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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
[Table view] |
Text
C lC Commonwealth Edis:n Co.
~
- Braidwood Station
- ,, _' ' R R 1. Box 81
' Braceville. IL 60407 Telephone 815/458-2801 December 8,1989 BW/89-3151 U. S. Nuclear Regulatory Commission
- Document Control Desk Washington, D.C. 20555
Dear Sir:
The enclosed Licensee Event Report from Braidwood Generating Station is being transmitted to you in accordance with the requirements of 10CFR50.73(a)(2)(1) & (v) which requires a 30-day written report.
This report is number 89-007-00; Docket No. 50-457.
Very truly yours, NE R. E. Querlo Station Manager Braidwood Nuclear Station i~
REQ /JDW/sjs (7126z)
Enclosure:
Licensee Event Report No. 89-007-00 l
cc: NRC Region III Administrator NRC Resident Inspector INPO Record Center CECO Distribution List 1 :.
l -
8912140109 891208 PDR ADOCK 05000457 S PDC
$db ;
) \
l
LICENSEE EVENT REPORT (LER) f arm Rev 2.0 Facill*ty Name (1) Decket Number (2) Pane (3)
JEAldwp9d1 el sl3LOI 01 di3L7 i Ierl0ls iltle (4) Dual Train Inoperability of Auxiliary feedwater System for Six Minutes Due to Procedural Deficiency Event Date (5) LER Nimber (6) Recort Date (7) Other Faellities Involved (8)
Month Day Year Year / Sequential
/jfj/ / Revision Month Day Year Facility Names _Qgdet Naber(s)
/// Nimber //jj/
f
// Number NONE 01 51 01 01.01 l l
- ~
11 1 11 0 81 9 81 9 01017 010 .1_ .L2 01 8 81 9 01s1010101 l- 1 p
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREENTS OF 10CFR (Check one or more of the followino) (11) 1 20.402(b) _ 20.405(c) _ 50.73(a)(2)(iv) _ 73.71(b)
POWER _ 20.405(a)(1)(1) _ 50.36(c)(1) .JL 50.73(e)(2)(v) _ 73.71(c)
LEVEL 20.405(a)(1)(ll) 50.36(c)(2) 50.73(a)(2)(vil) Other (Specify l9 l8 (101 0 __. 20.405(a)(1)(ill) J_ 50.73(a)(2)(1) _ 50.73(a)(2)(viii)(A) in Abstract f' /////////////N/////,/,///// _ 20.405(a)(1)(iv) _ 50.73(a)(2)(ll) _ 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)
LICENSEE CONTACT FOR THIS LER (12)
Name TELEPHONE NU>BER !
AREA CODE Phli Lw. HPES Coordinaler Ext. 2957 8l115 41 51 Bl -l 21 81 01 COMPLETE ONE LINE FOR EACH COMPON N FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- REPORIABLE TURER TO NPRDL TURER TO NPRDS I I I I l l l N l l l l l l l l l l_1 1 1 1 I I I I i 1 -l SUPPLEMENTAL REPORT EXPECTED (14) Expected Month l Day l Year i Submission lyes (If yndomphte EXPECTED SUBMISSION DATE) X l NO l l ll l ABSTRACT (Limit to 1400 spaces, i.e approximately fif teen single-space typewritten lines) (16)
On November 10, 1989 an Instrument Technician (INT) was recalibrating instrument loops for 2A and 28 F
Auxiliary Feedwater Pumps (AF) in accordance with Setpoint/ Scaling Change Requests ($$CR). The calibration l 1s procedurally directed by an Instrument Surveillance that provides for the calibration of both loops. As a {
prerequisite the 2A pump control switch was placed in the ' pull out' position. At 1738 the IMT completed the A loop. At 1927 the pump control switch was returned to the 'after trip' position and the pump was declared trperable. At 2049 the 2B pump control switch was placed in the ' pull out' position. The IMT went to the ,
cabinet where he had been working earlier. At 2137 the IMT placed the A loop in the test. The Reactor Operator identified that the IMT was on the wrong loop. At 2143 the IMT returned the loop to normal. It was discovered during event investigation that by placing the A instrument loop in test the 2A AF pump would have received a trip signal af ter 2.5 seconds of operation. With the 28 AF pump control switch in ' pull out',
automatic initiation of the AF system was unavailable for 6 minutes. The root cause was a procedural deficiency. A contributing cause was the f ailure of the IMT to verify the cabinet. Each AF loop will have a separate procedure. Surveillance cover sheets and cabinet keys will be color coded to match the cabinet doors. Previous corrective actions are not applicable.
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2947.x(121189)/2 i
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W:
- LIrrmtr EVENT rep 0RT fLER) TEXT tinffitRETION _ Fore Rev 2;d
-FACILift NAE (1) - DOCKET ltfpSER (2) lea laseER (6) Pane (3) l Year // Sequential //j/j Revision
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/// Nimber-sra'id nod 2 o I 5 1 0 I o I o I di 51 7 aI9 - oIo17 - 0l0 01 2 or ol s TEXT Energy Industry Identification System (EIIS) codes are identified in the text as (XX)
A. PLANT C00GITIONS PRIOR TO EVENT:
- Uni t : Braidwood 2, Event Date: November 10,'1989; Event Time: 2137; l
Node: .1 - Power Operation; Rx Power: 98%;
RCS (A8) Temperature / Pressure: NOT/NDP;
8.1 DESCRIPTION
OF EVENT:, 1
-l There were no systems or components inoperable at the beginning of the event which contributed to the, severity of' the event,'
. During the af ternoon on Novembe.* 10, 1989 an Instrument Maintenance Technician (IMT) (Non-Licensed instrunent-mechanic) was recalibrating the s. tlon pressure transmitters for the 2A and 28 Auxilialy feedwater Pumps .(AF) -)
l (BA) to new values. The instrument loops were designated as 2PSL-AF051 for the 2A AF pwap and 2PSL-AF055 for the.
28 AF pump ~ This change was in accordance with Setpoint/ Scaling Change Requests (SSCR)89-239 and 89-240 l< rsspectively. The calibration of the AF pump suction pressure transmitters is procedurally directed by Sw!S l' 3.2.1 204, an Instrument Surveillance that provides step by step direction for the calibration of both 2PSL-AF051' cnd 2PSL-AF055. The IMT was using this procedure.
f L -.
' As a prerequisite to performing this procedure the 2A AF purp was declared inoperable and the appropriate ;
Technical Specification Action Statements vers entered and cceplied with. The motor operated AF suction ~ valves ;
l- from the Essential Service Water iSX) (BI) System for the 2A AF pump were removed from service. This was to i
- prevent inadvertent opening during the performance of the calibrations. The. pump control switch was also placed l(
in the ' pull out' positien.
At 1738 the INT completed the recalibration of instrument loop 2PSL-AF051. The IMT notified the Shift Control-
- Room Engineer ($CRE) (SRO licensed supervisor) that the recalibration was completed. The SCRE initiated action to return the 2A AF pump to operable status. The SCRE was not familiar with the additional procedural requirements cssociated with an SSCR. As a result the SCRE handled the returning of the 2A AF pump to operable in the usual ,;
[
manner for a routine calibration. '
)
[ ' At 1927, the return to service of the AF pump suction valves was completed and the pump control switch was returned to the 'after trip' position. The 2A AF pump was declared operable and the Technical Specification
{
, Act ba Statement was exited. :
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At 1049 the 28 AF pump was declared inoperable. The applicable Technical Specification action statements were
- i; .gntered and compiled with. This was part of the preparation to perform the second half of the Bw!S 3.2.1-204, the calibration of the 2PSL-AF055 instrument loop. The suction valves for the 28 AF pump were removed from service tnd the control switch was placed in the ' pull out' position.
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Form Rev 2;8 LICrutrr EVENT REPORT (LER) TEXT CONTIIRIATION 1ACILIT'E NAE (1) DOCKET SU SER (2) LER 1R4SER (6) Pace (3)
Year // Sequtatial /j/j
/ Revision
/j/j/j
/ Number f
/// Number
,graggggd 2 0 l 5101010141517 8l9 - 010l7 - 010 01 3 0F 01.5 TEXT Energy Industry Identification System (E!!S) codes are identified in the text as (XX) l 1
B. DESCRIPTION OF EVENT: (cont'd)
At 2134 the IMT continued with Bwls 3.2.1-204. He proceeded to the Unit 2 Auxilf ary Electric Equipment Kuom {
and established direct communication with the Unit 2 Nuclear Station Operator thS0) (R0 licensed operator). ]
The IMT went to the cabinet where he had been working earlier, the 2PA33J. j i
At 2137 the IMT placed the instrument loop he had been working on earlier, the 2PSL-AF051, in test. The NSO {
questioned the INT to determine if he was on the correct loop. Indication had been lost for the 2A AF pump L suction pressure instead of the 28. The IMT recognized the error and informed the NSO that he was returning the instrument loop to normal. t i'
At 2143 the 2PSL-AF051 instrument loop was returned to normal. The loop had been in test for six minutes.
The event was screened for reportability. It was determined that a 10CFR50.72 ENS notification was not required. The IMT continued with the recalibration. a At 0854 on November 11, 1989 Bw!S 3.2.1-204 was completed.
i At 1535 a Shif t Foreman (SF) (SRO licensed supervisor) was reviewing the status of $$CR 89-240 for the i 2PSL-AF055 instrument loop. The SF discovered that SSCR 89-239 and its associated Nuclear Work request for -f 2PSL-AF051 did not have final completion signof f signatures. The 2A AF pump was conservatively declared inoperable. Limiting Condition for Operation (LCO) 3.0.3 was entered and complied with. The appropriate l;
pe-sonnel to complete the review of $$CR 89-239 were notified.
1 At 1647 the review of $$CR 89-239 was completed and found to be satisfactory. The 2A AF pump was declared ')
i l operable. LCO 3.0.3 was exited.
I j . At 1716 the return to service of the AF pump suction valves for the 2B AF pump had been completed. The pump l control switch had been returned to the 'af ter trip' position. The review of $$CR 89-240 for instrument loop .!
lL 2PSL-AF055 was completed and found to be satisfactory. The 28 AF pump was declared operable, and the l
Technical Specification Action Statement was exited.
l l During the day shift on November 13, 1989 an investigation of this event was conducted by station personnel.
Based on the results of this investigation the following was concluded:
- 1. Declaring the 2A AF pump operable prior to the completion review of SSCR 89-239 was a deviation from l
i station policy. Based on the fact that the work for SSCR 89-239 was satisfactorily performed and ,
completed the conservative declaration of inoperability of the 2A AF pump and entry into LC0 3.0.3 at !
- ! 1535 on November 11, 1989 was unnecessary. f i
!i 2. At 1406 it was discovered that by placing, the 2PSL-AF051 instrument loop in the test position the 2A AF l{ pump would have recelted a trip signal after 2.5 seconds of operation. As a result automatic initiation of the AF system was unavailable during the 6 minutes from 2137 to 2143 on November 10, 1989 when this 4 loop was in test with the 2B AF pump control switch in the ' pull out' position. This was determined to j be a reportable event pursuant to 10CFR50.72(b)(2)(iii).
The appropriate NRC notification via the ENS phone system was made at 1652 pursuant to 10CFR50.72(b)(2)(lii).
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29472(121189)/4
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- j. Year /// Sequential / Revision
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Jl0 ef 4 ot _ela TEKT Energy Industry Identification System (EII$) codes are tientified in the test as (KX) 9.- 9ESCRIPTION OF EVENT: (cont'd)
- This event is being reported pursuant to:
10Cf R50.73(a)(2)(l) - any opera *.4on or condition prohibited by the plants Technical $pecifications.
10CFR50.72(a)(2)(v) - any event or e ondition that alone could have prevented the fulfillment of the safety function of struttures or systems that are needed to mitigate the consequences of an accident.
Based on the initial informatiot. associated with this event a 'Braidwood $tation Error Evaluation presentation" was held to review this event with the personnel directly involved and their supervisor. 1he c rrective actions addressing both root and contributing causes are detailed below.
C. CAUSE OF EVENT:
s The root cause of this event was a procedural de(Iclency. The calibration of the pressure loops for both trains of AF is performed within the body of one procedure. Being in the same procedure for the performance
$f the calibration of 2P$t-AF055 loop created a mind set for the IMT. This mind set caused the IMI to focus cn returning to the panel he had been in for the first half of the procedure. As a result the IMT returned to the cabinet he had worked in earlier. This deficiency created the error.
A contributing cause to this event was the f ailure of the INT to verify that he was in the correct cabinet.
The cause for the $CRE declaring the 2A AF pump operable prior to the completion review of $$CR 89-239 was a Training deficiency. The SCRE was not familiar with the $$CR program as it related to making setpoint changes during regularly scheduled calibrations.
D. $AFE7Y ANALY$l$:
This event had no af fect on the safety of the plent or the public. Manual initiation of the 28 AF pump was cvailable throughout the event as well as the normal feedwater system (SJ).
Under the worst case condition of extended AF system unavailabilty during an accident scenario, the emergency procedures provide for either the estabitshment of feed te the $ team Generators (AB) from the normal i
fcedwater system or cooldown and depressurization of the RCS to a point where the Residual Heat Removal (BP)
. System can be placed in service using redundant ECC$ components, all of which were operable and available far this event.
E. CORRECTIVE ACTIONS:
The 2PSL-AF051 was immediately returned to operable status upon discovery of the error.
Based on the initial information associated with this event the personnel directly involved with this event l
participated in a "Braldwood Station Error Evaluation Presentation" to identify the root and contributing
! causes'of this event. Based on the conclusions of this presentation the following actions will be taken: '
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l 2947;(121189)/5
' '* LICINKLIYU(T_kEPORT (Ltti TERLCggI1l$gUtu _ rarm Rev 2.0 FA(JtTTE NAE (1) DOCKET Ast[R (2) _ LER _Itse[t 161 Pane _(31 Year g
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oIo17 oIo el s or el s i
.9tsidwand 0J_LLLI o I e l_iL1L2 sI9 - -
TEKi Energy Industry Identification System (E!!$) codes are identified in the text as [KX)
E. CORRECTIVE ACTION $: (cont'd)
Bw!$ 3.2.1-204 will be rewritten as two separate procedures. This action will be tracked to completion by cction item 457-200-89-09101.
The Instrument Surveilleare Data Package cover sheets will be color coded to match the color of the cabinet doors in the Aust11ery Electric Equipment Room which are already color coded. This will help ensure that IMT
! personnel enter the correct cabinets. This action will be tracked to completion by action ites ;
457-200-89-09102.
The 6eys of the cabinets will also be color coded to match the color of the cabinet doors in the Auxillary Electric Equipment Room which are already color coded. This action will be tracked to completion by action item 457-200-89-09103.
A training tailgate session will be conducted for appropriate Operating Department personnel detalling the r;quirements of the $$CR program. This action will be tracked to completion by action item 457-200-89-09104.
F. FREV1005 OCCURRENCES:
i There was a previous occurrence of performing actions on the opposite train.
DVR No. LER Ho. Title 20-1-88-019 456/88-002 Reactor Trip and Safety Injection Due to Cognitive personnel Error The corrective actions were Implemented addressing both root and contributing causes. Previous corrective actions are not applicable to this event.
'I j G. COMPONENT FAlt0RE DATA:
1 This event was not the result of component failure, nor did any components f all as a result of this event.
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1 2947;(121189)/6
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