Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML18039A6661998-12-31031 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 ML20199F6501997-11-14014 November 1997 Special Rept:On 971031,one High Range Primary Containment Radiation Monitor Declared Inoperable for More than Seven Days.Caused by Component/Equipment Failure Inside Drywell. Will Repair or Replace Detector or Associated Cable ML20207K9241988-10-0707 October 1988 RO 88-01:on 880725,during Inventory of Snm,Discrepancy Noted for Intermediate Range Monitor Detector Removed from Core Location C.Caused by Inadequage SNM Control & Accountability Practices Existing at Time of Installation & Shipment ML20235J4541987-07-0202 July 1987 Special Rept 87-01,Rev 1:on 870321,three Seismic Triggers Would Not Provide Required Control Room Annunciation Upon Receipt of Horizontal 0.1 G Seismic Acceleration.All Instruments Removed from Site Repaired.Instructions Revised ML18032A4181987-07-0202 July 1987 Ro:On 870227 & 0505 Oil Spills Occurred Resulting in Oil Sheens.Spilled Matl Did Not Involve PCB-contaminated Oil. Feb Spill Went to Plant Intake Forebay & May Spill Went Directly Into Tennessee River ML18031B2851987-03-31031 March 1987 Special Rept:On 870321,loss of Seismic Monitoring Instrumentation Discovered.Caused by Inadequacy in Instructions & Training.All Instruments Removed from Site Will Be Repaired & Restored to Operation ML20117N7501985-05-0808 May 1985 Advises That Rept Will Not Be Prepared for RO BFRO-50-296/85011 ML20086G5971984-01-0303 January 1984 Telecopy RO 50-259/83073:on 831231,reactor Water Sample Indicated Chloride Concentration of 525 Ppb.Steam Flow Greater than 100,000 Lbm/H.Caused by Possible Resin Intrusion.Investigation in Progress ML20083E1551983-12-15015 December 1983 Telecopy RO 50-296-83060:on 831214,nine of 13 two-stage Relief Valves Tested Initially Failed to Lift within Allowable Range.Cause Being Evaluated W/Manufacturer.Nine Valves Will Be Reset & Retested Prior to Installation ML20082V3411983-12-12012 December 1983 Telecopy RO 50-259/83068:on 831210,RHR Pump 1C Motor Sparked & Smoked.Motor Shut Down & Restarted,Then Tripped on Overcurrent.Pump Declared Inoperable.Caused by Winding Failure.Motor Will Be Replaced ML20083A4301983-12-0808 December 1983 Telecopy Ro:On 831207,linear Crack Indication Identified by NDE in Weld DSHS-3-2 of Head Spray Piping of RHR Sys. Apparently Caused by Intergranular Stress Corrosion Cracking.Insp Per IE Bulletin 83-02 Will Be Performed ML20082D0251983-11-14014 November 1983 Telecopy Ro:On 831110,HPCI Isolated Due to Failure of Exhaust Rupture Disc.Cause Unknown.Maint Request Issued to Replace Disc.Investigation Continuing ML20078M9781983-10-14014 October 1983 Telecopy Ro:On 831013,routine Analysis of 831007 Scram Revealed That 2-LT-85-45A Did Not Initiate Trip When SDIV Exceeded 50 Gallons.On 831014,testing of Transmitter Revealed Slow & Erratic Response to Measured Variable ML20078H3281983-10-0606 October 1983 Telecopy RO 83061:on 831004,hydrogen-oxygen Analyzer Sample Pump B Determined Inoperable Following Notification from Metal Bellows Corp of Generic Deficiency.Pump Replaced W/ Upgraded Model in Stock on 831005 ML20080L8961983-09-20020 September 1983 Telecopy Ro:On 830919,Surveillance 4.7.A.2.G3 Determined Leakage Rates Exceeded for MSIV Lines A,C & D.Caused by Leakage Past Main Valve Seat.Seating Surfaces Modified ML20076J5841983-08-28028 August 1983 Telecopy Ro:On 830826,cracks Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Total Welds to Be Inspected Increased from 53 to 79.Updated Insp Results Encl ML20076J7451983-08-25025 August 1983 Telecopy RO BFRO-50-259/83049 R9:on 830825,weld Crack Indications Discovered in Welds on Core Spray & Reactor Water Cleanup.Number of Welds to Be Inspected Increased from 53 to 79 ML20076F3351983-08-23023 August 1983 Telecopy RO 50-259/83-49:on 830811,pipe Weld Cracking Indications Revealed by Addl Ultrasonic Insps.Possibly Caused by Corrosion.Addl Welds Inspected.Insp Repts to Be Submitted Periodically ML20080E0771983-08-22022 August 1983 Telecopy Ro:On 830812,cracks Found on Welds DCS-1-7, DSRWC-1-3,DCS-1-8 & DSRWC-1-2.Cause Not Stated.Total Number of Welds to Be Inspected Increased from 53 to 79 ML20080D6921983-08-22022 August 1983 Telecopy RO 83049R7:on 830812,indications Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Addl 29 Welds Will Be Inspected.Insp Results Encl ML20080D5721983-08-18018 August 1983 Telecopy Ro:On 830812,weld Cracks Discovered in Core Spray & Reactor Water Cleanup Sys.Addl 29 Welds Will Be Inspected. Insp Results Encl ML20076F6911983-08-17017 August 1983 Telecopy Ro:On 830812,indications Found on Pipe Welds for Core Spray & Reactor Water Cleanup.Addl 29 Welds Will Be Inspected Increasing Total Number of Welds to Be Inspected to 82 ML20076F5211983-08-15015 August 1983 Telecopy Ro:On 830812,core Spray Weld DCS-1-7 Had Intermittent Indication on Pipe Side of Weld Approx 41% Through Wall Depth.Reactor Water Cleanup Weld DSRWC-1-3 Had Two Indications Approx 5 Inches Long ML20076F8641983-08-15015 August 1983 Telecopy Ro:On 830815,indications Identified on Welds DCS-1-7,DSRWC-1-3,DCS-1-8 & DSRWC-1-2.Weld Insp Results Encl ML20076F5351983-08-12012 August 1983 Telecopy Ro:On 830812,during Routine Surveillance Testing, Four of Four Turbine first-stage Permissive Switches Discovered Out of Tech Spec Limits.Caused by Setpoint Drift. Setpoints Reset ML20077A0341983-07-12012 July 1983 Supplemental Ro:On 830604,13,14 & 15 Standby Gas Treatment Train B Declared Inoperable.Caused by Increased Damper Closure Since Measurements Made in May 1983.Dampers Returned to Preset Position ML20077A2791983-07-0606 July 1983 Telecopy RO 50-259/83036:on 830705,seven two-stage Target Rock Relief Valves Tested at Wyle Labs for as-found Set Pressure Failed to Lift within Allowable Range.Caused Under Evaluation.Valves Will Be Reset & Retested ML20024C0611983-06-29029 June 1983 Telecopy Ro:On 830613 & 14,train B Discovered Inoperable & Operability of Standby Gas Treatment Sys Trains Exceeded Tech Specs for Approx 6 H.Caused by Malfunctioning Square Root Converter.Plant Instruction Rev in Progress ML20071N4461983-05-24024 May 1983 Telecopy RO 50-286/8331:on 830520,reactor Low Pressure Switches PS-3-74B & PS-68-96,switch 2 Found Below Tech Spec Limits.Caused by Setpoint Drift.Setpoints Reset & Design Change Request DCR 1398 Initiated to Replace Switches ML20071H5801983-05-18018 May 1983 Telecopy RO 50-259/83024:on 830517,design Review of Emergency Diesel Generator Room Ventilation Sys Capabilities Revealed Design Temp Limits of Some Electrical Components May Be Exceeded.Caused by Error in Heat Dissipation Data ML20069M4551983-04-25025 April 1983 Telecopy RO 50-259/83021:on 830424,130 Fuel Bundles Unloaded from Core & Placed in High Density Fuel Storage Rack in Spent Fuel Storage Pool Not Tested for Boron Concentration. Caused by Inadequate Procedures ML20069L3361983-04-20020 April 1983 Telecopy RO 50-296/83024:on 830419,review of Licensing Documents Revealed Lead Test Assemblies Could Reach Max of 18.8 Kw/Ft in Event of Rod Withdrawal Error.Caused by Error in Preparation & Review of GE Licensing Documents ML20069K7371983-04-18018 April 1983 Telecopy RO 50-259/83020:on 830418,leakage Rate for Line a MSIV Found Above Tech Spec Limit.Caused by Leakage Past Main Valve Seat.Corrective Maint & long-term Mod Planned ML20064N9851983-02-0909 February 1983 Telecopy Message of RO 50-260-8302:on 830208,pressure Switches PS-68-96,PS-3-74A & PS-3-74B Found Out of Tech Spec Limits During Performance of Surveillance Instruction 4.2.B-7.Caused by Setpoint Drift.Switches Recalibr ML20064L2561983-02-0808 February 1983 Telecopy Ro:On 830207,reactor Low Water Level Switches Found Out of Tolerance.Caused by Instrument Drift.Switches Recalibr,Tested & Returned to Svc.Switches Will Be Replaced W/Analog Transmitter/Trip Unit Sys at Later Date ML20064M1461983-02-0707 February 1983 Telecopy Message of RO 50-259/83006:on 830205,relief Valve PCV 1-22 Failed to Reseat Fully After Actuation to Control Reactor Pressure.Probably Caused by Excessive Leakage of Pilot Valve.Pilot Valve & Solenoid Actuator Replaced ML18025B7241982-02-0909 February 1982 Ro:On 820104,suspended Solids Samples Exceeded Daily Max Limit of 100 Mg/L.Caused by High Increase in Turbidity & Suspended Solids Due to 3.4 Inches of Rainfall.No Corrective Action Taken Because Occurrences Not Typical ML20009F6691981-06-30030 June 1981 Ro:On 810629,during Refueling Outage,Ultrasonic Test Insp Revealed Reactor Water Cleanup Sys Inboard Primary Containment Isolation Valve Indication.Cause Unknown. Indication Will Be Removed & Weld Repaired ML20030C0691981-06-17017 June 1981 Ro:On 810616,during Routine Surveillance Testing,Turbine first-stage Permissive Switches PS-1-81A & B & PS-1-91A & B Were Found Above Tech Spec Limits.Caused by Setpoint Drift. Setpoints Reset to More Conservative Value ML20030C2511981-06-16016 June 1981 RO 50-259/8132:on 810609,during Routine Surveillance Testing,Reactor Pressure Switches PS-68-93 & PS-68-94 Were Found Out of Tech Spec Limits.Caused by Setpoint Drift. Setpoints Reset to Proper Value ML20030C0631981-06-16016 June 1981 Ro:On 810616,fire Protection Preaction Sys for Reactor Bldg Elevations 565,593 & 621 Were Found Isolated.Caused by Worker Failure to Return Sys to Svc Prior to Discontinuing Fire Watch.Sys Valved Into Svc Upon Discovery ML20030C0861981-06-12012 June 1981 Ro:On 810611,during Routine Surveillance Testing,Reactor High Pressure Switches for Isolating RHR Shutdown Cooling Suction Valves Were Found Above Tech Spec Limits.Caused by Setpoint Drift.Setpoints Reset to Proper Valve ML20030C2161981-06-10010 June 1981 RO 50-259/8130:on 810609,during Installation of New Interlock Sys,Power Supply Was Inadvertently Lifted on All Secondary Containment Door Interlocks.Caused by Personnel Error.Power Supply Restored ML20030C2491981-06-0202 June 1981 RO 50-259/8129:on 810601,during Surveillance Testing,Turbine Switches PS-1-81A & B & PS-1-91A & B Found Out of Tech Spec Limits by Max 13.8%.Caused by Setpoint Drift.Setpoints Reset.Design Change Request Initiated ML20030C0821981-05-28028 May 1981 RO 81-028/01P-0:on 810527,during Routine Surveillance Test, Turbine first-stage Permissive Switches PS-1-81A & B & PS-1-91A & B Were Found Above Tech Spec Limits.Caused by Setpoint Drift.Setpoints Reset to Proper Value ML20030C2611981-05-22022 May 1981 RO 50-259/8125:on 810521,main Steam Relief Valve Out Found of Tech Spec Limits.Cause Under Investigation.Affected Valves Will Be Disassembled for Insp Re Dimensional Tolerances & Thermal Properties of Base Matls ML20030C2421981-05-0707 May 1981 RO 50-296/8120:on 810507,NRC Inspector Identified That HPCI Should Have Been Declared Inoperable When HPCI Discharge Valve 73-44 Was Not Opened Per Procedures.Personnel Unaware of Procedure.Corrective Action Being Evaluated ML20030C2311981-05-0404 May 1981 RO 50-259/8116:on 810501,while Performing post-mod Testing on Newly Installed Sprinkler Sys,Auto Start Initiation Logic for Fire Pumps Found Inoperable.Caused by Lifting of Power Supply.Relay Panel Rewired & Auto Start Verified ML20030C0741981-04-27027 April 1981 Ro:On 810425,requirements for MSIV High Temp Isolation Were Not Met.Isolation Logic Channels Jumpered & Rendered Inoperable.Caused by Personnel Error.Jumper Removed. Investigation Ongoing ML20010B8631981-03-0505 March 1981 RO 50-259/81-09:on 810304,during Evaluation of IE Info Notice 80-45,mode Selector Switch Had Same Deficiency Identified in Notice.Apparently Caused by Circuitry Design Deficiency.Procedure Revisions Will Be Made 1998-12-31
[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
ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With 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
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 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 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-1999-002-02, :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-1999-001-05, :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-1999-003-02, :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 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 ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With 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 ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr 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 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 ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr ML18039A7271999-03-11011 March 1999 Safety Evaluation Supporting Amend 258 to License DPR-52 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
05000259/LER-1999-001-01, :on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With1999-02-12012 February 1999
- on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With
1999-09-30
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