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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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, Commonwe:lth Edison Braidwood Nucl2:r Powzr St: tion
' g. Route #1, Box 84 Braceville, Illinois 60407 Telephone 815/458-2801 May 16,1990 BW/90-0533 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)(1)(B) which requires a 30-<iay written report.
This report is number 90-006-00; Docket No. 50-456.
Very truly yours, I
. E. Querto Station Manager Braidwood Nuclear Station REQ /JDW/jfe (7126z)
Enclosure:
Licensee Event Report No. 90-006-00 cc: NRC Region 111 Administrator NRC Resident inspector INPO Record Center CECO Distribution List 9005220366 900536 '
PDR> ADOCK 05000436 6 PDC- -l j'
LITENSEE EVECT REPORT (LER)
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iltle (4') Diesel Generator Slow $ tert From Crisscrossed $ tarting Airlines Due to Programatic Deficiency
_htnt Date ($) LER Nymher (6) Rtport. Dale (7) Other Facilities invol_ vel 19)
Honth Day Year Year Sequential Revision
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OP(RATING H0DE (9) LIht1Lont_or_more of the follor.inal (111 6_ _ 20.402(b) _._ 20.40$(c) ___ 50.73(a)(2)(iv) ,_ 73,71(b) l'0WE R __ 20.405(a)(1)(1) _., 50.36(c)(1) _._ 50.73(a)(2)(v) __._ 73.7)(c)
LEVEL 20.405(a)(1)(ll)
__ __ 50.36(c)(2) __ 50.73(a)(2)(vil) ,_._ Other (Specify
_LlD1 -0 0.__gLD 20.405(a)(1)(lli) l_ 50.73(a)(2)(1)
__ __ 50.73(a)(2)(viii)(A) in Abstract
//////////////////////////, __ 20.405(a)(1)(iv) __ 50.73fe)(2)(li) __ 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)
LICIHSLLEQUIACLLOL1 HILLER _L121 Name TELEP,MQNE NUte[R AREA CODE allainteski. Itih $13.f f Ext. 2482 8l115 4151 Bl -l 2lJj_QL1 10MPLLILONLLINE FOR EACH CQMPONENT FAILVRLDLiCRIBLD_IM.It{ll. REPORT (13)
CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE CAU$E SYSTEM COMPONENT MANUFAC- rep 0RfABLE
_ lMRER _10_NERui. _IVELR _.10 HPRDS.
l- 1 JJJ._
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__1 J.J ! JJ _L I I I l- - - JI I SVEELib(MIALELPQRT EXPECILD (14) Expected Month.j_DALLltAt l Submission
"' Iil 11tLill JtL_10mpltiellf1ClLD_1VDML5510!LDATE1 _JLj_NO
- l ABSTRACT (Limit to 1400 spaces, i.e. approximately fif teen $1ngle-space typewritten lines) (16)
On November 4,1989 the IB Diesel Generator (DG) exhaust manifold was replaced. This replacement required-disconnection of the starting air distribution system tubing at couplings in a trough that routed the tubes to the individual cylinders. Af ter completion of the maintenance all testing was successfully completed and the DG was declared operable. On December 4,1989 during performance of the monthly operability test, the IB DG experienced a " slow start". Af ter completing troubleshooting several starts were performed with Occeptable start times. The 1B DG was declared operable and successfully completed the next 4 monthly tests. On April 16, 1990 the IB DG experienced a slow start again. During an investigation of the starting air distribution system it was discovered that the starting airlines for cylinders 6L and 9L were crisscrossed and that SL and BL were crisscrossed at the couplings in the trough. The cause of this event was a programatic deficiency. The time check performed was not capable of detecting an alrline crisscross.
The crossed air distributor lines were reconnected and vert fled to be correct. The starting airitnes on the remaining DGs will be checked. The DG maintenance procedures will be revised to require a steeting air system check if maintenance is performed on toe system. The effects on the IB DG will be evaluated. No previous occurrences. i
)
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3015m(051590)/l
. LICEN$[WNT REPORT (LLB) TEXT CQRIlNUATION fore Rev 2.0 FACIt!TY NAME (1) DOCKET NUMBER (2) _LilLMELILift) pane 01 s
.' Year g $equential
_Hupkgr g//
Revision ,
. 2R / Numben ar_ald eof 1 0 1 5 1 0 1 0 1 0 1 41 51 6 910_ - o1016 - oI o el 2 or el s TEXT Energy Industry identification System ([11$) codes are identified in the text as (xx)
,A. PLANT CONDITIONS PRIOR TO EVENT:
Unit: Braidwood it Event Date: November 4, 1989:
Mode: 6 Refueling: Rx power: 0%;
9 RC$ (AB) Temperature / Pressure: Ambient / Atmospheric .
B. DESCRIPTION Or EVENT!
On November 4,1989 the five year Haintenance inspection for the 18 Diesel Generator (DG) (EK) was completed. The exhaust manif old had been replaced as a part of this maintenance inspection. This replacement required . I disconnection of the starting air distribution system tubing at couplings in a trough that routed the tubes to the ,
individual cylinders.
- Af ter completion of the maintenance inspection all DG surveillance testing was successfully completed and the DG vas declared operable.
On December 4,1989 during performance of the monthly operability test, the 1B DG experienced a " slow start" of .
13.8 seconds to achieve rated speed and voltage. This was in excess of the 10 seconds specified in the Technical
$p;cifications. The IB DG was declared inoperable and the appropriate Technical $pecification Action $tatements were entered and complied with.
As part of the trouble shooting procedure an inspection of the fuel racks and fuel pumps was conducted._ An additional 4 olation valve was closed on an unused air receiver. This receiver had previously been isolated by a chick valve. During a test run of the DG it had been identified that the receiver had shown an increase in pr:ssure during the starting air cranking sequence. It was theorized that the check valve leakage had lowered the cir pressure in the starting air distribution system which had resulted in the slow start. Af ter completing these actions several test starts were perforined. The DG start times were below the limit and acceptable. The monthly
- l nparability test was successfully completed, i
l On December 6,1989 the IB DG was declared operable.
The IB DG'successfully completed the Monthly Operability tests conducted January 2. January 29, February 26, and March 26,1990 with start times acceptable and normal.
At 1124 on April 16.1990 the 1B DG was started as part of an unscheduled Operability test following' the discovery .
of a defective resistor on_the 2A DG gavernor control circuit (reference LER 50-457/90-004). The DG experienced a slow start of 12.8 seconds. The IB DG was declared inoperable. The appropriate Technical $pecification Action Statements were entered and complied with. Troubleshooting activities were initiated.
On April 17, 1990 during an extensive investigation of the starting air distribution system it was discovered that l' th3 starting airlines for cylinders 6L and 9L were crisscrossed and that SL and BL were crisscrossed. The crisscross occurred at airline coupilngs in a trough that routed the airlines f rom the starting air distributor to l the individual cylinders.
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LICEN_$EE EVENT REPORT (LER) TEXT CONTI M 110N fortLRtLLQ.
FACIllTY NAME (1) DOCKET NUMBER (2) LER NUff1lLM) Pagt 13)
.' Year // Sequential /// Revision
/j,/,
// Nutber /,/,/, Humber
_RyJ1dwppd 1 _Dl5101010_l_41516 910 - 01016 - 01 0 01 3 _OF 01_$
TEXT Energy Industry Identification System (C115) codes are identified in the text as [XX)
B. DESCRIPTION Of [ VENT: (cont'd)
The airline tubing was disassembled, reconnected, and each airline was individually time checked to insure c3rrect routing.
At 0903 on April 18, 1990 the IB DG was started for performance of its operability surveillance. The DG -
start time was noreel and acceptable.
At 1236 the IB DG was declared operable and the Technical Specification Action Statement was exited.
The $ystem Test Engineer conducted a preliminary evaluation of the ef fects of the crisscrossed airlines on the 10 DG starting air distribution system. 1he scope of this evaluation was limited to engine component position (i.e. admitting starting air during a compression stroke or with intake or exhaust valves open).
Random stopping position from a previous DG run was'also assumed. Internal mechanical forces were not considered. Based on the results of this evaluation it was identified that the IB DG would have experienced a 30% probability of a slower than normal start and a potential 1% probability of a no start. A graph dGlalling cylinder component position for the four af fected cylinders and starting air valve sequence for all 20 valves has been provided on the last page of this report.
This event is being reported pursuant to 10CfR50.73(a)(2)(i) - any operation or condition prohibited by the plant's Technical $pecifications.
C. CAUSE OF EVENT:
The root cause of this event was a programmatic deficiency. The existing programs for post maintenance testing provided for time checking of the starting air distribution system. This check was perforwed by vGrifying that the starting air valve on a select cylinder operated at the specified time as the flywheel rotated. This test is the standard industry practice for verifying correct timing of the starting air i distribution system but it is not capable of detecting an airline crisscross unless the crisscross occurs on .
! the specified cylinder. Having no program to test for this error created the event.
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l 3015m(051590)/4 l
LICIM51LIYulf REPORT f1LR) TEXT IILNTINuAf ton 7o
FACILITY NAME (1) 00CKti NUMBER (2) _ 1ULiq $((L{$1 page (3)
,. Year ///
ffj Sequential //j/ Revision ff
- fff J umber /// hm, tp r_
Jtilh9pd 1 0 l 5 I QMMj_4U1J 910 - 01016 - 01 0 01 4 0F_ _QJ_.$
itKT Energy Industry Identification System (t!!$) codes are identified in the test as [XX)
D. 5AfETV ANALY$l$:
This event had no effect on the safety of the plant or the public. The 1A DG was operable and evallable from November 4, 1990 thru April 18. 1990 except for a seven hour period during a cold wave on December 20, 1989 when the 1A DG was administrative 1y declared inoperable due to its lube oli temperature dipping below 100 degrees f. It was still evallable during that seven hour period.
Under the worst case conditions of a DG failure occurring af ter a valid initiating signal following a $afety injection there would still be no ef fect. The redundancy of the safety system design provides for full safe shutdown capability f rom a single t$F bus. The diversity of the electrical distribution system provides for powerint, p ($F bus f rom its $ystem Auxiliary Transformer, its own Diesel Generator, or its corresponding cpposite bnit ($r bus which is capable of being powered from its Diesel Generator or $ystem Auxiliary T r:ns f eriner. This is enveloped in section 8 of the Updated Final Safety Analysis report.
E. CORRECTIVE ACTIONS: ,
th) crossed air distributor lines were reconnected and verified to be correctly connected.
Th> starting air distribution systems on the remaining Braidwood $tation Diesel Generators will be checked.
l This action will be tracked to completion by action item 456-200-90-01901.
The Diesel Generator Haintenance procedure will be revised to require a starting air distribution system l check if maintenance is performed that requires disconnection of components in the starting air distribution systee. This action will be tracked to completion by action itee 456-200-90-01903.
I l F. PREVIOV$ OCCURRENCE $:
I l Thire have been no previous similar cccurrences.
G. COMPONENT FAltVRC DATA:
This event was not the result of component failure, nor did any components fall as a result of this event. ,
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3015m(051590)/5
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. LI[LIG[E EVENT. REPORT (LER) TEKT CONTINCATION Fore Rev 2.0 [
fACILIIY NAME (1) DOCKET NUMBER (2) 11!LtfMER.15) Pase (31 l 4
.' Year ///
ffj Sequential //j/ Revision f
- e. . UL_ tinhtr /jfR. _ HW!nb.tr._ !
_SIA.{dws.nd 1 0151010.10141.Sj_6 910 - 01016 . OI 0 01 5 0F 01 5 l
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