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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D6301994-05-0505 May 1994 LER 94-003-00:on 940405,reactor Tripped Due to Main Power Transformer Failure.Corrective Actions:Detailed Investigation Performed for Collateral Damage & Isophase Bus Cleaned & inspected.W/940505 Ltr ML20029D2351994-04-29029 April 1994 LER 94-006-00:on 940330,discovered That Braidwood Cooling Lake Hydrographic Survey Was Not Completed within Required Time.Cause Was Personnel Error.Corrective Action: Surveillance Was Completed within 24 hours.W/940429 Ltr ML20029D6121994-04-29029 April 1994 LER 94-002-00:on 940331,discovered 2A Auxiliary Feedwater Pump Auto Starting.Caused by Procedural Deficiency. Auxiliary Feedwater Pump 2A Secured by Placing Control Switch in Pull Out position.W/940429 Ltr ML20046D5971993-08-19019 August 1993 LER 93-005-00:on 930720,missed Surveillance on Containment Isolation Valve Occurred Due to Personnel Error & Mgt Deficiency.Enhanced Procedures,Training & Counseling. W/930819 Ltr ML20044F5531993-05-19019 May 1993 LER 93-003-00:on 930419,TS Violated Due to Source Range Reactor Trip Capability Being Blocked.Caused by Personnel Error & Procedural Deficiency.Individuals Involved Counseled & Procedure developed.W/930518 Ltr ML20044D2071993-05-14014 May 1993 LER 93-002-00:on 930414,unplanned ESF Actuation Occurred When All Four SI Accumulator Isolation Valves Closed & Accumulator Pressure Reduced.Caused by Mgt Deficiency. Training Will Be conducted.W/930514 Ltr ML20024G7411991-04-24024 April 1991 LER 91-005-00:on 910326,main Control Room Ventilation Sys Shifted to Emergency Mode of Operation Due to Momentary Fluctuation in Voltage Available to Monitor.Lightning Protection Sys Being modified.W/910424 Ltr ML20028H8631991-01-24024 January 1991 LER 90-023-00:on 901230,generator Neutral Ground Overcurrent Protective Relay Actuated & Tripped Main Generator.Caused by Internal Generator Defect.Main Generator Disassembled & Rotor Removed to Locate ground.W/910124 Ltr ML20028G9151990-09-24024 September 1990 LER 90-015-00:on 900827,auxiliary Bldg Vent Stack Grab Sample Missed.Caused by Personnel Error & Deficient Work Practices.Training Provided,Program Modified & Station Reviewing Nonroutine Surveillance process.W/900924 Ltr ML20043H4071990-06-20020 June 1990 LER 90-007-00:on 900523,pressurizer Pressure Channel 458 Failed Low & Channel 455 Deviated in Excess of Remaining Two Channels.Caused by Defective Wire on Internal Portion of Pressure Transmitter.Transmitter replaced.W/900621 Ltr ML20043G6051990-06-14014 June 1990 LER 90-008-00:on 900517,unit at Power Permissive Circuit Actuated on Train a of Solid State Protection Sys.Caused by Procedural Deficiency in That Switch Rotation Not Specified. Procedure revised.W/900614 Ltr ML20043A6571990-05-16016 May 1990 LER 90-006-00:on 891204 & 900416,diesel Generator 1B Experienced Slow Start.Caused by Crisscrossed Starting Airlines for Cylinders 6L & 9L.Starting Airlines Reconnected & Verified to correct.W/900516 Ltr ML20043A6611990-05-14014 May 1990 LER 90-004-00:on 900416,diesel Generator 2A Speed Oscillated Prior to Maint Teardown.Caused by Component Failure.Resistors Replaced & Placed on 3-yr Replacement frequency.W/900516 Ltr ML20042G7041990-05-11011 May 1990 LER 90-005-00:on 900413,determined That Pressures for MSIVs a & D Were Outside Acceptance Criteria of Procedure.Caused by Procedural Deficiencies.Procedures Being Revised to Reflect Values of 4,800 Psig to 6,000 psig.W/900511 Ltr ML20042F5441990-05-0404 May 1990 LER 90-003-00:on 900405,inadvertent Train B Safety Injection Initiation Signal Occurred Due to Programmatic Deficiency. Training Developed & Lens Evaluated for Replacement. W/900503 Ltr ML20006E4811990-02-0909 February 1990 LER 90-002-03:on 900119,discovered That Flanges Not Added to Procedure 1BwOS, Primary Containment Integrity Verification of Outside Containment Isolation Devices. Caused by Program Weakness.Training held.W/900216 Ltr ML20006E4041990-02-0202 February 1990 LER 90-001-00:on 900112,reactor Tripped During Dc Ground Isolation Activities When Auxiliary Relay Energized,Causing Turbine Governor & Reheat Interceptor Valves to Close.Caused by Increasing Steam Pressure.Valves closed.W/900206 Ltr ML19354E0141990-01-22022 January 1990 LER 89-020-00:on 891223,failure to Verify Safety Injection Accumulator Boron Concentration within Specified Time.Caused by Programmatic Deficiency.Procedure Revised to Include Action Requirement sheet.W/900122 Ltr ML19354E0131990-01-16016 January 1990 LER 89-008-00:on 891228,equipment Attendant Discovered Refueling Water Storage Tank Vent Line Temp Less than 35 F. Caused by Preservice Deficiency.Storage Tank Vent Path Temp Verified at 36 F.W/900119 Ltr ML20006B2081990-01-12012 January 1990 LER 89-019-00:on 891219,discovered That Procedure Did Not Adequately Test Response Times for High Steamline Pressure Rate Steamline Isolation Signal.Caused by Deficient Procedure.Procedures Re Response Time revised.W/900112 Ltr ML20005F9611990-01-0808 January 1990 LER 89-017-00:on 891206,gas Detector Channel of Process Radiation Monitor Experienced Spike,Resulting in Alert Alarm.On 891210,spike on Channel Resulted in High Radiation Alarm.Caused by Failed detector.W/900109 Ltr ML20005E8561990-01-0202 January 1990 LER 89-018-00:on 891215,as Lead on volt-ohm Meter Landed, Containment Bldg Fuel Handling Incident Area Radiation Monitor Went Into Alert Alarm & Interlock Actuation.Caused by Procedure Deficiency.Signal reset.W/900102 Ltr ML20005E7851989-12-29029 December 1989 LER 89-016-00:on 891201,RHR Pump Suction Relief Valve Premature Actuation Occurred & Failed to Reseat.Caused by Deficient Work Practices & Pesonnel Error.Maint Procedures Reviewed.Training conducted.W/891229 Ltr ML19354E1621989-12-18018 December 1989 LER 87-006-01:on 870120,4 H Fire Watch Patrol Detained by Radiation Chemistry Personnel Due to Not Signing Latest Radiation Work Permit & on 870131,did Not Start Route.Caused by Personnel Error.Personnel retrained.W/900110 Ltr ML20005D6801989-12-0808 December 1989 LER 89-007-00:on 891110,w/auxiliary Feedwater Pump 2B Pump Control Switch in Pull Out Per Stated Reasons,Automatic Initiation of Pump Sys Unavailable for 6 Minutes.Caused by Procedural Deficiency.Keys to Be Color coded.W/891208 Ltr ML19332E6261989-12-0202 December 1989 LER 89-015-00:on 891020,sample Canisters for Auxiliary Bldg Vent Stack Radiation Monitor Removed & Not Analyzed within 48 H.Caused by Programmatic Deficiencies & Personnel Error. Procedures & Training Programs revised.W/891204 Ltr ML19332E5121989-11-29029 November 1989 LER 89-014-00:on 891030,inadvertent Safety Injection Occurred on Train B During Installation of Card Holders. Caused by Personnel Error Design Deficiency.Sys Mod Request submitted.W/891129 Ltr ML19332E6411989-11-22022 November 1989 LER 89-002-01:on 890416,main Steamline Low Pressure Reactor Trip,Safety Injection & Main Steamline Isolation Occurred. Caused by Mgt & Procedural Deficiencies.Formal Policy on Use of Extra Operator During Startup developed.W/891129 Ltr ML19332C5681989-11-17017 November 1989 LER 89-006-00:on 890314,nonlicensed Operator Placed Eductor 2B Spray Additive Tank Suction Throttle Valve 2CS021B in Locked Open Position.Caused by Incorrect Valve Labeling. Valves to Be Provided W/High Visibility labels.W/891117 Ltr ML19327C2591989-11-15015 November 1989 LER 89-012-00:on 891016,momentary Loss of Power to Fuel Handling Bldg (Fhb) Area Radiation Monitor Caused Fhb Charcoal Booster Fan to Auto Start.Caused by Personnel Error.Fan Secured & Isolation Signal reset.W/891114 Ltr ML19354D4711989-11-0303 November 1989 LER 89-013-00:on 891005,discrepancy W/Design of Steam Generator Blowdown Sys Identified,Minimizing Auxiliary Feedwater Flow Requirements.Caused by Preservice Design Deficiency.Temporary Design Changes made.W/891103 Ltr ML19354D4721989-11-0101 November 1989 LER 89-005-00:on 891002,discovered That Tech Spec Action Statement Was Not Entered When safety-related Bus Was Removed from Svc.Caused by Procedural deficiency.Out-of-svc Procedure Will Be revised.W/891101 Ltr ML19325D5191989-10-20020 October 1989 LER 89-011-00:on 890920,high Head Safety Injection Valve 1SI8801A Not Capable of Being Powered by Operable Emergency Power Source.Caused by Diesel Generator 1A Being Out of Svc. Policy Statement Issued & Program revised.W/891020 Ltr ML19325D4851989-10-13013 October 1989 LER 89-010-00:on 890915,measured Leakrate of Hydrogen Analyzer Containment Isolation Valve Was Larger W/Valve Indicating Closed.Caused by Incorrect Labeling of Coil Leads.Valve Replaced W/Different Model valve.W/891012 Ltr ML19325C2851989-10-0303 October 1989 LER 89-004-00:on 890907,reactor Trip Occurred as Result of Lightning Induced Voltage Transient Affecting Rod Control Sys.Caused by Lightning Striking Containment.Rod Control Sys Devices reset.W/891006 Ltr 1994-05-05
[Table view] Category:RO)
MONTHYEARML20029D6301994-05-0505 May 1994 LER 94-003-00:on 940405,reactor Tripped Due to Main Power Transformer Failure.Corrective Actions:Detailed Investigation Performed for Collateral Damage & Isophase Bus Cleaned & inspected.W/940505 Ltr ML20029D2351994-04-29029 April 1994 LER 94-006-00:on 940330,discovered That Braidwood Cooling Lake Hydrographic Survey Was Not Completed within Required Time.Cause Was Personnel Error.Corrective Action: Surveillance Was Completed within 24 hours.W/940429 Ltr ML20029D6121994-04-29029 April 1994 LER 94-002-00:on 940331,discovered 2A Auxiliary Feedwater Pump Auto Starting.Caused by Procedural Deficiency. Auxiliary Feedwater Pump 2A Secured by Placing Control Switch in Pull Out position.W/940429 Ltr ML20046D5971993-08-19019 August 1993 LER 93-005-00:on 930720,missed Surveillance on Containment Isolation Valve Occurred Due to Personnel Error & Mgt Deficiency.Enhanced Procedures,Training & Counseling. W/930819 Ltr ML20044F5531993-05-19019 May 1993 LER 93-003-00:on 930419,TS Violated Due to Source Range Reactor Trip Capability Being Blocked.Caused by Personnel Error & Procedural Deficiency.Individuals Involved Counseled & Procedure developed.W/930518 Ltr ML20044D2071993-05-14014 May 1993 LER 93-002-00:on 930414,unplanned ESF Actuation Occurred When All Four SI Accumulator Isolation Valves Closed & Accumulator Pressure Reduced.Caused by Mgt Deficiency. Training Will Be conducted.W/930514 Ltr ML20024G7411991-04-24024 April 1991 LER 91-005-00:on 910326,main Control Room Ventilation Sys Shifted to Emergency Mode of Operation Due to Momentary Fluctuation in Voltage Available to Monitor.Lightning Protection Sys Being modified.W/910424 Ltr ML20028H8631991-01-24024 January 1991 LER 90-023-00:on 901230,generator Neutral Ground Overcurrent Protective Relay Actuated & Tripped Main Generator.Caused by Internal Generator Defect.Main Generator Disassembled & Rotor Removed to Locate ground.W/910124 Ltr ML20028G9151990-09-24024 September 1990 LER 90-015-00:on 900827,auxiliary Bldg Vent Stack Grab Sample Missed.Caused by Personnel Error & Deficient Work Practices.Training Provided,Program Modified & Station Reviewing Nonroutine Surveillance process.W/900924 Ltr ML20043H4071990-06-20020 June 1990 LER 90-007-00:on 900523,pressurizer Pressure Channel 458 Failed Low & Channel 455 Deviated in Excess of Remaining Two Channels.Caused by Defective Wire on Internal Portion of Pressure Transmitter.Transmitter replaced.W/900621 Ltr ML20043G6051990-06-14014 June 1990 LER 90-008-00:on 900517,unit at Power Permissive Circuit Actuated on Train a of Solid State Protection Sys.Caused by Procedural Deficiency in That Switch Rotation Not Specified. Procedure revised.W/900614 Ltr ML20043A6571990-05-16016 May 1990 LER 90-006-00:on 891204 & 900416,diesel Generator 1B Experienced Slow Start.Caused by Crisscrossed Starting Airlines for Cylinders 6L & 9L.Starting Airlines Reconnected & Verified to correct.W/900516 Ltr ML20043A6611990-05-14014 May 1990 LER 90-004-00:on 900416,diesel Generator 2A Speed Oscillated Prior to Maint Teardown.Caused by Component Failure.Resistors Replaced & Placed on 3-yr Replacement frequency.W/900516 Ltr ML20042G7041990-05-11011 May 1990 LER 90-005-00:on 900413,determined That Pressures for MSIVs a & D Were Outside Acceptance Criteria of Procedure.Caused by Procedural Deficiencies.Procedures Being Revised to Reflect Values of 4,800 Psig to 6,000 psig.W/900511 Ltr ML20042F5441990-05-0404 May 1990 LER 90-003-00:on 900405,inadvertent Train B Safety Injection Initiation Signal Occurred Due to Programmatic Deficiency. Training Developed & Lens Evaluated for Replacement. W/900503 Ltr ML20006E4811990-02-0909 February 1990 LER 90-002-03:on 900119,discovered That Flanges Not Added to Procedure 1BwOS, Primary Containment Integrity Verification of Outside Containment Isolation Devices. Caused by Program Weakness.Training held.W/900216 Ltr ML20006E4041990-02-0202 February 1990 LER 90-001-00:on 900112,reactor Tripped During Dc Ground Isolation Activities When Auxiliary Relay Energized,Causing Turbine Governor & Reheat Interceptor Valves to Close.Caused by Increasing Steam Pressure.Valves closed.W/900206 Ltr ML19354E0141990-01-22022 January 1990 LER 89-020-00:on 891223,failure to Verify Safety Injection Accumulator Boron Concentration within Specified Time.Caused by Programmatic Deficiency.Procedure Revised to Include Action Requirement sheet.W/900122 Ltr ML19354E0131990-01-16016 January 1990 LER 89-008-00:on 891228,equipment Attendant Discovered Refueling Water Storage Tank Vent Line Temp Less than 35 F. Caused by Preservice Deficiency.Storage Tank Vent Path Temp Verified at 36 F.W/900119 Ltr ML20006B2081990-01-12012 January 1990 LER 89-019-00:on 891219,discovered That Procedure Did Not Adequately Test Response Times for High Steamline Pressure Rate Steamline Isolation Signal.Caused by Deficient Procedure.Procedures Re Response Time revised.W/900112 Ltr ML20005F9611990-01-0808 January 1990 LER 89-017-00:on 891206,gas Detector Channel of Process Radiation Monitor Experienced Spike,Resulting in Alert Alarm.On 891210,spike on Channel Resulted in High Radiation Alarm.Caused by Failed detector.W/900109 Ltr ML20005E8561990-01-0202 January 1990 LER 89-018-00:on 891215,as Lead on volt-ohm Meter Landed, Containment Bldg Fuel Handling Incident Area Radiation Monitor Went Into Alert Alarm & Interlock Actuation.Caused by Procedure Deficiency.Signal reset.W/900102 Ltr ML20005E7851989-12-29029 December 1989 LER 89-016-00:on 891201,RHR Pump Suction Relief Valve Premature Actuation Occurred & Failed to Reseat.Caused by Deficient Work Practices & Pesonnel Error.Maint Procedures Reviewed.Training conducted.W/891229 Ltr ML19354E1621989-12-18018 December 1989 LER 87-006-01:on 870120,4 H Fire Watch Patrol Detained by Radiation Chemistry Personnel Due to Not Signing Latest Radiation Work Permit & on 870131,did Not Start Route.Caused by Personnel Error.Personnel retrained.W/900110 Ltr ML20005D6801989-12-0808 December 1989 LER 89-007-00:on 891110,w/auxiliary Feedwater Pump 2B Pump Control Switch in Pull Out Per Stated Reasons,Automatic Initiation of Pump Sys Unavailable for 6 Minutes.Caused by Procedural Deficiency.Keys to Be Color coded.W/891208 Ltr ML19332E6261989-12-0202 December 1989 LER 89-015-00:on 891020,sample Canisters for Auxiliary Bldg Vent Stack Radiation Monitor Removed & Not Analyzed within 48 H.Caused by Programmatic Deficiencies & Personnel Error. Procedures & Training Programs revised.W/891204 Ltr ML19332E5121989-11-29029 November 1989 LER 89-014-00:on 891030,inadvertent Safety Injection Occurred on Train B During Installation of Card Holders. Caused by Personnel Error Design Deficiency.Sys Mod Request submitted.W/891129 Ltr ML19332E6411989-11-22022 November 1989 LER 89-002-01:on 890416,main Steamline Low Pressure Reactor Trip,Safety Injection & Main Steamline Isolation Occurred. Caused by Mgt & Procedural Deficiencies.Formal Policy on Use of Extra Operator During Startup developed.W/891129 Ltr ML19332C5681989-11-17017 November 1989 LER 89-006-00:on 890314,nonlicensed Operator Placed Eductor 2B Spray Additive Tank Suction Throttle Valve 2CS021B in Locked Open Position.Caused by Incorrect Valve Labeling. Valves to Be Provided W/High Visibility labels.W/891117 Ltr ML19327C2591989-11-15015 November 1989 LER 89-012-00:on 891016,momentary Loss of Power to Fuel Handling Bldg (Fhb) Area Radiation Monitor Caused Fhb Charcoal Booster Fan to Auto Start.Caused by Personnel Error.Fan Secured & Isolation Signal reset.W/891114 Ltr ML19354D4711989-11-0303 November 1989 LER 89-013-00:on 891005,discrepancy W/Design of Steam Generator Blowdown Sys Identified,Minimizing Auxiliary Feedwater Flow Requirements.Caused by Preservice Design Deficiency.Temporary Design Changes made.W/891103 Ltr ML19354D4721989-11-0101 November 1989 LER 89-005-00:on 891002,discovered That Tech Spec Action Statement Was Not Entered When safety-related Bus Was Removed from Svc.Caused by Procedural deficiency.Out-of-svc Procedure Will Be revised.W/891101 Ltr ML19325D5191989-10-20020 October 1989 LER 89-011-00:on 890920,high Head Safety Injection Valve 1SI8801A Not Capable of Being Powered by Operable Emergency Power Source.Caused by Diesel Generator 1A Being Out of Svc. Policy Statement Issued & Program revised.W/891020 Ltr ML19325D4851989-10-13013 October 1989 LER 89-010-00:on 890915,measured Leakrate of Hydrogen Analyzer Containment Isolation Valve Was Larger W/Valve Indicating Closed.Caused by Incorrect Labeling of Coil Leads.Valve Replaced W/Different Model valve.W/891012 Ltr ML19325C2851989-10-0303 October 1989 LER 89-004-00:on 890907,reactor Trip Occurred as Result of Lightning Induced Voltage Transient Affecting Rod Control Sys.Caused by Lightning Striking Containment.Rod Control Sys Devices reset.W/891006 Ltr 1994-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
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T Commonwealth ECoon Braidwood Nucizir Powst St: tion
- 'o Route #1. Box 04 Braceville, Illinois 60407 Telephone 81$/458 2801 May 16,1990 BW/90-0525 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Dear Sir:
The enclosed Licensee Event Report from Braldwood Generating Station is being transmitted to you in accordance with the requirements of 10CFR50.73(a)(2)(v) which requires a 30-day written report.
This report is number 90-004-00; Docket No. 50-457.
Very truly yours, rd )
R. E. Querlo Station Manager Braidwood Nuclear Station .
REQ /JDW/jfe (7126z)
Enclosure:
Licensee Event Report No. 90-004-00 cc: NRC Region 111 Administrator NRC Resident inspector INPO Record Center CECO Distribution List p
. unammr s #. !
DEVIATION REPORT DVR NO.
_ $1A UNIT YEAR NO. Form Rev 2.0.
PARLLl T11LE OF DEVIATION OCCURRED 2A DG Erratic Operation AU
_ . . DAIL Tl!4E
$Y$1EM AlllCIED PLANT STATUS AT llML OF EVEN1 TESTING 2A DG H0DE 6 POWER (%) D WORK REQUE$T NO. l1l l l DESCRIPTION OF EVENT At 0315 the 2A DG was **.arted for a four hour run prior to a maintenance teardown. At 0316 the 2A DG began to oscillate from 300-600 RPMs after reaching rated speed and voltage. The 2A DG was then shutdown. When the 2A DG was shutdown no cooldown cycle occurred. Tech $taff was called out to investigate.
P01LN11 ALLY $1GNIFICANT EVENT PER N$D DIRECTIVE A-07 YES N0 I I LL_l 10CFR50.72 NRC RED PHONE l l
""J lNO _,gt$H.ppt J. ProsPuo O M 6/90 N0ilflCAT10N HADE l. X l fly l
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DATE
_teRI_Ll OPERATING ENGINEER'S COMMENTS Unit was in Mode 6 - Diesel was not being considered operable for Emergency Doron injection, machine was being run to take Hot Web Deflection measurements just prior to being taken 00$ for 18 month overhaul.
NON REPORTADLE EVENT 30 DAY REPORTABLE /10CFR5L131til211xL REGION !!! DATE TIME l _L_I l
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$TATION MANAGER DATE 86-5176 (form 15-52-1) 11-20-0$
30112(051090)/1
LICENSEE EVENT REPORT (LER) p g
((cilityName(1) Docket Number (2) _fagtJ3)
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93 50.73(a)(?)(iv) 6 _ 20.402(b) _ 20.a05(c) _ __ 73.7)(b)
POWER ___ 20.405(a)(1)(1) .___ 50.36(c)(1) 2. 50.73(a)(2)(v) __._ 73.71(c)
LEVEL .__ 20.405(a)(1)(ti) __ 50.36(c)(2) __._ 50.73(a)(2)(vil) __ Other (Specify LID L . _ _0 !0_!0 _ 20.405(a)(1)(itt) __ 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) in Abstract '
////////////////////////// __ 20.405(a)(1)(iv) ___. 50.73(a)(2)(ii) _ 50.73(a)(2)(viii){B) below and in
////////////////////////// _ _ 20.405(a)(1)(v) _ _ 50.73(a)(2)(iii) _ 50.73(a)(2)(x) Text)
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At 0315 on April 16,1990 the 2A Diesel Generator (DG) was started to perform a four hour warm up run. The DG started normally and achieved rated t+eed of 600 RPM.' Shortly after startup the DG speed began oscillating between 300 and 600 RPM. The 2A DG was immediately shut down. At 0913 it was identified that the cause of the speed oscillations was a f ailure of one of the dropping resistors in the Governor Unit. The resistor was replaced. This resistor had failed on the IB DG several weeks earlier. Byron Station, which has four DGs that are identical to Braidwood DGs, had experienced a f ailure of. this resistor also. At 1607 the 2A DG was started for a maintenance test. DG speed remained constant at 600 RPM. At 1653 the 2A DG was started for its monthly operability run.' The DG had successfully completed the test. DG speed had remained constant at 600 RPM - At 2118 the 2A DG was de'lared c operable. The root cause of the event was component:
failure. The resistor in the governor power-dropping resistor board f ailed creating an open circuit. An evaluation of the f ailure mode of the resistor was conducted. it has been concluded that the cause was simple long term heat fatigue. The resistors have been replaced on all DGs at the' station. and placed on a thrse year replacement f requency. The resistor is being evaluated for 10CFR part 21 applicability.
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4 3011m(051090)/2
, LICENSEE EV[1l1 REPORT (LER) TEXT CONTINUATION Fore Rev 2.L FACILITY NAME,(1). DOCKET NUMBER (2) LER NUMBER (6) Page (3) ,
Year /// Sequential /// Revision r ff
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_0IoI4 - 0Io oL2 _ Or - 01 3 1 EXT Energy Industey Identification System (E!!$) codes are identified la the text as (XX)
A. PLANT CONDITIONS PRIOR TO EVENT:
Unit: Braidwood 2: Event Date: 04/16/90; Event T'**: 0315; Mode: 6 - Refueling; Rx Power: 0%; <
RC$ (AD) Temperature / Pressure: Ambient / Atmospheric ;
D. DESCRIPi!ON OF EVENT: .
Th;re were no systems or components inoperable at the beginning of the event which contributed to the severity of thz event. -
At 0315 on April 16,1990 the 2A Diesel Generator (DG) (D;) was started to perfonn a four hour warm up run in preparation for its scheduled 18 month maintenance inspection. The 2A DG started normally and achieved rated '
speed of 600 RPH and normal voltage of about 4.16 KV. Shortly af ter startup the 2A DG speed began oscillating - i between 300 and 600 RPH. The 2A DG was immediately shut down.
t At 0913 it was identified that the cause of the speed oscillations was a failure of one of the dropping resistors in the Governor Unit. The resistor was replaced. The equivalent resistor on the IB DG had failed several weeks earlier during maintenance. Byron Station, which has four DGs that are identical to Braidwood's DGs, had I cxperienced a failure of this resistor also. This event was screened for reportability. Based on the failures superienced at Braidwood and Byron it was determined that a four hour non-emergency report was appropriate pursuant to 10CFR50.72(b)(2)(iii)(A).
Th) appropriate NRC notification via the LNS phone system was made at 1220.
At 1607 the EA DG was started for a maintenance test. The DG successfully completed the test DG Speed remained constant et 600 RPH.
At 1615 the 2A DG was shut down.
At 1653 the 2A DG was started for its monthly operability run.
! +
At 1819 the 2A DG was shut down. The D6 had successfully completed the test. DG speed remained constant at 600 RPH. ,
t At 2118, f ollowing the completion of the reviews of the test run data and the work package, the 2A DG was declared cperable.
This event is belng reported pursuant 'to 10CFR50.73(a)(2)(v)(A)-any event or condition that alone could have i prevented the fulfillment of the safety function of structures or systems that are needed to shutdown the reactor
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TEKT Energy Industry Identification System (E!!$) codes are identified in the text as (XX) l' C. CAU$E OF EVENT:
L.
The root cause of the event was component failure. The resistor in the governor power-dropping resistor board failed open. The f ailed resistor is one of 2 resistors in parallel on the positive lead of the governor's DC power supply. With one of the resistors f ailed, creating an open circuit, the voltage drop ceross the remaining resistor increased resulting in insufficient power supply to the governor. An evaluation of the f ailure mode of the resistor was conducted by $ argent and Lundy Engineers. Based on the r:sults of this evaluation it has been concluded that the cause was simple long term heat fatigue.
D. $AFETY ANALY$l$:
This event had no effect on the safety of.the plant or the public. . The 2B DG was operqble and available throughout the event. Only 1 DG is required in Mode 6.
Under the worst-case conditions of this f ailure occurring af ter a ' valid initiating signal following a Saf ety.
Injection there would still be no effect. The redundancy of the safety system design provides for full Saf t shutdown capability f rom a single ESF bus. The diversity of the electrical distribution system provides for powering an ESF bus from its System Auxiliary Transformer, its own Diesel Generator, or its corresponding '
nprosite Unit ESF bus which is capable of being powered from its Diesel Generator or System Auxiliary Transformer. This is enveloped in section 8 of the Updated final- Safety Analysis Report.
'E. CORRECTIVE ACTIONS:
Both power dropping resistors in the 2A, IA and 18'0G were replaced. These resistors had been replaced on April 4, 1990 for the 2B DG.
r These resistors have been placed on a replacement f requency of three years in accordance with the recopenendations of the Engineering evaluation.
l l The resistor is being evaluated for 10CFR part 21 appitcability. This action is being tracked to completion by action item 457-200-90-01001.
-F. PREVIOU$ OCCURRENCES:
There have been no previous similar reported occurrences at Draidwood Station.
G. COMPONENT fAltURE DATA:
Manufacturer Nomenclature Model Number / MFG part. Number
' pacific Resistor 100CH300 ohm 70wattresisthr l
Note: This item supplied as part of the Woodward Governor Model 2301.
3011:(0$1090)/4