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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] |
Text
. . - .
A m________.- _ _ _ _ _ _ . . - . . . _ . - _ _ . . _ . . _ _ . . _ _ _ _ _ , . _
Tennessee Valley Aeonty, Post Off ce Box 2000. Soddy Daisy. lennessee 37379-2000 Robert A. Fenech vce President. SeQuoyah Nuclear Plant July 30, 1993 i
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk f Washington, D.C. 20555 _
l f
Centlemen:
TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 -
DOCKET NOS. 50-327 AND 50-328 - FACILITY OPERATING LICENSES DPR-77 AND DPR LICENSEE EVENT REPORT (LER) 50-327/93017 The enclosed LER provides details of a technical specification (TS). . ,
limiting condition for operation action statement that was not complied with.
This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(b) as an operation prohibited by TSs.
Sincerely, ,
? 'M Robert A. Fenech Enclosure '
cc: See page 2 i
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U.S. Nuclear Regulatory Commission Page 2 July 30,1993 cc (Enclosure):
INPO Records Center
' Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta,. Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint,-North 11555 Rockville Pike.
Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711
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NRC form 366 U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92 tlCENSEE EVENT REPORT (LER)
FACILITY NAME (1) lDOCKETNUMBER(2) l_PAGL131-
,JtRVoyah Nuclear Plant (SON). Unj.t 1 1015l0l0l013 12 17 1110LL013 l
TI"LE (4) Failure to Comply with Technical Specification Limiting Condition for Operation Action Statement
_atd_ Notify NRC by Telephone Regardina the Auxiliary Buildino Fire Sup.pn ssion System Beina Nonfunctional
_EENT DAY (5) l LER NUMBER (6) l REPORT DATE (7) l OTHER FAHL111LS_JHV_QLyED_(8) l l l l l SEQUENTIAL l l REVISION l l l l FACILITY NAMES lDOCKETNUMBER(S)
MONTHl DAY lYEAR lYEAR l I NUMBER l l NUMBER IMONTHl DAY lYEAR l Seavovah. Unit 2 1015101010131218 ;
I I I l_I l_I I I I I I QLtiL2.L1LsL11 91 31 1011171 1 0_I O I OI 713Lol 9131 _Jsls10191DI i 1 t OPERATING l lTHISREPORTISSUBMITTEDPURSUANTTOTHEREQUIREMENTSOF10CFR5: ;
HODE l l (Check one or more of the following)(ll)
(9) 1 61 l20.402(b) l__l20.405(c) l_l50.73(a)(2)(iv) l_]73.71(b)
POWER l l__l20.405(a)(1)(i) L 150.36(c)(i) l__l50.73(a)(2)(v) l_l73.7i(c)
LEVEL l l_l20.405(a)(1)(ii) l_l50.36(c)(2) L_l50.73(a)(2)(vii) l._l0THER(Specifyin ,
(10) 101 OLQj_l20.405(a)(1)(lii) lKKl50.73(a)(2)(i) l_l50.73(a)(2)(viii)(A) l Abstract below and in l_l20.405(a)(1)(iv) l_l50.73(a)(2)(li) L 150.73(a)(2)(viii)(B) i Text, NRC rorm 366A)
I 120.405fa)(1)(v) I 150.73(a)(21(iii) I 150.73(a)(2)(x) l LICEtl3EL_CDNIACT FOR THIS LER (12)
NAME l TELEE11QNE NUMBER lAREACODEl +
C. H. Whittemore. Compliance Licensino l6111518l4131-l712l110 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPQRT (13) l l l l REPORTABLE l l l l l l REPORTABLE l CAUSIjSX11EliLc0MtDNENT IMANUFACIVRERl TO NPRDS [ ICAUSEjlyJIftil COMPONENT lMANUfACI1LRERl TO NPRDS l l I I I I I I I I I I 1 I I I I I i 1 1 I I I I I I l i I I I I I I I I I I I I I I I I I I I .
I I I I I I I I I I I I I I I I I I I I I i l I i
- SUPPLEMENTAL R_EPORT EXPECTED (14) l EXPECTED lMQMTHlDAYlYEAR
_,_ l_ l SUBMISSION l l l ,
! YES (If ves. complete EXPECTED _ SUBMISSION DATE) l X l NO l DATE (15) l l l l I I i I
ABSTRACT (Limit to 1400 spaces, i .e., approximately fif teen single-space typewritten lines) (16) i On July 2, 1993, with Unit 1 in Mode 6 for the Cycle 6 refueling outage and Unit 2 in Mode 5 for a maintenance outage, it was discovered that a 24-hour telephone notification to NRC had not been carried out as required by Technical Specification (TS) Limiting :
Condition for Operation (LCO) 3.7.11.1 Action Statement (b)(2)(a). The TS requires that '
a backup suppression system be established and that NRC be notified any time the high ~!
pressure fire protection (HPFP) water suppression system is inoperable. A portion of '
the auxiliary building HPFP water suppression system had been taken out of service for a planned maintenance activity. Appropriate compensatory measures had been established.
The cause of the event was personnel error because of an inadequate review of the LCO action statement. Upon discovery, the notification was made and an incident investigation was initiated. The maintenance activity was completed and the system was returned to service on July 3, 1993.
I l
I l
NRC form 366(6-89) i
, NRC-Form 366A U.S. NUCLEAR REGULATORY COMMISSION Approvod OMB No. 3150-0104 (6-89) Expires 4/30/92
, LICENSEE EVENT RET 9RT (LER)
. TEXT CONTINUATION FACILITY NAME (1) lDOCKETNUMBER(2)} LER NUMBER (6) l l PAGE (3) l l l l SEQUENTIAL l l REVISION l l l l l Sequoyah Nuclear Plant (SQN), Unit 1 l jlEARl i NUMQIR l l NUMBER l l l l l 10lSJQ[Qj013 12 17 19 13 l-l_0 l 1 1 7 l-l O_l 0 1 01 2j.Qfj_QJ_L TEXT (If more space is required, use additional NRC Form 366A's) (17)
I. PLANT CONDITIONS Unit I was in Mode 6 for the Unit 1 Cycle 6 (U1C6) refueling outage (RFO) and Unit 2 was in Mode 5 for a maintenance outage.
II. DESCRIPTION OF EVENTS A. Eyent At approximately 1530 Eastern daylight time (EDT) on July 2, 1993, it was discovered that Limiting Condition for Operation (LCO) Action Statement 3.7.11.1.b.2 had not been completely complied with in that a notification to NRC, i.e., a 24-hour telephone call, had not been carried out as required by technical specifications (TSs). On June 21, 1993, Operations personnel tagged out a section of the auxiliary building high pressure fire protection (HPFP) system to allow maintenance to be performed on fire suppression piping. This section of piping contained several TS-required hose stations and sprinkler systems. LCOs 3.7.11.2 and 3.7.11.4 were entered, and compensatory measures in the form of fire watches and backup fire suppression were established at 2100 EDT on June 21, 1993, to reflect the hose stations and sprink..er systems being nonfunctional. LCO 3.7.11.1 for the fire protection suppression water -
system should also have been entered. However, the LCO was not entered, and the telephone call required by the_LCO 3.7.11.1 action statement was not made. On June 22, 1993, at 1541 EDT, the day-shift assistant shift operations supervisor (ASOS) entered Loos 3.7.11.1 and 3.7.11.4 to reflect an increased maintenance work scope; valves designated as isolation valves on the original action plan were leaking through. The LCO action statement requiring that NRC be notified by telephone was again not carried out. On July 2, 1993, when the day-shift shift operations supervisor (SOS) and Fire Protection Manager were discussing a related matter,'the error was discovered. Upon discovery, the appropriate LCO action. statement requirements were complied with.
B. InDperable StInnt.ures. Components. or Systems That Contributed to the Event None.
C. Dates and Aoproximate Times of Major Occurrente.R June 21, 1993 Initial hold tags were attached to isolation valves to isolate at 2100 EDT a section of piping that contained the pin hole leaks. LCOs 3.7.11.2 and 3.7.11.4 were entered. Appropriate compensatory measures were established. The telephone notification to NRC was not made because LCO 3.7.11.1 was not entered.
NRC form 366(6-89)
', NRC'Torm 366A U.S. NUCtEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Enpires 4/30/92
. LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACItITY NAME (1) lDOCKETNUMBER(2)I LER NUMBER (6) I l PAGE (3) l l .l l SEQUENTIAL l l REVISION l l l l l Sequoyah Nuclear Plant (SQN), Unit 1 l lYEAR l l NUMBER l l NUMBER [ l l l l 10lil01QJQl3 12 17 19 13 l-l Q_] 1 I 7 l _l. O I O Q j_310Tl 01 5 TEXT (If more space is required, use additional NRC Form 366A's) il7)
June 22, 1993 An additional section of the fire suppression system was at 1541 EDT added to the original maintenance work order. LCOs 3.7.11.1 and 3.7.11.4 were cntered for the additional section of the fire suppression system that was made nonfunctional. The telephone call was not made because this was considered an extension to the orginal LCOs.
June 22, 1993 After reviewing the previous shift's log entry concerning the at 1945 EDT 3.7.11.1 entry and discussing the issue, the night shift ASOS entered 3.7.11.1 for the initial scope of maintenance activity. The LCO entry was noted as a late entry for June 21, 1993 (the telephone call was not made).
July 2, 1993 The error of not making the telephone call on June 21, 1993, at 1000 EDT was discovered when two SOSs and the Fire Protection Manager were discussing the entry into LCO 3.7.11.1 for a similar issue.
July 2, 1993 NRC was notified by telephone regarding the June 21, 1993, at 1600 EDT event where a section of the auxiliary building fire suppression system was taken out of service and rendered nonfunctional.
July 3, 1993 Af ter being repaired, the IIPFP piping was returned to at 2048 EDT service, and LCOs 3.7.11.1, 3.7.11.2, and 3.7.11.4 were exited.
D. Other Systems or Secondary Functions Affected None - No other system was involved.
E. Method of Discovery The error was discovered when two SOSs and the Fire Protection Manager were discussing the entry of 3.7.11.1 for a similar issue.
F. Operation Action Upon discovery of the error, the Operations Manager informed the appropriate ;
personnel and notified NRC by telephone. l G. Safety System Responaga l None - No safety system response was required.
NRC F orm %6(6-89) l
.. NR form 366A U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) lDOCKETNUMBER(2) l LER NUMBER (6) l l PAGE (3) l l l l SEQUENTIAL l l REVISION] l l -l l Sequoyah Nuclear Plant (SQN), Unit 1 l lYEAR I l NUMBER .l_ l NUMilIRl l l l l l015faj0l013 l2_171913 l-l 01 1 17l-l01 0lOl_4l0Fl0l5 TEXT (If more space is required, use additional NRC Form 366A's) (17)
III. CAUSE OF EVENT A. Ituediata_Cauan The immediate cause of the event was the failure to comply with the LCO action statement in its entirety.
B. Rnot Cause The root cause of this event is personnel error because of an inadequate review of Gie LCD setion statement on the part of Operations' personnel. ,
C. Can.tributing Cault TS 3.7.11.1 is written with the intent of notifying NRC when a major fire suppression header or pump is nonfunctional because of an unexpected loss of equipment or accident. However, literal compliance of the TS requires a 24-hour telephone call when any part of the fire suppression system (withir. '
the LCO description) is taken out of service and made nonfunctional even for .:
preplanned maintenance activity. The logic of this type of action le not consistent with the safety significance of the issue, nor with the action statements of other LCOs outside the Fire Protection arena.
IV. ANALYSIS OF EVENT Maintenance was being performed via approved plant procedures with an action plan r in effect. The appropriate TS LCO action statement compensatory measures were in place, with the exception of the 24-hour telephone call to NRC. Therefore, it can i be concluded that there were no adverse consequences to plant personnel or to the public as a result of this event.
V. CORRECTIVE ACTIONS A. 11amediate Corrective Action Upon discovery of the missed notification, NRC was informed by telephone of the condition of the fire suppression system in the auxiliary building and also of the missed notification. The telephone call was confirmed by f acsimile on the next working day. Additionally, an incident investigation i was initiated to determine the cause of the event and to formulate corrective action to prevent recurrence.
WRC Form 366(6-89) l
$ Nil { Form 366A U.S. NUCLEAR REGUtATORY COMMISSION Approved OMB No. 3150-0104 (6-89) Expires 4/30/92
. LICENSEE EVENT REPORT (LER)
- TEXT CONTINUATION FACItITY NAME (1) lDOCKETNUMBER(2)j LER NUMBER (6) l l PAGE (3) l l l l SEQUENTIAL l l REVISION l l l l l Sequoyah Nuclear Plant (SQN). Unit 1 l 1YI.AR_1_ l NUtjQER l 1 NUM31R_1 l l l l 1215j1[QJD l 3 12 17 19 13 l-l 0 1 1 l 7 l-LD l 0101Sl0Fl015 TEXT (If more space is required, use additional NRC Form 366A's) (17)
B. Corrective Action to Prevent Recurrence The Operations Superintendent has issued a policy order to Operations personnel describing their responsibility to ensure TS compliance.
The Fire Protection Manager has submitted a training letter describing this event to Operations Training for issue to all ASOS/ SOS personnel.
The Fire Protection Manager has submitted a TS change request to revise the fire protection TS action statement reporting requirements.
VI. ADDITIONAL INFORMATION A. Eailed Componenta None - This was a planned work activity to repair through-the-wall pin hole i leaks in the fire suppression piping.
B. Previous Similar Events A search of the LER and the Nuclear Experience Review databases was conducted for previous or similar events. The results of this search revealed 29 items, only one of which occurred at SQN. This one item (LER 327/91014) was reviewed and found not to be relevant to the present event.
A search of the specia! reports generated at SQN from 1987 to the present was conducted. This search revealed that 112 reports had been submitted to NRC primarily for fire protection issues. Only 13 of the reports submitted to the commission involved TS LCO 3.7.11.1. Each of these 13 reports was reviewed for the purpose of establishing whether any of the reporting requirements had been untimely. Each and every report documented that the telephone and facsimile notifications had been timely and in compliance with the TS action ,
statements.
In summary, this event can be classified as an isolated incident with no previous or similar issues involving corrective actions that could have or should have prevented this event.
VII. COMMITMENTS None.
j I
NRC f orm 366(6-09) I