determine the cause for the personnel error and any additional corrective actions. ,
NIC Form 384A (6A9)
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-. . LICEh'3EE EVENT REPORT (LER) ',Ns* *JL*,uMfd',"o"'!;gn/%cf7,f.' ,*o',"J"4
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- Beaver VAlloy Power Station Unit 1 o p l0 l0 Io l 313 l4 9l1 -
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0 l0 0l40F0 1 sm ra w, a,,e e s, < n, es.ww nac eme nn REPORTABILITY
_This event was reported to the Nuclear Regulatory Commission at 0438 hours0.00507 days <br />0.122 hours <br />7.242063e-4 weeks <br />1.66659e-4 months <br /> in accordance with-10 CFR 50.72.b.2.ii. This written report is being submitted in accordance with 10CFR50.73.a.2.iv, as an' event. involving an Engineered Safety Features Actuation.
u- ,
, PREVIOUS OCCURRENCES.
Two-previous similar events were identified:
-LER 88-014-00 Steam- driven auxiliary feedwater pump-actuation due to diaphragm failure.
LER 90-014 A failed pressure switch caused . the automatic- start of the steam drivon' auxiliary feedwater pump and steam generator :
blowdown isolation.
JAFETY IMPLICATIONS There were no safety implications to the-public as a result.of this-- event. Blowdown ~ isolation valves TV-ED-100A,B,C and sampling isolation .;-valves TV-SS-117A,B,C are containment-isolation. valves which actuated to their_ required safety related
_(closed); _ positions. Blowdown. from-all_.three steam generators had. been _ isolated prior to -this = event by trip valves:at the blowdown flash'tankLinlet.
' NIC Poem 3eSA 4 49) .
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