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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029E3351994-05-10010 May 1994 LER 94-006-00:on 940415,both Trains of CREVS Declared Inoperable.Caused by Tornado Warning & Sighting of Tornado Moving Toward Plant.Tornado Warnings downgraded.W/940510 Ltr ML20029E2021994-05-0909 May 1994 LER 94-004-00:on 940408,determined That TS Pressurizer Cooldown Limit Exceeded on 930618 & Not Restored within Required Timeframe.Caused by Unanticipated Sys Interaction. SI for Check Valve Opening Tests revised.W/940509 Ltr ML20029D8151994-05-0303 May 1994 LER 94-005-00:on 940403,inadvertent Fwis Occurred.Caused by Personnel Failure to Follow Work Document Instructions. Corrective Action:Individuals Were Counseled on Requirements to Follow Work Document Instruction steps.W/940503 Ltr ML20046B8351993-07-30030 July 1993 LER 93-017-00:on 930621,discovered 24-hour Telephone Notification Had Not Been Carried Out as Required by TS LCO 3.7.11.1 Action Statement (b)(2)(a) Due to Personnel Error. NRC Informed of Missed notification.W/930730 Ltr ML20046B8501993-07-30030 July 1993 LER 93-018-00:on 930704,DG Started Due to Improper WO Planning.Restored Power to 1BB Shutdown Board & Stopped Running DGs.W/930730 Ltr ML20046A4691993-07-19019 July 1993 LER 93-016-00:on 930619,Phase A,Auxiliary Bldg & Containment Isolations Manually Initiated as Result of Fuel Assembly Failing to Remain in Upright Position After Being Released. All Fuel Movement stopped.W/930719 Ltr ML20045J0111993-07-14014 July 1993 LER 93-015-00:on 930614,1A Start Bus Alternate Feeder Breaker Tripped Upon Start of Unit 1 RCP Which Resulted in Start of DG Due to Current Transformer Wired Incorrectly. Restored Offsite Power & Secured Final DG.W/930714 Ltr ML20045H0171993-07-12012 July 1993 LER 93-014-00:on 930611,determined That Inadequate Ventilation Design Resulted in Potential Inoperability of Vital Power Equipment.Design Being modified.W/930712 Ltr ML20045B9951993-06-15015 June 1993 LER 93-004-01:on 930222,determined That Blind Flange on Elevation 734 Personnel Airlock Outer Housing Leaking.Due to Improper Installation of Blind Flange.Evaluation Performed of Other 14 Double O-ring Blind flanges.W/930615 Ltr ML20045B9311993-06-10010 June 1993 LER 93-013-00:on 930514,fire Watch Was Not Performed within Time Frame Required by Tech Specs Due to Inadequate Supervision by Fire Protection Foreman.Fire Watch Patrol reestablished.W/930610 Ltr ML20045A7261993-06-0707 June 1993 LER 93-011-00:on 930507,discovered That Fire Barrier Breached W/O Proper Compensatory Measures Established.On 930505,door Leading to Room Housing Containment Spray HX 1A Breached.Roving Fire Watch Established & LCO 3.7.12 Entered ML20044H4501993-06-0303 June 1993 LER 93-012-00:on 930504,apparent Failure to Properly Identify & Plug SG Tube Determined to Exceed TS Plugging Limit.Caused by eddy-current Coordinator Not Ensuring Task requirements.Eddy-current Procedure revised.W/930603 Ltr ML20044H1561993-05-28028 May 1993 LER 93-010-00:on 930430,Westinghouse Identified Error in Development of Calculations for Cold Overpressure Mitigation Sys Setpoints.Caused by Vendor Failure to Consider Elevation Difference.Engineering Evaluation Performed ML20044E6341993-05-17017 May 1993 LER 93-009-00:on 930417,TS Surveillance Not Performed for Three Pipe Support Snubbers Because of Omission of Snubbers from Surveillance Instruction for Visual Insp.Snubbers Visually Inspected & Functionally tested.W/930517 Ltr ML20044B6751993-02-23023 February 1993 LER 93-001-00:on 930124,Unit 1 Ice Bed Temperature Recorder in MCR Declared Inoperable.Caused by Ineffective Communication.Appropriate Personnel Involved W/Event Have Been counseled.W/930223 Ltr ML20044B6141993-01-21021 January 1993 LER 92-026-00:on 921222,determined That Several ASME Section XI Pressure Tests Not Performed Due to Section XI Program Implementation Not Being well-defined,controlled or Documented.Test Expeditiously performed.W/930121 Ltr ML20024H2441991-05-22022 May 1991 LER 91-007-00:on 910422,LCO 3.0.3 Entered When Shaft of Train a Main Control Room Air Handling Unit Failed from Fatigue & Train B Out of Svc for Maint.Caused by Shaft Misalignment.New Shaft installed.W/910522 Ltr ML20029C1761991-03-21021 March 1991 LER 91-002-00:on 910211,unit Operated in Condition Prohibited by Tech Spec 3.3.3.8 Limiting Condition for Operation.Cause Under Investigation.Night Order Issued to Personnel Re Removal of Equipment from svc.W/910321 Ltr ML20029C1231991-03-18018 March 1991 LER 90-016-01:on 901117,determined That Calibr of Nuclear Instrumentation Sys intermediate-range Channels Set Nonconservatively.Caused by Lack of Operability Control for Rod Motion.Action Plan developed.W/910318 Ltr ML20029A6711991-02-25025 February 1991 LER 91-002-00:on 910124,LCOs 3.0.5 & 3.8.1.1 Entered When Both Trains of Emergency Gas Treatment Sys Declared Inoperable.Caused by Blown Fuse & Excessive Cycling of Air Start Sys.Fuse replaced.W/910225 Ltr ML20028H0331990-09-27027 September 1990 LER 90-019-00:on 900828,failure to Update P-250 Plant Computer Constants Resulted in Axial Flux Difference.Caused by Inadequate Procedures & Inappropriate Personnel Actions. Procedure 0-PI-NXX-092-001.0 revised.W/900927 Ltr ML20028G9201990-09-26026 September 1990 LER 90-020-00:on 900829,ventilation Sys Inoperable Due to Train B Diesel Generator Out of Svc.Caused by Stuck Microswitch Contacts on Pressure Switch 0-PS-311-172. Pressure Switch Adjusted & Returned to svc.W/900926 Ltr ML20044A9361990-07-0909 July 1990 LER 90-011-00:on 900608,determined That Actual Nuclear Instrumentation Sys Power Range Detector Currents Were 20% to 31% Lower than Predicted.Caused by Calibr Values Being Incorrectly Calculated.Channels corrected.W/900709 Ltr ML20044A3241990-06-25025 June 1990 LER 90-010-00:on 900526,limiting Condition for Operation Entered Because MSIV Failed to Close When Another MSIV Inoperable for Maint.Cause Attributed to Valve Stem & Valve Guide Binding.Operations Training Ltr issued.W/900625 Ltr ML20043H5091990-06-21021 June 1990 LER 90-009-00:on 900527,automatic Start of Auxiliary Feedwater Pumps Occurred When Both Main Feedwater Pumps Placed in Tripped Condition.Caused by Personnel Error.Trip Circuitry Reset & Operators counseled.W/900621 Ltr ML20043E5401990-06-0707 June 1990 LER 90-008-00:on 900514,two Control Room Isolations Occurred as Result of Spurious Spikes.Caused by Loose Terminations on Relay Socket.Loose Connections Properly terminated.W/900607 Ltr ML20043A4211990-05-16016 May 1990 LER 90-010-00:on 900416,containment Ventilation Isolation Occurred.Caused by Allowing Gaseous Radiation Level to Increase Too Close to Alarm Setpoint.Recovery from Isolation initiated.W/900516 Ltr ML20043A2261990-05-14014 May 1990 LER 90-009-00:on 900404,lower Containment Radiation Monitor Found Inoperable & Lower Containment Atmosphere Aligned to Upper Containment Radiation Monitor During Sampling.Caused by Personnel Error.Chemistry Training revised.W/900514 Ltr ML20043A2271990-05-14014 May 1990 LER 90-006-00:on 900414,auxiliary Bldg Isolation Occurred from Spent Fuel Pit Area Radiation Monitors 0-RM-90-102 & 103.Caused by Personnel Error.Training Ltr Issued to Instrument Mechanics & Operations personnel.W/900514 Ltr ML20043A2201990-05-14014 May 1990 LER 90-007-00:on 900413,discovered That Tech Spec Surveillance Requirement Not Performed within Required Interval.Caused by Personnel Error.Surveillance Successfully Performed Since missed.W/900514 Ltr ML20042G7861990-05-0909 May 1990 LER 90-005-00:on 900409,emergency Start of Four Emergency Diesel Generators Occurred While Attempting Transfer of Power.Caused by Personnel Error.Individuals Reprimanded, Training Initiated & Procedures revised.W/900509 Ltr ML20042G7931990-05-0909 May 1990 LER 90-008-00:on 900410,reactor Trip Occurred Resulting from General Warning Alarm on Both Trains of Solid State Protection Sys.Caused by Personnel Error.Individuals Disciplined & Site Wide Message distributed.W/900509 Ltr ML20042F3741990-05-0202 May 1990 LER 90-003-00:on 900404,control Room Ventilation Sys (CRVS) Transferred to Pressurization Mode.Caused by Electrical Transient in Vital Instrument Ac Bus PY-21A.CRVS Reset & Returned to Normal Operating modes.W/900502 Ltr ML20042E4191990-04-13013 April 1990 LER 90-007-00:on 900317 & 26,containment Ventilation Isolations Occurred During Purge Activities.Caused by Inadequate Procedural Guidance for Setpoint Determination. Alarm & Trip Setpoints increased.W/900413 Ltr ML20042E2021990-04-13013 April 1990 LER 90-005-00:on 900315,inadvertent Containment Vent Isolation Occurred While Preparing to Purge Containment. Caused by Lack of Attention to Detail by Operator.Operator Counseled & Received Administrative reprimand.W/900413 Ltr ML20012F5221990-04-0505 April 1990 LER 90-006-00:on 900307,containment Ventilation Isolation Occurred.Caused by Containment Particulate Level Too Close to Setpoint.Module Replaced.Radiation Alarm Setpoint Increased from 10% to 40% of Tech Spec limit.W/900406 Ltr ML20012D8611990-03-23023 March 1990 LER 90-004-00:on 900221,handswitches Controlling Operation of Isolation Valves on Steam Supply Line to Auxiliary Feedwater Pump Found in Manual Position.Cause Undetermined. Handswitches Placed in P-auto position.W/900323 Ltr ML20012C4271990-03-12012 March 1990 LER 90-003-00:on 900211,inadvertent Containment Vent Isolation Occurred.Caused by Lack of Attention to Detail in That Operator Did Not Look Closely Enough at Switch Designations.Personnel Involved counseled.W/900312 Ltr ML20011F7191990-03-0101 March 1990 LER 89-031-01:on 891205,RHR Pumps Determined to Have Deadheading Problem Identified by NRC Bulletin 88-004.Caused by Inadequate Technical Response to Bulletin.Training Ltr Issued to 10CFR50.59 reviewers.W/900301 Ltr ML20011F7421990-02-26026 February 1990 LER 90-002-00:on 900127,control Room Isolation Occurred When Circuit Breaker Opened Supplying Power to Radiation Monitor. Caused by Failure by Personnel to Exercise Sufficient Caution.Responsible Engineers reinstructed.W/900226 Ltr ML20011F7391990-02-26026 February 1990 LER 90-002-00:on 891122,value for Distance from Floor to Ctr Line of Level Switch 2-LS-87-21 Transposed in Variable Leg Calculation.Caused by Inattention to Detail.Procedure Revised to Replace Incorrect setpoint.W/900226 Ltr ML20006E3311990-02-0909 February 1990 LER 90-001-00:on 900112,Limiting Condition for Operation 3.0.3 Entered When Three of Four Lower Compartment Cooler Fan Motors Exceeded Lubrication Frequency.Caused by Personnel Error.Personnel counseled.W/900209 Ltr ML20006D5341990-02-0707 February 1990 LER 90-001-00:on 900108,discovered That Several ERCW Valves Not Being Periodically Verified to Be Correct.Caused by Personnel Error During Procedure Revs & Workplan Reviews. Info Notice Issued to Workplan reviewers.W/900207 Ltr ML19354E1631990-01-22022 January 1990 LER 89-036-00:on 891221,discovered That Surveillance Test Results Used for Declaring Diesel Generator 1B-B Operable Deficient.Caused by Instruction Not Including 60 Minute Run Time.Event Will Be Reviewed w/supervisors.W/900122 Ltr ML19354D8941990-01-16016 January 1990 LER 89-034-00:on 891215,leak Identified from Fitting on Vol Control Tank Level Transmitter & Auxiliary Bldg Evacuated, Preventing Fire Watch Patrol from Entering Bldg for Hourly Rounds.Fitting tightened.W/900116 Ltr ML19354D9061990-01-16016 January 1990 LER 89-033-00:on 891216,refueling Water Storage Tank Level Transmitters Failed High Due to Freezing from Extremely Cold Weather & Inappropriate Use of Calculations.Engineering Procedures Revised & Heating Installed in encl.W/900116 Ltr ML20005F8851990-01-0909 January 1990 LER 89-035-00:on 891210,turbine/reactor Trip Occurred from hi-hi Feedwater Level of 75% in Steam Generator 3.Caused by Failure of Loop 3 Main Feedwater Regulating Valve to Close. Equipment Adjusted & repaired.W/900109 Ltr ML20005E0801989-12-22022 December 1989 LER 89-032-00:on 891205,RHR Pumps Determined to Have Deadheading Problem,Per NRC Bulletin 88-004,resulting in Plant Operation Outside Design Basis.On 891128,RHR Pump Exceeded Head Criteria.Pumps started.W/891222 Ltr ML20005E0831989-12-22022 December 1989 LER 89-032-00:on 891201,discovered That Tech Spec Surveillance Requirement to Verify That Valves 1-67-748 & 2-67-748 in Open Position Not Met.Caused by Personnel Error.Correct Valve Position verified.W/891222 Ltr ML20005E1161989-12-22022 December 1989 LER 89-030-00:on 891204,fire Suppression Sys Deluge Valve Isolated More than 1 H W/O Required Continuous Fire Watch Establishment.Caused by Personal Communication Breakdown. Valve Opened & Foreman in Charge counseled.W/891222 Ltr 1994-05-09
[Table view] Category:RO)
MONTHYEARML20029E3351994-05-10010 May 1994 LER 94-006-00:on 940415,both Trains of CREVS Declared Inoperable.Caused by Tornado Warning & Sighting of Tornado Moving Toward Plant.Tornado Warnings downgraded.W/940510 Ltr ML20029E2021994-05-0909 May 1994 LER 94-004-00:on 940408,determined That TS Pressurizer Cooldown Limit Exceeded on 930618 & Not Restored within Required Timeframe.Caused by Unanticipated Sys Interaction. SI for Check Valve Opening Tests revised.W/940509 Ltr ML20029D8151994-05-0303 May 1994 LER 94-005-00:on 940403,inadvertent Fwis Occurred.Caused by Personnel Failure to Follow Work Document Instructions. Corrective Action:Individuals Were Counseled on Requirements to Follow Work Document Instruction steps.W/940503 Ltr ML20046B8351993-07-30030 July 1993 LER 93-017-00:on 930621,discovered 24-hour Telephone Notification Had Not Been Carried Out as Required by TS LCO 3.7.11.1 Action Statement (b)(2)(a) Due to Personnel Error. NRC Informed of Missed notification.W/930730 Ltr ML20046B8501993-07-30030 July 1993 LER 93-018-00:on 930704,DG Started Due to Improper WO Planning.Restored Power to 1BB Shutdown Board & Stopped Running DGs.W/930730 Ltr ML20046A4691993-07-19019 July 1993 LER 93-016-00:on 930619,Phase A,Auxiliary Bldg & Containment Isolations Manually Initiated as Result of Fuel Assembly Failing to Remain in Upright Position After Being Released. All Fuel Movement stopped.W/930719 Ltr ML20045J0111993-07-14014 July 1993 LER 93-015-00:on 930614,1A Start Bus Alternate Feeder Breaker Tripped Upon Start of Unit 1 RCP Which Resulted in Start of DG Due to Current Transformer Wired Incorrectly. Restored Offsite Power & Secured Final DG.W/930714 Ltr ML20045H0171993-07-12012 July 1993 LER 93-014-00:on 930611,determined That Inadequate Ventilation Design Resulted in Potential Inoperability of Vital Power Equipment.Design Being modified.W/930712 Ltr ML20045B9951993-06-15015 June 1993 LER 93-004-01:on 930222,determined That Blind Flange on Elevation 734 Personnel Airlock Outer Housing Leaking.Due to Improper Installation of Blind Flange.Evaluation Performed of Other 14 Double O-ring Blind flanges.W/930615 Ltr ML20045B9311993-06-10010 June 1993 LER 93-013-00:on 930514,fire Watch Was Not Performed within Time Frame Required by Tech Specs Due to Inadequate Supervision by Fire Protection Foreman.Fire Watch Patrol reestablished.W/930610 Ltr ML20045A7261993-06-0707 June 1993 LER 93-011-00:on 930507,discovered That Fire Barrier Breached W/O Proper Compensatory Measures Established.On 930505,door Leading to Room Housing Containment Spray HX 1A Breached.Roving Fire Watch Established & LCO 3.7.12 Entered ML20044H4501993-06-0303 June 1993 LER 93-012-00:on 930504,apparent Failure to Properly Identify & Plug SG Tube Determined to Exceed TS Plugging Limit.Caused by eddy-current Coordinator Not Ensuring Task requirements.Eddy-current Procedure revised.W/930603 Ltr ML20044H1561993-05-28028 May 1993 LER 93-010-00:on 930430,Westinghouse Identified Error in Development of Calculations for Cold Overpressure Mitigation Sys Setpoints.Caused by Vendor Failure to Consider Elevation Difference.Engineering Evaluation Performed ML20044E6341993-05-17017 May 1993 LER 93-009-00:on 930417,TS Surveillance Not Performed for Three Pipe Support Snubbers Because of Omission of Snubbers from Surveillance Instruction for Visual Insp.Snubbers Visually Inspected & Functionally tested.W/930517 Ltr ML20044B6751993-02-23023 February 1993 LER 93-001-00:on 930124,Unit 1 Ice Bed Temperature Recorder in MCR Declared Inoperable.Caused by Ineffective Communication.Appropriate Personnel Involved W/Event Have Been counseled.W/930223 Ltr ML20044B6141993-01-21021 January 1993 LER 92-026-00:on 921222,determined That Several ASME Section XI Pressure Tests Not Performed Due to Section XI Program Implementation Not Being well-defined,controlled or Documented.Test Expeditiously performed.W/930121 Ltr ML20024H2441991-05-22022 May 1991 LER 91-007-00:on 910422,LCO 3.0.3 Entered When Shaft of Train a Main Control Room Air Handling Unit Failed from Fatigue & Train B Out of Svc for Maint.Caused by Shaft Misalignment.New Shaft installed.W/910522 Ltr ML20029C1761991-03-21021 March 1991 LER 91-002-00:on 910211,unit Operated in Condition Prohibited by Tech Spec 3.3.3.8 Limiting Condition for Operation.Cause Under Investigation.Night Order Issued to Personnel Re Removal of Equipment from svc.W/910321 Ltr ML20029C1231991-03-18018 March 1991 LER 90-016-01:on 901117,determined That Calibr of Nuclear Instrumentation Sys intermediate-range Channels Set Nonconservatively.Caused by Lack of Operability Control for Rod Motion.Action Plan developed.W/910318 Ltr ML20029A6711991-02-25025 February 1991 LER 91-002-00:on 910124,LCOs 3.0.5 & 3.8.1.1 Entered When Both Trains of Emergency Gas Treatment Sys Declared Inoperable.Caused by Blown Fuse & Excessive Cycling of Air Start Sys.Fuse replaced.W/910225 Ltr ML20028H0331990-09-27027 September 1990 LER 90-019-00:on 900828,failure to Update P-250 Plant Computer Constants Resulted in Axial Flux Difference.Caused by Inadequate Procedures & Inappropriate Personnel Actions. Procedure 0-PI-NXX-092-001.0 revised.W/900927 Ltr ML20028G9201990-09-26026 September 1990 LER 90-020-00:on 900829,ventilation Sys Inoperable Due to Train B Diesel Generator Out of Svc.Caused by Stuck Microswitch Contacts on Pressure Switch 0-PS-311-172. Pressure Switch Adjusted & Returned to svc.W/900926 Ltr ML20044A9361990-07-0909 July 1990 LER 90-011-00:on 900608,determined That Actual Nuclear Instrumentation Sys Power Range Detector Currents Were 20% to 31% Lower than Predicted.Caused by Calibr Values Being Incorrectly Calculated.Channels corrected.W/900709 Ltr ML20044A3241990-06-25025 June 1990 LER 90-010-00:on 900526,limiting Condition for Operation Entered Because MSIV Failed to Close When Another MSIV Inoperable for Maint.Cause Attributed to Valve Stem & Valve Guide Binding.Operations Training Ltr issued.W/900625 Ltr ML20043H5091990-06-21021 June 1990 LER 90-009-00:on 900527,automatic Start of Auxiliary Feedwater Pumps Occurred When Both Main Feedwater Pumps Placed in Tripped Condition.Caused by Personnel Error.Trip Circuitry Reset & Operators counseled.W/900621 Ltr ML20043E5401990-06-0707 June 1990 LER 90-008-00:on 900514,two Control Room Isolations Occurred as Result of Spurious Spikes.Caused by Loose Terminations on Relay Socket.Loose Connections Properly terminated.W/900607 Ltr ML20043A4211990-05-16016 May 1990 LER 90-010-00:on 900416,containment Ventilation Isolation Occurred.Caused by Allowing Gaseous Radiation Level to Increase Too Close to Alarm Setpoint.Recovery from Isolation initiated.W/900516 Ltr ML20043A2261990-05-14014 May 1990 LER 90-009-00:on 900404,lower Containment Radiation Monitor Found Inoperable & Lower Containment Atmosphere Aligned to Upper Containment Radiation Monitor During Sampling.Caused by Personnel Error.Chemistry Training revised.W/900514 Ltr ML20043A2271990-05-14014 May 1990 LER 90-006-00:on 900414,auxiliary Bldg Isolation Occurred from Spent Fuel Pit Area Radiation Monitors 0-RM-90-102 & 103.Caused by Personnel Error.Training Ltr Issued to Instrument Mechanics & Operations personnel.W/900514 Ltr ML20043A2201990-05-14014 May 1990 LER 90-007-00:on 900413,discovered That Tech Spec Surveillance Requirement Not Performed within Required Interval.Caused by Personnel Error.Surveillance Successfully Performed Since missed.W/900514 Ltr ML20042G7861990-05-0909 May 1990 LER 90-005-00:on 900409,emergency Start of Four Emergency Diesel Generators Occurred While Attempting Transfer of Power.Caused by Personnel Error.Individuals Reprimanded, Training Initiated & Procedures revised.W/900509 Ltr ML20042G7931990-05-0909 May 1990 LER 90-008-00:on 900410,reactor Trip Occurred Resulting from General Warning Alarm on Both Trains of Solid State Protection Sys.Caused by Personnel Error.Individuals Disciplined & Site Wide Message distributed.W/900509 Ltr ML20042F3741990-05-0202 May 1990 LER 90-003-00:on 900404,control Room Ventilation Sys (CRVS) Transferred to Pressurization Mode.Caused by Electrical Transient in Vital Instrument Ac Bus PY-21A.CRVS Reset & Returned to Normal Operating modes.W/900502 Ltr ML20042E4191990-04-13013 April 1990 LER 90-007-00:on 900317 & 26,containment Ventilation Isolations Occurred During Purge Activities.Caused by Inadequate Procedural Guidance for Setpoint Determination. Alarm & Trip Setpoints increased.W/900413 Ltr ML20042E2021990-04-13013 April 1990 LER 90-005-00:on 900315,inadvertent Containment Vent Isolation Occurred While Preparing to Purge Containment. Caused by Lack of Attention to Detail by Operator.Operator Counseled & Received Administrative reprimand.W/900413 Ltr ML20012F5221990-04-0505 April 1990 LER 90-006-00:on 900307,containment Ventilation Isolation Occurred.Caused by Containment Particulate Level Too Close to Setpoint.Module Replaced.Radiation Alarm Setpoint Increased from 10% to 40% of Tech Spec limit.W/900406 Ltr ML20012D8611990-03-23023 March 1990 LER 90-004-00:on 900221,handswitches Controlling Operation of Isolation Valves on Steam Supply Line to Auxiliary Feedwater Pump Found in Manual Position.Cause Undetermined. Handswitches Placed in P-auto position.W/900323 Ltr ML20012C4271990-03-12012 March 1990 LER 90-003-00:on 900211,inadvertent Containment Vent Isolation Occurred.Caused by Lack of Attention to Detail in That Operator Did Not Look Closely Enough at Switch Designations.Personnel Involved counseled.W/900312 Ltr ML20011F7191990-03-0101 March 1990 LER 89-031-01:on 891205,RHR Pumps Determined to Have Deadheading Problem Identified by NRC Bulletin 88-004.Caused by Inadequate Technical Response to Bulletin.Training Ltr Issued to 10CFR50.59 reviewers.W/900301 Ltr ML20011F7421990-02-26026 February 1990 LER 90-002-00:on 900127,control Room Isolation Occurred When Circuit Breaker Opened Supplying Power to Radiation Monitor. Caused by Failure by Personnel to Exercise Sufficient Caution.Responsible Engineers reinstructed.W/900226 Ltr ML20011F7391990-02-26026 February 1990 LER 90-002-00:on 891122,value for Distance from Floor to Ctr Line of Level Switch 2-LS-87-21 Transposed in Variable Leg Calculation.Caused by Inattention to Detail.Procedure Revised to Replace Incorrect setpoint.W/900226 Ltr ML20006E3311990-02-0909 February 1990 LER 90-001-00:on 900112,Limiting Condition for Operation 3.0.3 Entered When Three of Four Lower Compartment Cooler Fan Motors Exceeded Lubrication Frequency.Caused by Personnel Error.Personnel counseled.W/900209 Ltr ML20006D5341990-02-0707 February 1990 LER 90-001-00:on 900108,discovered That Several ERCW Valves Not Being Periodically Verified to Be Correct.Caused by Personnel Error During Procedure Revs & Workplan Reviews. Info Notice Issued to Workplan reviewers.W/900207 Ltr ML19354E1631990-01-22022 January 1990 LER 89-036-00:on 891221,discovered That Surveillance Test Results Used for Declaring Diesel Generator 1B-B Operable Deficient.Caused by Instruction Not Including 60 Minute Run Time.Event Will Be Reviewed w/supervisors.W/900122 Ltr ML19354D8941990-01-16016 January 1990 LER 89-034-00:on 891215,leak Identified from Fitting on Vol Control Tank Level Transmitter & Auxiliary Bldg Evacuated, Preventing Fire Watch Patrol from Entering Bldg for Hourly Rounds.Fitting tightened.W/900116 Ltr ML19354D9061990-01-16016 January 1990 LER 89-033-00:on 891216,refueling Water Storage Tank Level Transmitters Failed High Due to Freezing from Extremely Cold Weather & Inappropriate Use of Calculations.Engineering Procedures Revised & Heating Installed in encl.W/900116 Ltr ML20005F8851990-01-0909 January 1990 LER 89-035-00:on 891210,turbine/reactor Trip Occurred from hi-hi Feedwater Level of 75% in Steam Generator 3.Caused by Failure of Loop 3 Main Feedwater Regulating Valve to Close. Equipment Adjusted & repaired.W/900109 Ltr ML20005E0801989-12-22022 December 1989 LER 89-032-00:on 891205,RHR Pumps Determined to Have Deadheading Problem,Per NRC Bulletin 88-004,resulting in Plant Operation Outside Design Basis.On 891128,RHR Pump Exceeded Head Criteria.Pumps started.W/891222 Ltr ML20005E0831989-12-22022 December 1989 LER 89-032-00:on 891201,discovered That Tech Spec Surveillance Requirement to Verify That Valves 1-67-748 & 2-67-748 in Open Position Not Met.Caused by Personnel Error.Correct Valve Position verified.W/891222 Ltr ML20005E1161989-12-22022 December 1989 LER 89-030-00:on 891204,fire Suppression Sys Deluge Valve Isolated More than 1 H W/O Required Continuous Fire Watch Establishment.Caused by Personal Communication Breakdown. Valve Opened & Foreman in Charge counseled.W/891222 Ltr 1994-05-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
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o EVALUATION LOGIC FOR PART 21 SQRO-50-327/
Originating Document No. 80050_and PRO' 1-80-107 &
Yes Eo 1-80-108 I. Deficiency of a plant necurity system? X
- 1. Could defect create a substantial safety hazard? X If yes, report as part 21.
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II. Is the component necessary to ensure: -
- 1. The integrity of the reactor coolant boundary? X
- 2. The capabili ty to shut down reactor and maintain it in a safe shutdown condition? X
- 3. The capability to prevent or mitigate the consequences of accidents which could result in potential cffsite exposure comparable to those referred to in 10 CFR 100.117 X
't III. Is defect in a basic component one that has been accepted for ownership? X Installed for une or operation? X If a yes in II and III above, could defect create a substantial safety hazard? X If yes, report as part 21.
IV. Is defect in a baste component:
A condition that could contribute to exceeding of safety limit? X If yes to one of II and IV above, report as part 21.
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