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 Issue dateTitleTopic
ML18039A90415 October 1999LER 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
ML18039A89814 October 1999LER 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
ML18039A8958 October 1999LER 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 InstructionsFuel cladding
ML20212J6311 October 1999SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1Incorporated by reference
ML20217G37230 September 1999Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With
ML18039A87530 September 1999LER 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 LtrMissed surveillance
ML20217F96730 September 1999Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML20212F47623 September 1999Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively
ML20212E63423 September 1999Suppl 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
ML20212F08323 September 1999Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI IntervalSafe Shutdown
VT-2
Incorporated by reference
ML20212D38320 September 1999Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV
ML20212C47631 August 1999Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With
ML18039A88231 August 1999Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept.Probabilistic Risk Assessment
Significance Determination Process
Design basis earthquake
Large early release frequency
Earthquake
Hardened vent
ML20212B85631 August 1999Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With
ML18039A8396 August 1999BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts.Hydrostatic
Coatings
Nondestructive Examination
VT-2
Moisture barrier
Liquid penetrant
Dissimilar Metal Weld
ML20210N1222 August 1999Safety 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 3Nondestructive Examination
Incorporated by reference
ML20210L4362 August 1999Cycle 9 12-Month SG Insp Rept
ML20216E37831 July 1999Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20210L44531 July 1999Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20210R09331 July 1999Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML20210G66328 July 1999Cycle 9 90-Day ISI Summary Rept
ML18039A82026 July 1999LER 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
ML18039A81720 July 1999LER 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 LtrMissed surveillance
ML18039A81619 July 1999LER 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 LtrAbnormal operational transient
Corrosion bonding
ML20209J07716 July 1999Safety 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 ExistFire Barrier
ML18039A81212 July 1999LER 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 LtrFuel cladding
ML20196H86230 June 1999NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 ReptHigh Radiation Area
Power change
ML20209H43830 June 1999Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML20209H38330 June 1999Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With
ML20211F90330 June 1999Cycle 9 Refueling Outage
ML20196J85228 June 1999Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i)Non-Destructive Examination
Incorporated by reference
ML18039A81028 June 1999LER 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 ResetHalf scram
ML20196F88123 June 1999Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate ValvesBackfit
ML18039A80714 June 1999LER 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
ML18039A80214 June 1999LER 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
ML18039A80114 June 1999LER 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
ML20195K29531 May 1999Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20196B80531 May 1999Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML18039A7796 May 1999LER 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 TightenedFuel cladding
ML20206Q8955 May 1999Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10
ML20206R50330 April 1999Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With
ML18039A77630 April 1999Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3.
ML20206R07330 April 1999Monthly Operating Repts for Apr 1999 for Bfnp.With
ML18039A75623 April 1999Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal.Safe Shutdown
Non-Destructive Examination
Mission time
VT-2
Large early release frequency
Maintenance Rule Program
Fuel cladding
ML18039A7678 April 1999Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr.Shutdown Margin
ML18039A7467 April 1999LER 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
ML20205N8341 April 1999Part 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
ML20205F9341 April 1999Safety 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
ML20205S06031 March 1999Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331Fuel cladding
ML20205P98131 March 1999Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
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