ML20205D253
From kanterella
Jump to navigation
Jump to search
| ML20205D253 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/13/1985 |
| From: | Robert Lewis TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| LER-85-040, LER-85-40, NUDOCS 8509230571 | |
| Download: ML20205D253 (1) | |
Similar Documents at Browns Ferry | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20239A4131987-09-0909 September 1987
[Table view]Ler:On 770105,radiator Monitor on RHR Svc Water Discharge Line from HX 1A Showed Increase in Radiation Level.Caused by Leaking Inner Head Gasket Due to Loose Stud Bolts.Locknuts Installed on Each Stud Bolt 05000260/LER-1986-003, Corrected Page 2 to LER 86-003-00:on 860226,energized Isolation Logic Tripped.Caused by Personnel Error.Temporary Cover for Protection Against Accidental Bumping of Bus Transfer Switch Provided1986-04-10010 April 1986 Corrected Page 2 to LER 86-003-00:on 860226,energized Isolation Logic Tripped.Caused by Personnel Error.Temporary Cover for Protection Against Accidental Bumping of Bus Transfer Switch Provided 05000259/LER-1985-054, Advises That LER 85-054-00 Cancelled1986-02-10010 February 1986 Advises That LER 85-054-00 Cancelled 05000259/LER-1985-049, Corrected Page 1 to LER 85-049-00:on 850623,during Performance of Work on Diesel Generator Battery Racks, Several Rack Support Studs Found Broken.Caused by Use of Stud Matl Not Suitable for Welding1985-10-25025 October 1985 Corrected Page 1 to LER 85-049-00:on 850623,during Performance of Work on Diesel Generator Battery Racks, Several Rack Support Studs Found Broken.Caused by Use of Stud Matl Not Suitable for Welding ML20205D2531985-09-13013 September 1985 Notifies That LERs Will Not Be Prepared Using 50-259/85040 & 50-259/85042.Info Will Be Included in 50-259/85039 ML20137G8431985-08-14014 August 1985 LER Will Not Be Prepared Under 50-259/85038.Info to Have Been Included in Rept Incorporated as Rev to BFRO-50-259/85036 R1 05000259/LER-1983-018, Updated LER 83-018/031-2:on 830325,while Performing SI 4.2.A-13,standby Gas Train B Found Inoperable.Caused by Erratic Mcdonnel & Miller Flow Switch.Switch Replaced & SI 4.7.B-1 & SI 4.7.A-13 Completed1984-07-27027 July 1984 Updated LER 83-018/031-2:on 830325,while Performing SI 4.2.A-13,standby Gas Train B Found Inoperable.Caused by Erratic Mcdonnel & Miller Flow Switch.Switch Replaced & SI 4.7.B-1 & SI 4.7.A-13 Completed 05000259/LER-1984-022, Updated LER 84-022-01:on 840212,investigation Determined That Single Failure or LOCA & Loss of Offsite Power Could Cause Equipment Necessary for Electrical Board Room Cooling to Be Lost.Caused by Design Oversight1984-07-20020 July 1984 Updated LER 84-022-01:on 840212,investigation Determined That Single Failure or LOCA & Loss of Offsite Power Could Cause Equipment Necessary for Electrical Board Room Cooling to Be Lost.Caused by Design Oversight 05000296/LER-1984-004, Followup LER 84-004-01:on 840228,RHR Outboard Loop II Isolation Valve CFV-74-67 Stem Found Broken Upon Disassembly.Caused by Overloading.Valve Stem Replaced W/Stronger & More Durable Matl1984-06-15015 June 1984 Followup LER 84-004-01:on 840228,RHR Outboard Loop II Isolation Valve CFV-74-67 Stem Found Broken Upon Disassembly.Caused by Overloading.Valve Stem Replaced W/Stronger & More Durable Matl 05000296/LER-1979-005, Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved1984-04-27027 April 1984 Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved 05000259/LER-1982-064, Updated LER 82-064/03X-1:on 820823 & Jan 1984,Station II Cable Tray Fixed Spray Sys Did Not Meet Tech Spec Requirements.Caused by Restriction in Supply Line Strainer Due to Buildup of Silt & Clam Shells1984-04-20020 April 1984 Updated LER 82-064/03X-1:on 820823 & Jan 1984,Station II Cable Tray Fixed Spray Sys Did Not Meet Tech Spec Requirements.Caused by Restriction in Supply Line Strainer Due to Buildup of Silt & Clam Shells 05000259/LER-1984-004, Updated LER 84-004-01:on 840106,reactor Mode Switch Moved from Run to Startup,Causing Half Scram.Caused by Personnel Error.Unit Manually Scrammed.Operator & Nuclear Engineer Counseled Re Use of Rod Notch Override1984-04-11011 April 1984 Updated LER 84-004-01:on 840106,reactor Mode Switch Moved from Run to Startup,Causing Half Scram.Caused by Personnel Error.Unit Manually Scrammed.Operator & Nuclear Engineer Counseled Re Use of Rod Notch Override 05000259/LER-1984-014, Updated LER 84-014-01:on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Revised1984-03-13013 March 1984 Updated LER 84-014-01:on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Revised 05000259/LER-1983-066, Updated LER 83-066/03X-1:on 831112,interlock That Prevents Bridge Travel Over Core W/One Rod Withdrawn & Fuel Grapple Extended Failed to Operate,Resulting in Loss of Rod Block Function.Caused by Improper adjustment.W/840309 Ltr1984-03-0909 March 1984 Updated LER 83-066/03X-1:on 831112,interlock That Prevents Bridge Travel Over Core W/One Rod Withdrawn & Fuel Grapple Extended Failed to Operate,Resulting in Loss of Rod Block Function.Caused by Improper adjustment.W/840309 Ltr 05000260/LER-1982-028, Followup LER 82-028/03X-3:on 810921,turbine Reactor Bldg Doors 237 & 238 Opened Simultaneously,Breaching Secondary Containment.Caused by Failed Folger Adams Interlock Sys Due to Loose Door Latch Screws.Procedures Revised1984-03-0909 March 1984 Followup LER 82-028/03X-3:on 810921,turbine Reactor Bldg Doors 237 & 238 Opened Simultaneously,Breaching Secondary Containment.Caused by Failed Folger Adams Interlock Sys Due to Loose Door Latch Screws.Procedures Revised 05000259/LER-1984-007, Followup LER 84-007-01:on 840127,operator Observed Decreasing Pressure on Control Atmospheric Dilution Tanks. Caused by Two Isolation Valves Being in Closed Position. Operating Instructions Revised1984-03-0202 March 1984 Followup LER 84-007-01:on 840127,operator Observed Decreasing Pressure on Control Atmospheric Dilution Tanks. Caused by Two Isolation Valves Being in Closed Position. Operating Instructions Revised 05000259/LER-1983-029, Updated LER 83-029/03L-1:on 830604,during Standby Gas Treatment Sys Operability Test,Train B Discovered Inoperable.Caused by Erratic Mcdonnel & Miller Model AF-1 Flow Switches.Damper Adjusted.W/Undated Ltr1984-02-27027 February 1984 Updated LER 83-029/03L-1:on 830604,during Standby Gas Treatment Sys Operability Test,Train B Discovered Inoperable.Caused by Erratic Mcdonnel & Miller Model AF-1 Flow Switches.Damper Adjusted.W/Undated Ltr 05000260/LER-1983-074, Updated LER 83-074/03X-1:on 831105 & 10,turbine Exhaust Inner Rupture Diaphragms Failed During HPCI Initiation. Investigation Underway to Determine Cause of Failures. Diaphragms Replaced & HPCI Returned to Svc1983-12-0505 December 1983 Updated LER 83-074/03X-1:on 831105 & 10,turbine Exhaust Inner Rupture Diaphragms Failed During HPCI Initiation. Investigation Underway to Determine Cause of Failures. Diaphragms Replaced & HPCI Returned to Svc 05000296/LER-1983-026, Supplemental LER 83-026/03X-4:on 830411,while Attempting to Establish EECW Flow Rate to Emergency Diesel Generator 3 Coolers,Head on HX Found Cracked.Caused by Mfg Defect.Cast Iron Head Replaced1983-11-25025 November 1983 Supplemental LER 83-026/03X-4:on 830411,while Attempting to Establish EECW Flow Rate to Emergency Diesel Generator 3 Coolers,Head on HX Found Cracked.Caused by Mfg Defect.Cast Iron Head Replaced 05000259/LER-1982-089, Updated LER 82-089/03T-1:on 821103,primary Containment Purge Sys Failed to Achieve Required Flow Rate.Caused by Sand Dust Clogging HEPA Filters.New Filters Installed1983-04-0808 April 1983 Updated LER 82-089/03T-1:on 821103,primary Containment Purge Sys Failed to Achieve Required Flow Rate.Caused by Sand Dust Clogging HEPA Filters.New Filters Installed 05000259/LER-1982-023, Followup LER 82-023/03X-2:on 820327,recirculation Pump 1A Tripped Due to Spurious Generator Starter Relay Operation. Caused by Hi-temp Relay Trip.Relay Reset in 20 Minutes & Pump Returned to Svc.No Recurrence Control Planned1982-10-13013 October 1982 Followup LER 82-023/03X-2:on 820327,recirculation Pump 1A Tripped Due to Spurious Generator Starter Relay Operation. Caused by Hi-temp Relay Trip.Relay Reset in 20 Minutes & Pump Returned to Svc.No Recurrence Control Planned 05000259/LER-1982-039, Reissued LER 82-039/03L-0:on 820609,fuse Blew Resulting in Inboard Primary Containment Isolation.Caused by Shorted Coil for Relay 16A-K66B,GE Type CR120A.Fuse & Relay Coil Replaced & Hydrogen Analyzers Returned to Normal1982-07-0606 July 1982 Reissued LER 82-039/03L-0:on 820609,fuse Blew Resulting in Inboard Primary Containment Isolation.Caused by Shorted Coil for Relay 16A-K66B,GE Type CR120A.Fuse & Relay Coil Replaced & Hydrogen Analyzers Returned to Normal 05000259/LER-1982-018, Updated LER 82-018/03X-1:on 820317,inspector Observed Bolts Missing from Reactor Core Isolation Cooling Turbine Exhuast Rupture Diaphragm Assembly.Outer Rupture Diaphragm Missing. Caused by Failure to Install Outer Rupture Disc1982-06-0101 June 1982 Updated LER 82-018/03X-1:on 820317,inspector Observed Bolts Missing from Reactor Core Isolation Cooling Turbine Exhuast Rupture Diaphragm Assembly.Outer Rupture Diaphragm Missing. Caused by Failure to Install Outer Rupture Disc 05000259/LER-1980-031, Updated LER 80-031/03X-1:on 820415,during 4 Kv Shutdown Bus 2 Transfer,Fault on Normal Feeder Bus from TS1B to 480-volt SD Bd 1B Caused Loss of Power to Board.Caused by Fault Condition at Busway Joint Above Board1982-06-0101 June 1982 Updated LER 80-031/03X-1:on 820415,during 4 Kv Shutdown Bus 2 Transfer,Fault on Normal Feeder Bus from TS1B to 480-volt SD Bd 1B Caused Loss of Power to Board.Caused by Fault Condition at Busway Joint Above Board 05000260/LER-1982-013, Updated LER 82-013/03X-1:on 820412,pressure Switch 2-PS-68-96 Found to Operate Above Tech Spec Limits.Caused by Drifted Calibr.Barton Model 288 Pressure Switch Recalibr, Functionally Tested & Returned to Svc1982-06-0101 June 1982 Updated LER 82-013/03X-1:on 820412,pressure Switch 2-PS-68-96 Found to Operate Above Tech Spec Limits.Caused by Drifted Calibr.Barton Model 288 Pressure Switch Recalibr, Functionally Tested & Returned to Svc 05000260/LER-1981-052, Updated LER 81-052/03X-1:on 811007,containment Atmosphere Hydrogen Analyzer B Sample Return Pump Discovered Cycling. Probably Caused by Randon Failure.Gas Calibr Performed & Analyzer Returned to Svc1982-04-12012 April 1982 Updated LER 81-052/03X-1:on 811007,containment Atmosphere Hydrogen Analyzer B Sample Return Pump Discovered Cycling. Probably Caused by Randon Failure.Gas Calibr Performed & Analyzer Returned to Svc 05000260/LER-1982-010, Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful1982-03-0404 March 1982 Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful ML20064H8771978-12-18018 December 1978 /01T-0 on 781205:during Refueling Outage 6 Msiv'S Exceeded Leakage Limits.Caused by Degradation of Valve Seating Surfaces Thru Normal Oper ML20197D4371978-11-15015 November 1978 /03L-0 on 781029:during Refueling,While Reloading Fuel in Vessel W/All Rods inserted,2 IRM Channels Were Inoperable in Same Trip Sys.Irm F Signal Cable Was Sheared by CRD Repair Platform IRM H Signal Cable Disconnected ML20064F0861978-11-15015 November 1978 /03L-0 on 781022:offgas Sampling Pump a Malfunctioned & Pump B Motor Would Not Start.Caused by Vanes Sticking on Pump A,Model MB21 Mfg by Metal Bellows Corp. Bearings & Centrifugal Switch Failed on Pump B Motor ML20064F0551978-11-15015 November 1978 /03L-0 on 781025:radwater Airborne Effluent Monitor Recorder RM-90-252 Failed to Oper Resulting in Loss of Continuous Effluent Monitoring.Caused by Broken Input Signal Lead ML20064E1691978-11-0606 November 1978 /03L-0 on 781016:two Zones of Fire Protec Fixed Spray Piping in Reactor Bldg Were Found Transposed Due to Misinterpretation of Drawings Causing Incorrect Installation of Piping.Piping Has Been Reconnected to Agree W/Drawings ML20064B7121978-10-0202 October 1978 /01T-0 on 780919:Foxboro Model 610 Pwr Supplies Provided Under TVA Contact 75K11-8680 Were Not Seismically Qualified,Qualified Pwr Supplies Have Been Provided & Will Be Installed ML20084U0271977-02-0909 February 1977 LER BFRO-50-259/775:on 770126,condenser Vacuum Switches PS-2-1A,2A & 8A Found Operating Below Tech Spec Limits. Caused by Setpoint Drift.Switches Reset ML20084T8491977-02-0404 February 1977 LERs BFRO-50-259/7627 & BFRO-50-260/7618:on 770119,GE Advised Util That MAPLHGR Limits Must Be Reduced to Ensure Peak Clad Temp Less than 2,200 F.Caused by Input Discrepancies in 10CFR50.46,App K Analyses ML20084U0291977-02-0303 February 1977 LER Bfro 50-259/774:on 770111,alarm Sounded in Spreading Room a Smoke Detector & Would Not Clear.Caused by Increased Sensitivity.Detector Replaced ML20084U0261977-01-28028 January 1977 LER BFRO-50-260/771:on 770101,alarm Sounded from Smoke Detector in Reactor Bldg & Would Not Clear.Caused by Increased Sensitivity.Alarm Replaced ML20084U0381977-01-26026 January 1977 Followup LER BFRO-50-296/7618:on 761117,torus Oxygen Sensor Failed to Respond Properly to Calibr Gas During Surveillance Testing.Caused by Misalignment of Sensor & Calibr Piston Assembly.Corrective Actions Not Stated ML20084T8461977-01-20020 January 1977 LER BFRO-50-259/772:on 761229,pressure Switch PS-3-74B Exceeded Tech Spec Setpoint.Caused by Setpoint Drift.Switch Inspected,Recalibr & Functionally Tested for Repeatability ML20084T8481977-01-17017 January 1977 LER BFRO-50-259/771:on 770103,vacuum Breaker 64-28E Remained Open Following Performance of Drywell Pressure Suppression Vacuum Breaker Surveillance Testing.Caused by Binding of Piston Rod W/Cylinder Bushing ML20084T8441977-01-17017 January 1977 LER BFRO-50-259/773:on 770104,liquid Released from RHR Svc Water HX 1A.Caused by Leaking Inner Head Gasket in 1A Hx. Release Not Detected Earlier Due to Operator Inattention ML20084U0321977-01-10010 January 1977 LER BFRO-50-296/7620:on 761212,during Startup Testing, Drywell Temp Recorder TR-64-52 Became Erratic.Caused by Broken Thermocouple Lead Inside Junction Box Due to Loose Screw Causing Excessive Vibration ML20084T8521976-12-21021 December 1976 LERs BFRO-50-259/7627 & BFRO-50-260/7618:on 761208,GE Advised Util That Revised Analyses of Input Errors to ECCS Analyses Is Less than 1%.Plant Operation Unaffected by Input Errors ML20084U0441976-12-16016 December 1976 LER BFRO-50-296/7618:on 761117,torus Oxygen Sensor Failed to Respond Properly to Calibr Gas During Surveillance Testing. Caused Not Stated ML20084U2731976-12-15015 December 1976 LER BFRO-50-260/7617:on 761116,HPCI Turbine Steam Supply Valve 2-FCV-73-16 Failed to Open & Breaker Overloads Found Tripped.Caused by Sheared Switch Gear Assembly Pin for Limitorque SMB-2 Valve Operator ML20084U0341976-12-14014 December 1976 LER BFRO-50-296/7619:on 761126,during Scheduled Maint Test, Diesel Generator 3D Start Circuit 1 Found Inoperable.Caused by Relay Failure in Start Circuit 1 Speed Sensing Circuit. Relay Replaced ML20084T8581976-12-0808 December 1976 LER BFRO-50-259/7625:on 761122,one Start Circuit Breaker on Diesel Generator B Found Inoperable.Caused by Failure of Square D Co 30 Amp Breaker L25V909 to Supply Power Due to Broken Stud Holder on Connector a ML20084U2761976-12-0808 December 1976 LER BFRO-50-260/7616:on 761115,electric Hydraulic Control Loss of Fluid Pressure Switch PS-47-142 Failed to Give Half Scram When Tested.Caused by Pressure Switch Plugged W/ Teflon Tape.Switch Cleaned ML20084T8591976-12-0303 December 1976 LER BFRO-50-259/7624:on 761104,torus Oxygen Sensor Failed to Respond Properly to Calibr Gas During Surveillance Test. Caused by Plugged Nozzle on Calibr Cylinder.Nozzle & Sensor Replaced ML20084T8621976-11-24024 November 1976 LER BFRO-50-259/7623:on 761103,diesel Generator D Exhibited Erratic Speed Behavior Under Load.Apparently Caused by Dirty Oil in Woodward Governor Model EG-B10 Actuator.Oil to Be Replaced Periodically 1987-09-09 Category:TEXT-SAFETY REPORT MONTHYEARML18039A9041999-10-15015 October 1999
[Table view]LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30 |
Text
TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 September 13, 1985 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Dear Sir:
TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 1 -
DOCKET No. 50-259 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORTS BFR0-50-259/85040 AND 259/85042 A Licensee Event Report (LER) will not be prepared under ntabers 50-259/85040 and 259/85042. Information that would have been reported in these LERs has been included in 50-259/85039. Please be advised of these vacancies in our accounting sequence.
Very truly yours, TENNESSEE VALLEY AUTHORITY d 5 1sul Robert L. Lewis
/_ActingPlantManager U
Browns Ferry Nuclear Plant cc: Regional Administrator INPO Records Center U.S. Nuclear Regulatory Commission Suite 1500 Office of Inspection and Enforcement 1100 Circle 75 Parkway Region II Atlanta, Georgia 3033 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector, BFN 8509230571 850913 DR ADOCK O 29 f2&
I10 J
An Equal Opportunity Employer
Retrieved from "https://kanterella.com/w/index.php?title=ML20205D253&oldid=3060793"