Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045J0111993-07-14014 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 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 ML20005D7351989-12-0707 December 1989 LER 89-026-00:on 891107,Limiting Condition for Operation 3.0.3 Entered as Result of More than One Rod Position Indicator (RPI) Per Bank Being Inoperable.Caused by Lack of Preventive Maint.Rpis adjusted.W/891207 Ltr ML19325D2481989-10-13013 October 1989 LER 89-013-00:on 890914,found That Min Number of Operable Photoelectric Fire Detectors Not Maintained for Zone 374. Caused by Identification & Ordering of Incorrect Replacement Fire Detectors.Hourly Fire Watch established.W/891013 Ltr ML20028B6251982-11-29029 November 1982 LER 82-130/03L-0:on 820928,during Routine Performance of Surveillance Instruction 106,group 1,rows 1 & 2 Min Average Ice Weight Less than Required.Caused by Sublimation of Ice in Crane Wall Area.Ice Added ML20052H6711982-05-14014 May 1982 LER 82-053/03L-0:on 820415,vital Battery Bank II Declared Inoperable When Cell 4 Connection Resistance Found Greater than 150 micro-ohms.Caused by Loose Bolt Connection.Bolt Torqued & Resistance Checked ML20040G6321982-02-0505 February 1982 LER 82-007/03L-0:on 820108,in Mode 1 at 100% Power,Rod Position Indicator P-4 (Shutdown Bank a) Indicated Greater than 12 Steps Below Step Counter.Defective Indicator Recalibr & Returned to Svc.Connector Pins Cleaned ML20039A5651981-12-10010 December 1981 LER 81-134/03L-0:on 811111,relay Contacts for Fire Zone 367 Reactor Coolant Pump 3 Found Wired Normally Closed.Correct Configuration Is Normally Open.Caused by Error in Connection Drawings.Connection Drawings Revised ML20039A5701981-12-0404 December 1981 LER 81-126/03L-0:on 811105,nuclear Instrumentation Sys Power Range Channel III (N-43) Declared Inoperable.Caused When Instrument Power Fuse Was Inadvertently Pulled Instead of Control Power Fuse.Procedures Revised ML20011B0251981-10-23023 October 1981 LER 81-121/03L-0:on 810925,flux Imbalance Penalty Function Generator XM-92-5005K Found Inoperable.Caused by Module Drift.Module Recalibr ML19350C3861981-03-24024 March 1981 LER 81-028/03L-0:on 810224,oxygen Analyzer Declared Inoperable.Caused by Damaged Oxygen Cell Due to Collection of Condensed Moisture.Lines Cleared,Cell Replaced & Analyzer Recalibr.Addl Vents Will Be Added ML19345F4181981-02-10010 February 1981 LER 81-008/03L-0:on 810116,three Intermediate Deck Doors to Ice Condenser,Under Air Handling Units 6A,8A & 8B,found Frozen Closed.Caused by Frozen Water in Drain Lines Due to Fuse Failure in Heat Tape Controller.Ice Removed ML19351C9381980-10-0202 October 1980 LER 80-148/03L-0:on 800904,shield Bldg Vent Monitor Declared Inoperable Due to Loss of Sample Air Flow.Caused by Worn Out Sample Pump Drive Belt.Belt Replaced & Monitor Returned to Svc ML19332A5981980-09-11011 September 1980 LER 80-152/03L-0:on 800812,diesel Generator Battery IB-B Cells 49-51 Were Found in Discharged Condition.Caused by Inadequate Procedure.Procedure Has Been Changed & Personnel Reinstructed ML19331D7461980-08-27027 August 1980 LER 80-094/03L-0:on 800620,w/unit in Modes 3,4 or 5,May 1980 Evaluation for Tritium Was Not Performed.Caused by Inadequate Description in Procedure SI-415 for Taking Monthly Samples While Unit Is in Different Modes ML19344B1451980-08-19019 August 1980 LER 80-124/03L-0:on 800719,during Low Power Testing in Mode 2,hydrogen Analyzer H2AN-43-200 Was Declared Inoperable Due to Low Sample Flow.Caused by Tripping of Sample Pump Motor Thermal Overload Due to Ambient Temp in Annulus ML19344E0871980-08-19019 August 1980 LER 80-133/03L-0:on 800718,sample Pump Motor for Hydrogen Analyzer 1-2AN-43-210 Declared Inoperable During Low Power Testing.Caused by Tripped Motor Thermal Overload. Motor Was Allowed to Cool & Thermal Overload Reset ML19330A8681980-07-22022 July 1980 LER 80-107/03L-0:on 800623,while in Mode 3,steam Generator 3 Level Indication,Loop 1-1-3-97,indicated Approx 10% Higher than Two Narrow Range Channels.Caused by Defective Transmitter on Panel 1-1-185 in Accumulator Room 4 ML19318C0801980-06-24024 June 1980 LER-80-077/03L-0:on 800525,B Train RHR & B Train Containment Spray Pumps Were Inoperable Because Valve FCV-63-73 Failed to Open.Caused by Valve Failing to Actuate Interlock Limit Switch ML19318A9461980-06-19019 June 1980 LER 80-061/03L-0:on 800521,auxiliary Bldg,Vent Radiation monitor,0-RM-90-10B,declared Inoperable Due to Spurious High Rad Spikes.Caused by Defective 24-volt Power Supply. Power Supply Replaced & Monitor Returned to Svc ML19309A8691980-03-28028 March 1980 LER 80-007/01T-0:on 800315,following Initial Core Loading, Found Incorrect (Nonconservative) Valve Operator Weights Used in Seismic Analysis for Component Cooling Water Valves FCV-70-133,134 & 183.Caused by Incorrect Vendor Data 1993-07-14
[Table view] Category:RO)
MONTHYEARML20045J0111993-07-14014 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 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 ML20005D7351989-12-0707 December 1989 LER 89-026-00:on 891107,Limiting Condition for Operation 3.0.3 Entered as Result of More than One Rod Position Indicator (RPI) Per Bank Being Inoperable.Caused by Lack of Preventive Maint.Rpis adjusted.W/891207 Ltr ML19325D2481989-10-13013 October 1989 LER 89-013-00:on 890914,found That Min Number of Operable Photoelectric Fire Detectors Not Maintained for Zone 374. Caused by Identification & Ordering of Incorrect Replacement Fire Detectors.Hourly Fire Watch established.W/891013 Ltr ML20028B6251982-11-29029 November 1982 LER 82-130/03L-0:on 820928,during Routine Performance of Surveillance Instruction 106,group 1,rows 1 & 2 Min Average Ice Weight Less than Required.Caused by Sublimation of Ice in Crane Wall Area.Ice Added ML20052H6711982-05-14014 May 1982 LER 82-053/03L-0:on 820415,vital Battery Bank II Declared Inoperable When Cell 4 Connection Resistance Found Greater than 150 micro-ohms.Caused by Loose Bolt Connection.Bolt Torqued & Resistance Checked ML20040G6321982-02-0505 February 1982 LER 82-007/03L-0:on 820108,in Mode 1 at 100% Power,Rod Position Indicator P-4 (Shutdown Bank a) Indicated Greater than 12 Steps Below Step Counter.Defective Indicator Recalibr & Returned to Svc.Connector Pins Cleaned ML20039A5651981-12-10010 December 1981 LER 81-134/03L-0:on 811111,relay Contacts for Fire Zone 367 Reactor Coolant Pump 3 Found Wired Normally Closed.Correct Configuration Is Normally Open.Caused by Error in Connection Drawings.Connection Drawings Revised ML20039A5701981-12-0404 December 1981 LER 81-126/03L-0:on 811105,nuclear Instrumentation Sys Power Range Channel III (N-43) Declared Inoperable.Caused When Instrument Power Fuse Was Inadvertently Pulled Instead of Control Power Fuse.Procedures Revised ML20011B0251981-10-23023 October 1981 LER 81-121/03L-0:on 810925,flux Imbalance Penalty Function Generator XM-92-5005K Found Inoperable.Caused by Module Drift.Module Recalibr ML19350C3861981-03-24024 March 1981 LER 81-028/03L-0:on 810224,oxygen Analyzer Declared Inoperable.Caused by Damaged Oxygen Cell Due to Collection of Condensed Moisture.Lines Cleared,Cell Replaced & Analyzer Recalibr.Addl Vents Will Be Added ML19345F4181981-02-10010 February 1981 LER 81-008/03L-0:on 810116,three Intermediate Deck Doors to Ice Condenser,Under Air Handling Units 6A,8A & 8B,found Frozen Closed.Caused by Frozen Water in Drain Lines Due to Fuse Failure in Heat Tape Controller.Ice Removed ML19351C9381980-10-0202 October 1980 LER 80-148/03L-0:on 800904,shield Bldg Vent Monitor Declared Inoperable Due to Loss of Sample Air Flow.Caused by Worn Out Sample Pump Drive Belt.Belt Replaced & Monitor Returned to Svc ML19332A5981980-09-11011 September 1980 LER 80-152/03L-0:on 800812,diesel Generator Battery IB-B Cells 49-51 Were Found in Discharged Condition.Caused by Inadequate Procedure.Procedure Has Been Changed & Personnel Reinstructed ML19331D7461980-08-27027 August 1980 LER 80-094/03L-0:on 800620,w/unit in Modes 3,4 or 5,May 1980 Evaluation for Tritium Was Not Performed.Caused by Inadequate Description in Procedure SI-415 for Taking Monthly Samples While Unit Is in Different Modes ML19344B1451980-08-19019 August 1980 LER 80-124/03L-0:on 800719,during Low Power Testing in Mode 2,hydrogen Analyzer H2AN-43-200 Was Declared Inoperable Due to Low Sample Flow.Caused by Tripping of Sample Pump Motor Thermal Overload Due to Ambient Temp in Annulus ML19344E0871980-08-19019 August 1980 LER 80-133/03L-0:on 800718,sample Pump Motor for Hydrogen Analyzer 1-2AN-43-210 Declared Inoperable During Low Power Testing.Caused by Tripped Motor Thermal Overload. Motor Was Allowed to Cool & Thermal Overload Reset ML19330A8681980-07-22022 July 1980 LER 80-107/03L-0:on 800623,while in Mode 3,steam Generator 3 Level Indication,Loop 1-1-3-97,indicated Approx 10% Higher than Two Narrow Range Channels.Caused by Defective Transmitter on Panel 1-1-185 in Accumulator Room 4 ML19318C0801980-06-24024 June 1980 LER-80-077/03L-0:on 800525,B Train RHR & B Train Containment Spray Pumps Were Inoperable Because Valve FCV-63-73 Failed to Open.Caused by Valve Failing to Actuate Interlock Limit Switch ML19318A9461980-06-19019 June 1980 LER 80-061/03L-0:on 800521,auxiliary Bldg,Vent Radiation monitor,0-RM-90-10B,declared Inoperable Due to Spurious High Rad Spikes.Caused by Defective 24-volt Power Supply. Power Supply Replaced & Monitor Returned to Svc ML19309A8691980-03-28028 March 1980 LER 80-007/01T-0:on 800315,following Initial Core Loading, Found Incorrect (Nonconservative) Valve Operator Weights Used in Seismic Analysis for Component Cooling Water Valves FCV-70-133,134 & 183.Caused by Incorrect Vendor Data 1993-07-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
ML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 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 ML20212A1841999-08-25025 August 1999 Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage 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 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 05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With 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 ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively 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 05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
ML20198C0211998-12-16016 December 1998 Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively 05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
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 ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively ML20195H0831998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 226 to Licenses DPR-77 & DPR-79,respectively 05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
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 05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
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 ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively 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 1999-09-30
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