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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
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'Af Telephone (412) 393-6000 O on 4 Shrppingport. PA 18077-0004 2
July 2,1993 ND3MNO:3467 Beaver Valley Power Station, Unit No.1 Docket No. 50-334, Licensee No. DPR-66 LER 93-009-00 United States Nuclear Regulatory Commission Document Control Desk-Washington, DC 20555 Gentlemen:
In accordance with Appendix A, Beaver Valley Technical Specifications, the following Licensee Event Report is submitted:
LER 93-009-00,10 CFR 50.73.a.2.i.B, " Unlocked High Radiation Area Barrier."
h4 T. R. Freeland General Manager Nuclear Operations JGT/sl Attachment.
9307070325 930702 Qq- /
, PDR. ADOCK 05000334 yy r/ l-S PDR "a _-l y
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h July 2,1993 ND3MNO:3467 Page 2 1
cc: Mr. T. T. Martin, Regional Administrator j United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. G. E. Edison, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 Larry Rossbach, Nuclear Regulatory Commission, BVPS Senior Resident inspector ,
J. A. Holtz, Ohio Edison
6 S. Main Street Akron, OH 44308 Larry Beck :
Centerior Energy 6200 Oak Tree Blvd. ,
independence, OH 44101-4661 k
INPO Records Center 700 Galleria Parkway :
Atlanta, GA 30339-5957 Mr. Robert Barkanic j Department of Environmental Resources !
P.O. Box 2063 I I
16th Floor, Fulton Building Harrisburg. PA 17120 ;
Director, Safety Evaluation & Control .;
Virginia Electric & Power Co. 'l P.O. Box 26666 >
One James River Plaza ,
Richmond, VA 23261 ;
I i
W. Hartley Virginia Power Company _l <
5000 Dominion Blvd.
2SW Glenn Allen, VA 23060 l t
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s
July 2,1993 .
ND3MNO:3467 !
Page 3
'I J. M. Riddle Halliburton NUS i Foster Plaza 7 l 661 Anderson Drive f Pittsburgh, PA 15220 l i
Bill Wegner, Consultant }
23 Woodlawn Terrace ,
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- 5 rm EXPIRES S/31/95 EST! MATED BURDEN PER RESPONSE TO COMPLY W'T M TH;5 tNFORMATION COLLE CTION REQUEST: 50.0 HRS FORAARD LICENSEE EVENT REPORT (LER) CevetNTs ntaRDmo suRDtN isTuATt TO T E NrOnuATiON AND RE. CORD 5 MANAGEVENT BRANCH fuNFsB 7714l U $. NUCLE AR Af GutATOFW COf.MSSON. W ASMNGTON, DC M58 5 0D?t. AND TO THE FAF'ERWORK RE DUC'lON PROJtCT 0750 01D4. OFFICE Or MANAGEMENT AND BUDGET, WASHNTON, DO M503 (See reverse for requued number of digrts/ characters for each block) pAcOTYNAME W DOCKET NUMBE R (2) PAGE p)
Beaver Valley Power Station Unit 1 05000 334 OF 04 ,
TITLE 14)
Unlocked High Radiation Area Barrier.
EVENT DATE (5) LER NUMBER (6 i REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8)
SEOJENTiAL FEVtSION
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N/A 05000 N/A F ACluiY NAMt DOCF.ET NUMBER 06 0 T 93 93 -
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OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 4: (Check one or more) (11)
MODE (9) 5 20 402(b) 20 405(c) 50 73(a)(2)(iv) 73 7i(d)
POWER 20 405(aH1)o) 50.36(c)(1) 50.73(aM2)(v) 73 71(c)
LEVEL (10) 0 20 405(a)(1 H") 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20 405(a)(1)(iri; );50.73(a)(2)(i) 50.73(aH2)(vm)(A) 20 405(a)(1)(w) 50.73(a)(2}(ii) 50.73(a)(2)(vur)(B) c o ,.,s 3%m 20 405(a)(1)(v) 50 73(aH2)(iii) 50.73(aH2)(x)
LICENSEE CONTACT FOR THIS LER (12) I put Tu LP"oNE N;veta meuoe Area cocei L R. Freeland, General Manager Nuclear Operations 41 2 643-1258:
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) past sys*r M COMO.E NT MANJf ACTURf A CAU E SYST M COMPONENT MANUF ACTURE R O S A NE XXXX XXXX N SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED "N" D^* R ^"
I yu SUBMISSION p m. mnm nPrc'tD mevss ON dam }l" DATE (15)
ABSTRACT (Limrt to 1400 spaces. i e.. approximately 15 single 4 paced typewritten lines) (16)
On 6/7/93, with Unit One in Mode 5 for the ninth refueling outage, Health Physics was performing a routine radiation barrier check, which verifies the integrity of the barrier and that the barrier is in place and posted. At 1740 hrs, the east ladder barrier to the Solid Waste area was found open. This area is a High Radiation Area and is required to be barricaded and conspicuously posted in accordance with Technical Specification 6.12. The area was searched i and no individuals were present. This barrier was previously verified locked closed during the daylight shift at 0936 hrs. A survey of the area indicated that there were no areas where the radiation levels were greater than 1000 millirem per hour, however an area that had radiation levels greater than 100 millirem per hour was present. With the barrier open, the area was still conspicuously ,
posted as a High Radiation Area, however, it was not adequately barricaded. The barrier was not closed when personnel exited the area. All personnel that had High Radiation Area keys during this ,
time period were interviewed. The results were inconclusive and it could not be ascertained who left the barrier open. No adverse radiological consequences resulted due to the barrier being inadvertently left open. A review of exposure records indicated that no station personnel received any abnormal dose during the time the barrier was open, we rOno m m
4 REQUIRED NUMBER OF DIGITS / CHARACTERS FOR EACH BLOCK j l
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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 m EXPIRES 5/31/95 ESTIMATED BVROEN PER RESPONSE TO Cop %Y W'TH TH:S
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TEXT CONTINUATION Ac Rtc 4 s uANAGEvEc s%N:s mes nuw s Nu:sR RE3ULATORY COWSSON. WAS"iN3?ON, DC 20555M1. AND TO THE PAPERWDRd REDUCTON PROJEC' (3153.cto45 DU CE OF MANAGEMEN'T AND BJDGET, WAS"tN3?ON. DC 20503, FACIUTV NAME (1) DOCRET NUMBER (2) LER NUMBER (5) PAGE(3) gg bEQJE C.A. REwSON NJMBER NUUBER 05000 oF Beaver Valley Power Station Unit 1 334 93 - 009- 00 02 04 TLxT (n more spece a rewec sne scamone cc+es of WC Form 3ts4; (17) i Description of Event On 6/7/93 at 1740 hrs, a Radiation Technician was performing a routine radiation barrier surveillance. The surveillance verifies the integrity of the barrier and that the barrier is in place and conspicuously posted. The Radiation Technician found the east wall -
ladder barrier to the Solid Waste area open. A portion of the Solid Waste area accessible from this ladder is a High Radiation Area (greater than 100 millirem per hour but less than 1000 millirem per hour) and is required to be barricaded and conspicuously posted as a High Radiation Area in accordance with Technical Specification 6.12. This barrier was previously verified locked closed during the previous barrier check at 0936 hrs.
A confirmation survey of the area indicated that there were no accessible areas where the radiation levels were greater than 1000 millirem per hour however an area at the bottom of another Solid Waste ladder prov1 ding access to the 722' elevation had radiation levels where an individual could have received greater than 100 millirem per hour to a major portion of their whole body. !
l With the barrier open, the area was still conspicuously posted as a High Radiation Area, however the area was not barricaded adequately i as required by Technical Specification 6.12. l t
,Cause of the Event The barricade was not verified closed when an individual or work crew exited the area. All personnel that had High Radiation Area ;
keys signed out during the time period between barrier checks were interviewed. The results were inconclusive and it could not be ascertained who left the barrier open.
Corrective Actions ;
1). At the time of discovery, the area was searched and no individuals were present in the area.
2). A comprehensive confirmation survey of the area was performed.
It was verified that the radiation levels in the portion of the :
Solid Waste area accessible from this barrier being left open were less than 1000 millirem per hour. However, an area was accessible where an individual could have received greater than '
l i
100 millirem per hour to a major portion of the whole body.
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NRC FOW 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 5 52 EXPIRES 5/31/95 ESTIMATD BJRDEN PER RESPONSE TO COUNY W"H TNS LICENSEE EVENT REPORT (LER) Ev"?SSSEGT$$'RNEMJ"oClMCM
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TEXT CONTINUATION REGULATOAV CCA*V$ SON WAS*0NGTON. DC 20S$5 D"C1. AND TO TME FAPERWORA REDuCTCN PRCUECT ptSX104;, OFFICE Cr VANAGEMEC AND BJDGE7. W A5'+N370%. DC 20533 f ACILITV NAME (1) DOCME1 NUMBER (2) l Lf R NUMBER (6) FAGE (3) gg LEQUENhAL kloh 0N NUMBER NUMBEM 05000 oF Beaver Valley Power Station Unit 1 334 93 - 009- 00 03 04 tea w , ,ar. ua. ,, ,.u a . .nw n w um ,,, m o n 3). All personnel that had High Radiation Area keys signed out during the time period between barrier checks were interviewed.
The results were inconclusive and it could not be ascertained who left the barrier open.
4). A review of exposure records indicated that no station personnel received any abnormal dose during the time period that the barricade was open.
5). A multi-disciplined, human performance oriented task force has been formed to assess the root causes of events involving high radiation barrier controls. The task force is led by the Manager, Health Physics Department and includes members from Operations, Health Physics, Maintenance, and Training. The task force will determine additional corrective actions needed to physical barriers, postings, station procedures, or training to maintain station standards for controlling access to high radiation areas.
Previous Similar Events A review of station documents revealed three previous similar events:
1). Unit 1 LER 93-006 documented an event where two operators entered a locked high radiation area to perform valving, and left the barrier door open. Due to the physical layout of the work area, they were unable to maintain adequate control over the access point.
2). Unit 1 LER 92-006 documented an event in which the East Valve Trench Area barrier door was discovered to be open during a routine radiation barrier check. This event was caused by a failure to properly verify that the door was locked upon exit from the area.
3). Unit 1 LER 89-014 documented an event in which the East Valve Trench Area barrier door was found open due to a faulty locking mechanism. 1 Reportability i This event resulted in a condition prohibited by Technical Specification 6.12. As a result, this Licensee Event Report is being submitted in accordance with 10 CFR 50.73.a.2.1.B.
NRcroRv3 cAvser
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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 5R EXP!RES 5/31/95 ESTW/A4D BJOEN PER RESPONSE TO Cou%v w'TH Tks INCORVATON COU EC'CN REQJEST. SO D HRS. FORAAC '
LICENSEE EVENT REPORT (LER) eOy,ecs REGiRotsa aseEN tSwATE TO T E yO=uATm ,
TEXT CONTINUATION AC MO CS MANAGEMENT B%ON EBB WW$ NJWA ,
REGJ ATOAV COUV SSON. AAS%GTON. DC 205t543D1. AND TO '
THE PAPCR*0R< REDUCCN PRO. JECT F53 010dj. OFFCE OF r MAW 4WE NT ANO BUDGE 7, WAS%3 TON. DC 79503 7 ACtLITY NAME 0) l DOCmET NUMBER (2) LIR NUMBER 45) PAGE (si YEAR
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NUMBER ' NUMBER 05000 or Beaver Va!!ey Power Station Unit 1 334 93 009- 00 04 04 i
rw gu n. av.v. ,,,.e,1 a. .~m ev., a uuC un us on Safety Implications This event is recognized as a violation of Technical Specifications and station radiological practices. No adverse radiological- !
consequences resulted due to the barrier being inadvertently left open. A review of exposure records indicated that no station personnel received any abnormal dose during the time period that the l barricade was open.
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