05000260/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