Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999
Cycle 9 12-Month SG Insp Rept
ML20210L4451999-07-31031 July 1999
Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20211F9031999-06-30030 June 1999
Cycle 9 Refueling Outage
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20205B6631999-02-28028 February 1999
Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
ML20198S7301998-12-31031 December 1998
Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20199J2571998-01-31031 January 1998
Cycle 9 Voltage-Based Repair Criteria 90-Day Rept
ML20199J2441998-01-29029 January 1998
Snp Unit 2 Cycle Refueling Outage Oct 1997
L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997
SG Secondary Side Loose Object Safety Evaluation
ML20203B9591997-09-18018 September 1997
Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn
ML20210J1761997-07-31031 July 1997
Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept
ML20138D1991997-04-0404 April 1997
Special Project97-928S, Sequoyah Nuclear Plant Assessments
ML20138C5371997-03-24024 March 1997
Rev 0 to Pressurizer Level Event
ML20217G2401997-03-0303 March 1997
Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow
ML20138P8611997-02-12012 February 1997
Response to Request for Info Re Adequacy & Availability of Design Bases Info
ML20117J3611996-08-0101 August 1996
SE of Safety Valve Setpoint Tolerance Relaxation
ML20117K9461996-03-0505 March 1996
Reliability Study
ML20117K9511996-02-29029 February 1996
Reliability Common Cause Assessment, for Feb 1996
ML20095J1891995-10-0505 October 1995
Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds
ML20081D3831995-03-12012 March 1995
Simulator Four Yr Test Rept for 950312
ML20083N9521994-11-16016 November 1994
10CFR50.59 Rept to Nrc
ML20024H8491993-07-19019 July 1993
Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles
ML20118D1941992-09-21021 September 1992
Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment
ML20114A6641992-08-15015 August 1992
920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period
ML20141M1341992-03-27027 March 1992
Spent Fuel Pool Mod for Increased Storage Capacity
ML20029C2011991-03-12012 March 1991
Initial Simulator Certification.
ML20028H8591990-09-0707 September 1990
Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues.
ML20136J0431990-06-30030 June 1990
Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks
ML20043B6061990-05-11011 May 1990
Diesel Generator Voltage Response Improvement Rept.
ML20006E5771990-02-0505 February 1990
Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis
ML20246D5351989-02-28028 February 1989
Steam Generator Tubing Insp Results
ML20247H1301988-11-30030 November 1988
Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns
ML20236D1951988-11-18018 November 1988
HVAC Damping Values
ML20134H6801988-09-0202 September 1988
Technical Evaluation of Procurement of Matls & Svcs
ML20245B4181988-08-17017 August 1988
Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water
ML20151Q2691988-08-0101 August 1988
Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping
ML20155J5721988-07-31031 July 1988
Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway
ML20207F6231988-07-0505 July 1988
Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2
ML20207B6301988-06-27027 June 1988
Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program
ML20147G9961988-03-31031 March 1988
Review of Operational Readiness Corrective Actions. Related Documentation Encl
ML20147H6331988-02-29029 February 1988
Plant,Diesel Generator Evaluation Rept
ML20147G8041988-02-25025 February 1988
Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs
ML20147G7861988-02-25025 February 1988
Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input
ML20234F2111988-01-0505 January 1988
Rept of Sequoyah Readiness Review
ML20195G8431987-12-0808 December 1987
Technical Evaluation Rept for Employee Concerns Element Rept 221.6(B), Rev 1, `Pipe Support Design,Observed Bending of Pipe Clamp Ears
ML20195G8371987-12-0606 December 1987
Technical Evaluation Rept for Employee Concerns Element Rept 218.4(b), Rev 2, `Pipe Stress Calculations,Wide Spread Deficiencies within Pipe Stress Calculations
ML20147F0581987-12-0202 December 1987
Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept
ML20127A6811987-11-30030 November 1987
Technical Evaluation Rept for Employee Concerns Element Rept 218.1(B),Rev 1, Pipe Stress Calculations,Thermal Analysis of Piping Subj to Temp Less than 120 F
ML20236B3481987-10-15015 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation
ML20236B3581987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector
1999-08-02
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Category:TEXT-SAFETY REPORT
MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
ML20217D2721999-10-12012 October 1999
Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively
ML20217B3651999-10-0606 October 1999
Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively
ML20212J6311999-10-0101 October 1999
SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1
ML20217G3721999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With
ML20212F4761999-09-23023 September 1999
Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively
ML20212F0831999-09-23023 September 1999
Safety 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 Interval
ML20212C4761999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With
ML20212A1841999-08-25025 August 1999
Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program
ML20210L4361999-08-0202 August 1999
Cycle 9 12-Month SG Insp Rept
ML20216E3781999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20210L4451999-07-31031 July 1999
Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20210G6631999-07-28028 July 1999
Cycle 9 90-Day ISI Summary Rept
ML20209H3831999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With
ML20211F9031999-06-30030 June 1999
Cycle 9 Refueling Outage
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20196J8521999-06-28028 June 1999
Safety 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)
ML20195K2951999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
ML20206Q8951999-05-0505 May 1999
Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10
ML20206G3751999-05-0404 May 1999
Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively
ML20206R5031999-04-30030 April 1999
Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With
ML20205N0361999-04-12012 April 1999
Safety Evaluation Supporting Amend 234 to License DPR-79
ML20205P9811999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20204E8211999-03-16016 March 1999
Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively
ML20205B6631999-02-28028 February 1999
Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
ML20204C3111999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20203H7381999-02-18018 February 1999
Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions
ML20206U4331999-02-0909 February 1999
Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively
ML20211A2021999-01-31031 January 1999
Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections
ML20198S7301998-12-31031 December 1998
Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20199G3641998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
ML20197J5621998-12-0303 December 1998
Unit 1 Cycle 9 90-Day ISI Summary Rept
ML20197K1161998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20196B0231998-11-19019 November 1998
Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively
ML20196C4091998-11-19019 November 1998
Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively
05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
ML20195F8061998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With
ML20154H6091998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
ML20154H6251998-09-17017 September 1998
Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr
ML20153B0881998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With
ML20238F2961998-08-28028 August 1998
Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively
ML20239A0631998-08-27027 August 1998
SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2
05000327/LER-1998-002-03, :on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance1998-08-14014 August 1998
- on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance
ML20236Y2091998-08-0707 August 1998
Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08
ML20237A4411998-07-31031 July 1998
Blended Uranium Lead Test Assembly Design Rept
1999-09-30
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