|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18038B3341995-07-11011 July 1995 LER 95-001-00:on 950615,under-voltage Condition Occurred on Shutdown Boards,Automatically Starting Edgs.Caused by Loss of Athens 161 Kv Line.Edgs Placed in Standby & Power Restored to buses.W/950711 Ltr ML18036B2201993-03-29029 March 1993 LER 93-001-00:on 930228,unplanned Actuation of ESF Occurred When 3 DGs Automatically Fast Started.Caused by Inappropriate Personnel Action.Licensee Will Replace Damaged CAS Logic Cable & Will Submit Followup rept.W/930329 Ltr ML18033B7021991-05-11011 May 1991 LER 91-003-00:on 910412,unplanned ESF Occurred When EDG Unexpectedly auto-started During Performance of Common Accident Signal Logic Surveillance Instruction.Suppl to LER Will Be Submitted by 910617.W/910511 Ltr ML18033B5581990-11-19019 November 1990 LER 90-004-00:on 901020,unplanned ESF Actuation Occurred. Investigation Ongoing to Determine Cause of Actuation.W/ 901119 Ltr ML18033B4101990-07-0202 July 1990 LER 90-004-00:on 900601,unplanned ESF Actuation Occurred as Result of Water in Cable Spreading Room a Dripping on ECCS Analog Trip Units.Caused by Design Oversight.Water Spill Wiped Up & Cabinets Covered W/Plastic sheeting.W/900702 Ltr ML20042G4561990-05-0404 May 1990 LER 90-005-00:on 900404,discovered That Compensatory Sample for Raw Cooling Water Sys Inadequately Taken.Caused by Personnel Error.Individual Counseled on Importance of Procedural Compliance.Required Sample taken.W/900504 Ltr ML20028A6071982-11-0909 November 1982 LER 82-082/03L-0:on 821011,continuous Air Monitor 1-90-256 Assumed Downscale Position Due to Miswiring of Alarm Circuit.Caused by Inadequate post-replacement Functional Test After Bell Replacement.Maint Instruction Written ML20027B7561982-09-21021 September 1982 LER 82-064/03L-0:on 820823,determined Station II Cable Tray Fixed Spray Sys Did Not Meet Tech Specs.Caused by Apparent Restriction in Supply Line Strainer.Strainer Cleaned & Flushed ML20052H7411982-03-14014 March 1982 Updated LER 82-001/01X-1:on 820115,during Offsite Verification of Process Computer Programming Changes Involving Data Shown in Tech Spec Tables 3.5.I-3 & 3.5.I-4, Input Error Made.Caused by Personnel Error ML20039C9651981-12-22022 December 1981 LER 81-080/03L-0:on 811124,reactor Core Isolation Cooling Sys Failed to Pass Pump Flow Rate Requirements During Operability Tests.Caused by Transmitter Amplifier Card Failure.Gemac 1589K75G702 Amplifier Card Replaced ML20004G0521981-06-19019 June 1981 LER 81-026/03L-0:on 810520,inservice Insp Ultrasonic Exam Did Not Receive Required Evaluation.Caused by Effect of Reduced Recording Level Not Being Recognized Until Recent Questions Were Raised in Area.Procedures Clarified ML20004D5451981-06-0404 June 1981 LER 81-022/03L-0:on 810511,during Normal Operation,Valve FCV-74-57 Motor Starter Thermal Tripped Upon Opening & Closing.Caused by Broken Bolts Which Hold Motor Together. Motor Bolts & Bearings Replaced ML20004B1001981-05-20020 May 1981 LER 81-014/03L-0:on 810424,MSIVs 1-14,1-15,1-37,1-38,1-51 & 1-52 Exceeded Tech Specs Allowable Leak Rate During Testing.Caused by Slight Steam Erosion Due to Deterioration of Valve Seating Surfaces.Maint & Retest Performed ML19350D8221981-05-15015 May 1981 LER 81-011/03L-0:on 810421,local Fire Protection Panel Circuit Breaker 25-331 Tripped & de-energized Panel.Cause Unknown.Breaker Reset ML20003E8621981-04-0808 April 1981 LER 81-015/03L-0:on 810317,HPCI Turbine Inner Exhaust Disc Ruptured.Cause Unknown.Disc Replaced ML20003F2021981-04-0707 April 1981 LER 81-014/03L-0:on 810313,mode a of Reactor Water Level Instrumentation Indicated Full Upscale Resulting in Turbine Trip.Caused by Loss of Ref Leg to 2-LITS-3-203A & B & 2-LIS-3-184 Due to Partially Open Equalizing Valve ML19350B8271981-03-13013 March 1981 LER 81-012/03L-0:on 810224,scram Discharge Level Switch (25 Gallon) Found 0.4% Above Setpoint During Performance of SI 4.1.A-8.Caused by Model SL-305-EI-X Level Switch, 3-LS-85-45E,setpoint Drift.Switch Recalibr ML20002C2231980-12-31031 December 1980 LER 80-088/03L-0:on 801202,diesel Generator 1c Tie Breaker 1812 on 4-kV Shutdown Board C Tripped.Caused by Faulty Diode in Overspeed Trip Annunciator Relay Circuit Permitting Spurious Signal to Operate Overspeed Trip Relay ML19345D3331980-12-0909 December 1980 LER 80-084/03L-0:on 801112,alternate Feeder Breaker 1930 Failed to Close.Caused by Lack of Contact Between Fuse Clip & Breaker Fuse & Dirty Auxiliary Contacts.Fuse Clip Adjusted & Contacts Cleaned ML18025B0081980-07-28028 July 1980 LER 80-024/01T-1:on 800628,during Routine Shutdown for maint,76 of 185 Control Rods Failed to Fully Insert.Caused by Reduction in Scram Discharge Vol Due to Retention of Water in East Side Header.Mods Will Be Implemented ML18025A9441980-06-27027 June 1980 LER 80-023/03L-0:on 800607,during Normal operation,2A Reactor Recirculation Motor Generator Set Tripped Due to Generator Stator Temp High Relay Actuation.Probable Cause Was Loose Wire Caused by Vibration ML18025A8391980-05-0101 May 1980 LER 80-008/03L-0:on 800402,3B Diesel Generator Governor Actuator Would Not Respond Properly During Operability Surveillance Instruction.Cause Unknown.Oil Contamination Suspected.Sump Flushed & Refilled ML19309F1961980-04-18018 April 1980 LER 80-026/03L-0:on 800322,HPCI Stop Valve Would Not Open Completely.Caused by Worn Mechanical Overspeed Trip Piston. Hydraulic Sys Adjusted & Stop Valve Tested ML18024B4831980-04-0707 April 1980 LER 80-015/03L-0:on 800309,during Startup,Rod Block Monitor a Was Bypassed for More than 24-hrs in 30-day Period.Caused by Need for Calibr & Maint.Channel Recalibr,Tested & Returned to Svc ML19309A8811980-03-28028 March 1980 LER 80-020/03L-0:on 800301,during Normal Operation,W/High Winds & Freezing Rain,Trinity Offsite 161-kV Power Source Was Lost Intermittently.Caused by Ice Loading & High Winds Requiring Operation of Line Protective Relay ML19296D1921980-02-25025 February 1980 LER 80-008/03L-0:on 800127,during Unit 1 Refueling Outage, Found HPCI Turbine Had Crack in Coupling Bearing Support Pedestal.Possibly Caused by Water Hammer in Main Steam Supply Line.Pedestal Is Being Replaced ML18024B0891979-11-0707 November 1979 Updated LER 79-006/03L-1:on 790507,during Normal Operation, Erratic Indication of Torus Hydrogen Sensor Observed. Hydrogen Sensor Replaced & Tested Satisfactory.Design Change Request Initiated ML18024A9031979-07-12012 July 1979 LER 79-017/03L-0 on 790615:during Normal Operation,Setpoint on Pressure Switch PS-3-22D Exceeded Specified Limit.Caused by Drift in Model B2T-A12SS Switch.Switch Recalibr & Satisfactorily Tested ML19274E5051979-03-22022 March 1979 LER 79-006/03L-0 on 790228:reactor,turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable for 3.5-h.Caused by Moisture in SC-2B Detector & Leaking Flanges.Moisture Removed & Flanges Tightened 1995-07-11
[Table view] Category:RO)
MONTHYEARML18038B3341995-07-11011 July 1995 LER 95-001-00:on 950615,under-voltage Condition Occurred on Shutdown Boards,Automatically Starting Edgs.Caused by Loss of Athens 161 Kv Line.Edgs Placed in Standby & Power Restored to buses.W/950711 Ltr ML18036B2201993-03-29029 March 1993 LER 93-001-00:on 930228,unplanned Actuation of ESF Occurred When 3 DGs Automatically Fast Started.Caused by Inappropriate Personnel Action.Licensee Will Replace Damaged CAS Logic Cable & Will Submit Followup rept.W/930329 Ltr ML18033B7021991-05-11011 May 1991 LER 91-003-00:on 910412,unplanned ESF Occurred When EDG Unexpectedly auto-started During Performance of Common Accident Signal Logic Surveillance Instruction.Suppl to LER Will Be Submitted by 910617.W/910511 Ltr ML18033B5581990-11-19019 November 1990 LER 90-004-00:on 901020,unplanned ESF Actuation Occurred. Investigation Ongoing to Determine Cause of Actuation.W/ 901119 Ltr ML18033B4101990-07-0202 July 1990 LER 90-004-00:on 900601,unplanned ESF Actuation Occurred as Result of Water in Cable Spreading Room a Dripping on ECCS Analog Trip Units.Caused by Design Oversight.Water Spill Wiped Up & Cabinets Covered W/Plastic sheeting.W/900702 Ltr ML20042G4561990-05-0404 May 1990 LER 90-005-00:on 900404,discovered That Compensatory Sample for Raw Cooling Water Sys Inadequately Taken.Caused by Personnel Error.Individual Counseled on Importance of Procedural Compliance.Required Sample taken.W/900504 Ltr ML20028A6071982-11-0909 November 1982 LER 82-082/03L-0:on 821011,continuous Air Monitor 1-90-256 Assumed Downscale Position Due to Miswiring of Alarm Circuit.Caused by Inadequate post-replacement Functional Test After Bell Replacement.Maint Instruction Written ML20027B7561982-09-21021 September 1982 LER 82-064/03L-0:on 820823,determined Station II Cable Tray Fixed Spray Sys Did Not Meet Tech Specs.Caused by Apparent Restriction in Supply Line Strainer.Strainer Cleaned & Flushed ML20052H7411982-03-14014 March 1982 Updated LER 82-001/01X-1:on 820115,during Offsite Verification of Process Computer Programming Changes Involving Data Shown in Tech Spec Tables 3.5.I-3 & 3.5.I-4, Input Error Made.Caused by Personnel Error ML20039C9651981-12-22022 December 1981 LER 81-080/03L-0:on 811124,reactor Core Isolation Cooling Sys Failed to Pass Pump Flow Rate Requirements During Operability Tests.Caused by Transmitter Amplifier Card Failure.Gemac 1589K75G702 Amplifier Card Replaced ML20004G0521981-06-19019 June 1981 LER 81-026/03L-0:on 810520,inservice Insp Ultrasonic Exam Did Not Receive Required Evaluation.Caused by Effect of Reduced Recording Level Not Being Recognized Until Recent Questions Were Raised in Area.Procedures Clarified ML20004D5451981-06-0404 June 1981 LER 81-022/03L-0:on 810511,during Normal Operation,Valve FCV-74-57 Motor Starter Thermal Tripped Upon Opening & Closing.Caused by Broken Bolts Which Hold Motor Together. Motor Bolts & Bearings Replaced ML20004B1001981-05-20020 May 1981 LER 81-014/03L-0:on 810424,MSIVs 1-14,1-15,1-37,1-38,1-51 & 1-52 Exceeded Tech Specs Allowable Leak Rate During Testing.Caused by Slight Steam Erosion Due to Deterioration of Valve Seating Surfaces.Maint & Retest Performed ML19350D8221981-05-15015 May 1981 LER 81-011/03L-0:on 810421,local Fire Protection Panel Circuit Breaker 25-331 Tripped & de-energized Panel.Cause Unknown.Breaker Reset ML20003E8621981-04-0808 April 1981 LER 81-015/03L-0:on 810317,HPCI Turbine Inner Exhaust Disc Ruptured.Cause Unknown.Disc Replaced ML20003F2021981-04-0707 April 1981 LER 81-014/03L-0:on 810313,mode a of Reactor Water Level Instrumentation Indicated Full Upscale Resulting in Turbine Trip.Caused by Loss of Ref Leg to 2-LITS-3-203A & B & 2-LIS-3-184 Due to Partially Open Equalizing Valve ML19350B8271981-03-13013 March 1981 LER 81-012/03L-0:on 810224,scram Discharge Level Switch (25 Gallon) Found 0.4% Above Setpoint During Performance of SI 4.1.A-8.Caused by Model SL-305-EI-X Level Switch, 3-LS-85-45E,setpoint Drift.Switch Recalibr ML20002C2231980-12-31031 December 1980 LER 80-088/03L-0:on 801202,diesel Generator 1c Tie Breaker 1812 on 4-kV Shutdown Board C Tripped.Caused by Faulty Diode in Overspeed Trip Annunciator Relay Circuit Permitting Spurious Signal to Operate Overspeed Trip Relay ML19345D3331980-12-0909 December 1980 LER 80-084/03L-0:on 801112,alternate Feeder Breaker 1930 Failed to Close.Caused by Lack of Contact Between Fuse Clip & Breaker Fuse & Dirty Auxiliary Contacts.Fuse Clip Adjusted & Contacts Cleaned ML18025B0081980-07-28028 July 1980 LER 80-024/01T-1:on 800628,during Routine Shutdown for maint,76 of 185 Control Rods Failed to Fully Insert.Caused by Reduction in Scram Discharge Vol Due to Retention of Water in East Side Header.Mods Will Be Implemented ML18025A9441980-06-27027 June 1980 LER 80-023/03L-0:on 800607,during Normal operation,2A Reactor Recirculation Motor Generator Set Tripped Due to Generator Stator Temp High Relay Actuation.Probable Cause Was Loose Wire Caused by Vibration ML18025A8391980-05-0101 May 1980 LER 80-008/03L-0:on 800402,3B Diesel Generator Governor Actuator Would Not Respond Properly During Operability Surveillance Instruction.Cause Unknown.Oil Contamination Suspected.Sump Flushed & Refilled ML19309F1961980-04-18018 April 1980 LER 80-026/03L-0:on 800322,HPCI Stop Valve Would Not Open Completely.Caused by Worn Mechanical Overspeed Trip Piston. Hydraulic Sys Adjusted & Stop Valve Tested ML18024B4831980-04-0707 April 1980 LER 80-015/03L-0:on 800309,during Startup,Rod Block Monitor a Was Bypassed for More than 24-hrs in 30-day Period.Caused by Need for Calibr & Maint.Channel Recalibr,Tested & Returned to Svc ML19309A8811980-03-28028 March 1980 LER 80-020/03L-0:on 800301,during Normal Operation,W/High Winds & Freezing Rain,Trinity Offsite 161-kV Power Source Was Lost Intermittently.Caused by Ice Loading & High Winds Requiring Operation of Line Protective Relay ML19296D1921980-02-25025 February 1980 LER 80-008/03L-0:on 800127,during Unit 1 Refueling Outage, Found HPCI Turbine Had Crack in Coupling Bearing Support Pedestal.Possibly Caused by Water Hammer in Main Steam Supply Line.Pedestal Is Being Replaced ML18024B0891979-11-0707 November 1979 Updated LER 79-006/03L-1:on 790507,during Normal Operation, Erratic Indication of Torus Hydrogen Sensor Observed. Hydrogen Sensor Replaced & Tested Satisfactory.Design Change Request Initiated ML18024A9031979-07-12012 July 1979 LER 79-017/03L-0 on 790615:during Normal Operation,Setpoint on Pressure Switch PS-3-22D Exceeded Specified Limit.Caused by Drift in Model B2T-A12SS Switch.Switch Recalibr & Satisfactorily Tested ML19274E5051979-03-22022 March 1979 LER 79-006/03L-0 on 790228:reactor,turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable for 3.5-h.Caused by Moisture in SC-2B Detector & Leaking Flanges.Moisture Removed & Flanges Tightened 1995-07-11
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000260/LER-1999-010, :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 Satisfactorily1999-10-15015 October 1999
- 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
05000260/LER-1999-009, :on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug1999-10-14014 October 1999
- on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug
05000260/LER-1999-008, :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 Instructions1999-10-0808 October 1999
- 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
05000296/LER-1999-005-02, :on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With1999-09-30030 September 1999
- 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
ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212G2241999-09-27027 September 1999 Safety Evaluation Supporting Amend 221 to License DPR-68 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 ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8481999-08-16016 August 1999 Safety Evaluation Supporting Amends 260 & 219 to Licenses DPR-52 & DPR-68,respectively ML18039A8521999-08-0909 August 1999 SER Granting Licensee Request for Temporary Exemption from Requirements of 10CFR50.65,dtd 990204 ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts ML18039A8361999-08-0303 August 1999 Safety Evaluation Re Revs to Radiological Consequences Analyses Resulting from Power Uprates for Browns Ferry,Units 2 & 3 ML18039A8321999-08-0202 August 1999 Safety Evaluation Supporting Amends 259 & 218 to Licenses DPR-52 & DPR-68,respectively 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 05000296/LER-1999-004-02, :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 Position1999-07-26026 July 1999
- 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
05000260/LER-1999-007, :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.With1999-07-20020 July 1999
- 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
05000260/LER-1999-006, :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%.With1999-07-19019 July 1999
- 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
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 05000260/LER-1999-005, :on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With1999-07-12012 July 1999
- on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With
ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With 05000260/LER-1999-004-01, :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 Reset1999-06-28028 June 1999
- 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 05000260/LER-1999-001-05, :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.With1999-06-14014 June 1999
- 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
05000260/LER-1999-002-02, :on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With1999-06-14014 June 1999
- on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With
05000260/LER-1999-003-02, :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 Scram1999-06-14014 June 1999
- 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
ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7861999-05-21021 May 1999 SER Accepting TVA Proposed Alternatives Contained in 3-ISI-3 & 3-ISI-6 Pursuant to 10CFR50.55a(a)(3)(i) 05000296/LER-1999-003-01, :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 Tightened1999-05-0606 May 1999
- 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
ML18039A7731999-05-0303 May 1999 SER Accepting Util Second 10-year Interval Inservice Insp Program Plan Relief from ASME Boiler & Pressure Vessel Code, Section XI requirements-relief Request 3-ISI-2 for Browns Ferry Nuclear Plant,Unit 3 ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With B130202, Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 31999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3 ML18039A7641999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternative to Use Wire Penetrameters for Radiography Exams as Provided for in ASME Section Iii,Provides Acceptable Level of Quality & Safety ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal ML18039A7401999-04-0808 April 1999 Safety Evaluation Approving Licensee Alternative for Second 10-yr Interval ISI for Class 1,2 & 3 Pressure Retaining Bolted Connections at Bfn,Unit 2 ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr 05000260/LER-1999-001-03, :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 Operable1999-04-0707 April 1999
- 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
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 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 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 ML18039A7271999-03-11011 March 1999 Safety Evaluation Supporting Amend 258 to License DPR-52 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 ML18039A6901999-02-23023 February 1999 SER Granting Relief from ASME Boiler & Pressure Vessel Code, Section XI Requirements,Relief Request 2-ISI-6 for Browns Ferry Nuclear Plant,Unit 2 05000296/LER-1999-002, :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.With1999-02-19019 February 1999
- 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
05000296/LER-1999-001-02, :on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With1999-02-12012 February 1999
- on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With
1999-09-30
[Table view] |
Text
,
) 4. Nie , , ap nWUl ATORY COMMISSION N HC i OllM .' inh _ ,
{f lit ,
LICENSEE EVENT ItL: T CtdtpfHtti(w'k ,, l,, { { { ] O't.[ ASL PRINT On T YPE At t. REouinED INFonMATIoN) l [g
([ [ [ A[ Ll Bl Rl Fl 3]@l!$ 0 l 0l -l 0 l 0 l 0 l 0 ] O l - l 0 l 0 l@[ 4 l 1 l 1 $7l (1A l l'd)1 l@l
- at 4 g H.t tai,6 ( c oj el 14 4 pCE NLt; Null 49t H 25 '.% LILENSE j yPE .60 enN s
[.'ll_L}" $,[,$N I Lhl 0l 5l 0] O[ 0l 2] 9 ] 6 @l 6tl 069l 6 lEVENT1l6 DATE l 8 l 1 @l 0 l 6REPORT 14 15 l 2 l DATE 9 l 8 l H01 l@
IA8 G1 DOCKE T NUM9EH t vr.Ni r,f;SCillPflON AND PROB AFILE CONSEQUENCES h l
DiT~] {__Dtiring, normal operation, while performing turbine first stage pressure permissive (SI 4.1. A-14) turbine first stage permissive switches PS-1-81A and B and PS-1-91Al E E [ test _
1
~ EJ4] Land B were found an average of 10.7 percent above the limits of T.S. table 3.1. A.
There were no redundant ;
E LThere was no danger to the health or safety of the public.
BFRO-50-259/78016, 79008, 80053; 260/79016, g
[j_@ l systems. Previous similar events:
l
^[n l il l 79017, 79024, 80020, 80057; 296/ 79007, 79012, 30022, 80030, 80045, 81017, 81023.
l IOlHl { 80 1 8 3 COMP. VALVE
..i '. ! E M CAUSE CAUSE SUBCODE COMPONENT CODE SU& CODE SU8 CODE CODE CODE lol9l 1 Il Al @ [Ej @ lE l@ [I l N l S l T l R l Uj@ ]@ ] @ 11 30 sta 1.i 20 1 8 9 f0 it R E VISION SE QUE N11 At oCCun 4t NCE REFORT COI'E TYPE NO f VI NI YE AH HF POH ? NO.
. O llgl, g",pn-a,, ,', 18111 L-j 1013101 [gj 27 l 01 11 28 29 i Tl 30 L-J 31 LJ 32 27 J2 11 24 76 HOURS SUB ITT 0 FOR1 S. SUPPLI A MAN FACTURER TAKIN A Tl ON 4 I MET LEJ@ly._J@ l zl@ l zJ@ l0IoIOIoI LY_j@
41
[42Y[@ l43Ll@ lB l0 l6 l9 l(
44 4;
_14 J's .s6 37 40
'8 J CAUSE DESCHIPTION AND COHHECTIVE ACTIONS
[ i I o ' [_The Barksdale bourdon tube pressure switch model B2T-A12SS setpoints had drif ted.
i i l The switches were reset to the proper values and SI 4.1.A-14 was satisfactorily
- ,;.,jI completed. Design change request 1398 has been initiated to replace these switches g
j
[g l with an analog transmitter with a trip switch.
l li 14nI nl 80 1
OTHER $f A TUS is OV HY DISCOVERY DESCRIPTION
't. POWE R ST 5 lB[gl Surveillance test ]
l i j '> ] [_E_jh l 0] 9l 8l@l NA l
" AC UVITY CO%ENT LOCATION OF RELE ASE nELE ASEn oF HI L F ASE AMOUNT OF AC11VITY NA 1 NA l 1 6 [.Zj h [Z_] @ l 44 l
45 80 1 H 1 to 31 PE f t%4fgNE l. I kPtr.UHLS Nt i' 'ilf it TYPE L r SCniP TION --
NA l t i 1010 I OJGLzJ@l ' "
' " ' ,mOmN A',,uU,'it s
~,,,,,,,, m,:,,,P,,0N8 j NA E, E,] L, at.oloJ,,8l , ,,
$ f i' .;. (10 (H t I nA14 Af .1 Iti f As'tl t i V -
f Yt f l H ',f'.p us' T i( sPJ NA }
ITTT1 M 9 W @lIn 80 J
fli f.,1tiP flON 2 o 1%tig l_gj hi NA l ?Illlllll1ll1E G107060342 8f0629 P 05000296 ,,n on e . {
nam or Pnt PAnen_ . SDR ADGCK Q DR ,
7
.. . ? ._ ,
rennessee Valley Aathority Form IIF 17.
Browns Ferry Nuclear Plant BF 15.2 6/04/81 l F.R SUPPI.F. MENTAL, INFORMATION Technical Specification inv<>!ved . Table _3 A A BFitO40~.._290 /._81030.
lleported Under Technical Specification _6 7 2 AO) *Date due NRC:__6/30/81_
Unit 3 Date of Occurrence ._ hL1h/6L_ Time of Occurrence __0830 Identification and Description of Occurrence: During performance of SI 4.1.A-14 PS-1-81A and B and PS-1-91A and B f ailed to operate within T.S. limits. The as found was: .PS-1-81A,187 psi; PS-1-81B,185 psi; PS-1-91A,183.5 psi, PS-1-91B, 184 psi. The above values include a 12.6 psig water leg. T.S. table 3.1.A setpoint is 1154 psig.
_ Conditions Prior to Occurrence:
. Unit 1 refueling outage Unit 2 maintenance outage Unit 3 at 98%
Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe. _
None Apparent Cause of Occurrence:
Drift of the setpoint. This drift historically seems to occur during times of the year when there are seasonal weather changes. Application of these switches are marginal.
An:3_ lysis of Occurrence.
There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.
Corrective Action:
The switches were reset to the proper values and SI 4.1.A-14 was satisfactorily completed. Design change request 1398 has been initiated to replace these switches with an analog transmitter with a trip switch. Setpoint has been made more conservative. As interim correction action we are investigating another more applicable switch.
Failure Data: BFRO-50-259/78016, 79008, 80053; 260/79016, 79017, 79024, 80020, 296/79007, 79012, 80022, 80030, 80045, 81017, 81023.
80057; i_o_n_:Per >d - I.if : time; llesponsibility - Document Control Supervisor R e_t en_t_
tllevision: _ _ __
_ _ _