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| This report is number 89-008-00; Docket No. 50-457.- i | | This report is number 89-008-00; Docket No. 50-457.- i |
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| Very truly yours, l f R.Station E. Querl Manager. | | Very truly yours, l f R.Station E. Querl Manager. |
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| LICENSEE EVENT REPORT (LER) , g iccility home (1) Docket Number (2) Pane (1) , | | LICENSEE EVENT REPORT (LER) , g iccility home (1) Docket Number (2) Pane (1) , |
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| l2974m(011990)/3 | | l2974m(011990)/3 |
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| . LICEptrr EVDff REP 0kT (LERl TEXT EONTitamT1DN Fare kev'2.0 | | . LICEptrr EVDff REP 0kT (LERl TEXT EONTitamT1DN Fare kev'2.0 |
| ' FACILITY NAE (1) DOCKET NUSER (2) LER liteEt (6) Pane (3) | | ' FACILITY NAE (1) DOCKET NUSER (2) LER liteEt (6) Pane (3) |
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| ff /{f/ Revision f | | ff /{f/ Revision f |
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| /// % =her /// | | /// % =her /// |
| I eralse 2- O l's 1 0 1 0 1 0 1 41 El 7 aI9 - 010l8 - 0 l= 0 01 3 0F 01 4 { | | I eralse 2- O l's 1 0 1 0 1 0 1 41 El 7 aI9 - 010l8 - 0 l= 0 01 3 0F 01 4 { |
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| '. The RWST heater was placed in a " continual operation'' mode to raise RWST temperature which would provide . | | '. The RWST heater was placed in a " continual operation'' mode to raise RWST temperature which would provide . |
| L. additional heat to the vent line. | | L. additional heat to the vent line. |
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| l RWST Vent Path Temperature was monitored.twice per eight hour shif t until December 26, 1989 when outside air f | | l RWST Vent Path Temperature was monitored.twice per eight hour shif t until December 26, 1989 when outside air f |
| ' temperature was above 35 degrees F and RWST vent path temperature had been indicating above.48 degrees F for several days. ' | | ' temperature was above 35 degrees F and RWST vent path temperature had been indicating above.48 degrees F for several days. ' |
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| : 1. The EA rounds sheets will be revised to include an administrative limit for RWST Vent Path temperature. | | : 1. The EA rounds sheets will be revised to include an administrative limit for RWST Vent Path temperature. |
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| This limit will provide advance notification so corrective actions can be taken prior to reaching the Technical- Specification Limit. The rounds will also be revised to add a note on each page where readings are taken for Technical Specification requirements instructing the EA to immediately notify the Shift Supervisor of an out of tolerance Technical Specification reading. These actions will be tracked to completion by action item 457-200-89-09201. | | This limit will provide advance notification so corrective actions can be taken prior to reaching the Technical- Specification Limit. The rounds will also be revised to add a note on each page where readings are taken for Technical Specification requirements instructing the EA to immediately notify the Shift Supervisor of an out of tolerance Technical Specification reading. These actions will be tracked to completion by action item 457-200-89-09201. |
| : 2. An evaluation will be conducted to identify methods to increase the capability to heat the RW$T Vent ' | | : 2. An evaluation will be conducted to identify methods to increase the capability to heat the RW$T Vent ' |
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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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- 4 * ' ^ N) v Br:ld wood Nucirr PJw:t St;ti:n Rout 3 C1. Box 64 I
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Braceville. Illinois 60407 i Telephone 81$/458-2801 j
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January 19,1990 l BW/90-0078 4 i
I U. S. Nuclear Regulatory Commission [
Document Control Desk i Washington, D.C. 20555 !
Dear Sir:
l i The enclosed L!censea Event Report from Braidwood Generating ';
Station is being transmitted to you in accordance with the requirements of l 10CFR50.73(a)(2)(1) which requires a 30-day written report.
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This report is number 89-008-00; Docket No. 50-457.- i
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Very truly yours, l f R.Station E. Querl Manager.
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-l Braldwood Nuclear Station j
- REQ /JDW/jfe !
i (7126z) i
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Enclosure:
Licensee Event Report No. 89-008-00 l cc: NRC Region !!I Administrator
.fi NRC Resident Inspector !
INPO Record Center !
CECO Distribution List i i
'9001250205'900116 M I
PDR ADOCK 05000457 j S PDC
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LICENSEE EVENT REPORT (LER) , g iccility home (1) Docket Number (2) Pane (1) ,
traidwood 2 01 El 01 01 01 41 El 7 1lefl0l4 Title (4) Refueling Water Storage Tank Vent Line Temperatee Less Than 35 Degrees F Due to Preservice Deficiency-d vent Date (El LER Number (6) Recort Date (7) Other Facilities Involved (B)
Moeth Pay Year Year /// Sequential /j/j/ Revision Month Day Year Facility "s Docket % d er(s)
//j/j f
Jumber f
/// Number None 01 51 01 01 01 l l
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11'2 21 e el 9 Bl 9 010l8 01 0 0l1 11 6 91 0 01 El 01 01 01 l l THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10CFR OPER M (theek one or more of the followino) (11) 1 E0.402(b) _ 20.40$(c) __ 50.73(a)(2)(iv) ._ 73.7)(b)
POWER _ 20.405(a)(1)(1) _ 50.36(c)(1) _ 50.73(a)(2)(v) _ 73.71(c)
LEVEL 20.405(a)(1)(ii) __ 50.36(c)(2) __._ 50.73(a)(2)(vii) .__. Other (Specify (101 0..!. 9 ! 9- _ 20.405(a)(1)(lii) _1_ 50.72(a)(2)(i) ._ 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
///j///}/Q///j/////}/}/j/j////// / 20.405(alli)(v) ._._ 50.73(a)(2)(iii) _ 50.73(a)(2)(x) Text)
LICENSEE CONTACT FOR THIS LER (12)
Name TELEPHONE NutBER ,
AREA CODE C. Melone. Technical Staf f Ennineer Ext. 2440 8l115 41 El 81 l 21 81 01 COMPLETE ONE LINE FOR EAEH COMPON N FAILURE DESCRIBED IN THis REPORT (13)
CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS TURER TO NPRDS I I I I I I I I I I I I I l-1 I I I I I I I l l l l l 1 -
SUPPLEMENTAL REPORT EXPECTED (14) Expected Month l Day l Year Submission
_hti_i U_.yfidMRlt ti.E X PE CT E D SUI)MUi10!LD AT E ) X l NO l ll ll ABSTRACT (Limit to 1400 spaces, i.e, approximately fif teen single-space typewritten lines) (16)
Outside air temperatures had beer fit' i 0 degrees F for several days with nightly lows reaching -18 degrees F.
, During the Midnight Shif t on Deced e 7,1989 an Equipment Attendant = (EA) and an EA trainee performing Auxiliary j Building Rounds recordeti the Unit s Rs$ueling Water Storage Tank (RWST) vent line temperature as 34 degrees F.
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- This temperature was required to be >/-35 degrees F. The EA trainee telephoned this information to the Unit 2 Nuclear Station Operator (NS0) who entered it in the NSO rounds. The HSO did not identify the below minimum reading. The rounds were reviewed by several supervisors who did not identify the below minimum reading. At 1430 during a review of the rounds, the below minimum reading was discovered. An EA was imediately dispatched to check the temperature. It was 36 degrees F. The cause of this event was a preservice deficiency. The capacity of the electrical heat tracing was not adequate. The failure to identify the below limit reading was due to ptrsonnel error, absence of alann, and absence of an administrative temperature limit. The RWST heater was placed in continual operation. The EA rounds will be revised. Methods to increase vent line heating capability and provide for a low temperature alarm will be evaluated. Training will be conducted. A program will be developed to flag rounds with an out of tolerance reading. No previous occurrences.
2974m(011990)/2
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-b Liersarr tvtNT kEPORT (LEkl TEXT CONTItRRTION Form key 2.0
' FACILITY H M (1) DOCKET NUSER (2)-- Lta etmare (6) - Paon (M I Year fj/j/ Sequential /j/j/
/
f Revision ]
/// M r /// Number l
_traidwood 2 oIsIeIoIo 1 41 51 7 a19 - D1ol8 - 01 0 el 2 0F 01 4 TEXT- Energy Industry Identification System (Ells) codes are identified in the text as (XX)
,.A. IPLANT CONDITIONS PRIOR TO EVENT:
=i Unit: Braidwood 2; Event Date: December 22, 1989; Event Time: 1430 Mode: 1 - Power Operation; Rx Power: 99 2 ; i L ,
-RCS (AB) Temperature / Pressure: NOT/NOP i i
B. DESCR!pTION OF EVENT:
t .. . ..
- There were no systems or components inoperable at the beginning of the event which contributed to the severity of '
the event. = Outside air temperatures at the station had been below 0 degrees F for several days prior to the event with nightly lows reaching -18 degrees F.
During the Nidnight Shif t on December 22, 1989 an Equipment Attendant (EA)(Non-Licensed Operator) and an EA ,
trainee were performing Auxiliary Butiding Rounds for Unit 2. One of the locally indicating values recorded in .;
the rounds was the Refueling Water Storage Tank (RWST) (9Q/BR) vent line temperature. This temperature was-
- required to be verified >/s35 degrees F on a daily frequency when outside. air temperature was less than 35 degrees F. The EA trainee recorded the indicated value of 34 degrees F. ,
The RWST vent path temperature is required to be transferred to the Nuclear Station Operator (NS0) (Licensed Reactor Operator) rounds sheet. The EA trainee telephoned this-information to the Unit 1 N$0 who recorded it in the Unit 2 NSO rounds. The NSO failed to recognize that the entered value was below the 35 degree F minimum.
THE NSO rounds were reviewed by'the Station Control Room Engineer ($CRE) (Licensed Senior Reactor' Opera' tor) (SRO) I who did not identify the below minimum reading. The EA rounds were reviewed by the Unit 2 NSO and the Shift-Foreman ($RO Licensed $vparvisor) who also did not identify the below minimum reading.
l- - At 1430 during the review of the Unit 2 NSO rounds, the day shif t SCRE discovered that the RWST vent path temperature was recorded as being one degree below the minimum value. An EA was issnediately dispatched to check the Unit 2 RWST vent path Temperature. The temperature was 36 degrees F. ,
This event is being reported pursuant to 10CFR50.73(a)(2)(1) - any operation or condition, prohibited by the plant's Technical $pecifications.
Bassd on the initial information associated with this event, a "Braidwood Station Error Evaluation Presentation" was held to review this event.with the personnel directly involved and their supervisor. 'The corrective-actions I cadrsssing both root and contributing causes are detailed below, f I
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l2974m(011990)/3
. LICEptrr EVDff REP 0kT (LERl TEXT EONTitamT1DN Fare kev'2.0
' FACILITY NAE (1) DOCKET NUSER (2) LER liteEt (6) Pane (3)
Sequential
. Year //{
ff /{f/ Revision f
M ar
/// % =her ///
I eralse 2- O l's 1 0 1 0 1 0 1 41 El 7 aI9 - 010l8 - 0 l= 0 01 3 0F 01 4 {
TEXT Energy industry identification System (EIIS) codes are identified in the text as [XX) l:
C; CAU$E OF EVENT !
'The' root cause of this event was a preservice deficiency. The capacity of.the electrical heat tracing of the
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RWST vent line was not adequate to maintale the temperature above 35 degrees F with outside air temperature at IB' degrees F below zero.
- The cause of. the f ailure to identify the below' limit read was personnel error. .Both the EA and NS0' rounds
- identified the reading as a Technical Specification reading. Both rounds identified that the minimum eccsptable value was 35 degrees F.
y C:ntributing causes to the failure to identify the below limit reading were:
- 1. There were no alarms associated with the RWST vent line temperature to key personnel into recognizing that a parameter was approaching a limit.
- 2. The rounds did not have an Administrative" Limit to alert personnel that a parameter is trending towards an unacceptable limit. ;
D. SAFETY ANALYSIS: ,
This event had no effect on the safety of the plant or the public. The RWST_was' functional and available.
Boration capability was also available f rom the Boric Acid Storage Tank (GA).-
Under the worst case condition of extended low temperature RWST Vent Line conditions causing an icing on the j v:nt line, there would still be no effect. Based on data contained in section 6 of the Updated Final Safety j . Analysis Report, adequate excess net positive suctisn head is available for operation of ECCS equipment even l trith a partial vacuum in the RWST. Prompt Operator recogni.tlon and action to remove from operation any component experiencing cavitation symptoms would provide for adequate ECCS operation until the switchover to r: circulation phase where the RWST would no longer be providing suction to ECCS components, g E. ' CORRECTIVE ACTIONS:
The RWST Vent Path temperature was verified at 36 degrees F upon discovery that it had been recorded at 34
( dIgrees F on the previous shift.
The Electrical Heat tracing was checked. It was found to be operating.
'. The RWST heater was placed in a " continual operation mode to raise RWST temperature which would provide .
L. additional heat to the vent line.
l RWST Vent Path Temperature was monitored.twice per eight hour shif t until December 26, 1989 when outside air f
' temperature was above 35 degrees F and RWST vent path temperature had been indicating above.48 degrees F for several days. '
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,2974miO11990)/4
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. . LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form key 2.0
'IACILITY~NAME (1) DOCKET NUMBER (2) LER MUMBER (6) Paoe (3)
Year. /// Sequential /// Revision fff fff
/// Numbgr /// Mer
,praidwood 2 0 1 5 1 0 1 0 1 0 1 41 El 7 819 - 010lB - 0l 0 01 4 0F Dj 4 TEXT Energy Industry Identification System (E!!$) codes are identified in the text as (XX)
Bas:d on the initial information associated with this event the personnel directly involved with this event I participated in a "Braidwood Station Error Evaluation Presentation" to identify root and contributing causes of this event. Based on the conclusions of this presentation the following corrective actions will be taken:
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- 1. The EA rounds sheets will be revised to include an administrative limit for RWST Vent Path temperature.
This limit will provide advance notification so corrective actions can be taken prior to reaching the Technical- Specification Limit. The rounds will also be revised to add a note on each page where readings are taken for Technical Specification requirements instructing the EA to immediately notify the Shift Supervisor of an out of tolerance Technical Specification reading. These actions will be tracked to completion by action item 457-200-89-09201.
- 2. An evaluation will be conducted to identify methods to increase the capability to heat the RW$T Vent '
Line and provide for a low temperature alare. This will be tracked to completion by action item 457-200-89-09202,
- 3. LThis event will be covered in a training tailgate session with appropriate Operating shif t personnel.
This will be tracked to completion by action item 457-200-89-09203. ,
4 A program will be developed to provide a aflagging" mechanism for rounds where an out of tolerance ,
Technical Specification reading has been recorded. This action will be tracked to completion by action
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item 457-200-89-09204.
l F. PREVIOUS OCCURRENCES There have been no previous occurrences.
G. COMPONENT FAILURE 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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