Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20212A1841999-08-25025 August 1999
Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program
ML20211A2021999-01-31031 January 1999
Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections
ML20237A4411998-07-31031 July 1998
Blended Uranium Lead Test Assembly Design Rept
ML20101N7441996-03-31031 March 1996
Nonproprietary TR, Mark-BW Fuel Assembly Application for Sequoyah Nuclear Units 1 & 2
ML20117D3201995-09-30030 September 1995
Rev 1 to Containment Integrity Analyses for Ice Weight Optimization Engineering Rept
ML20078A7301994-05-31031 May 1994
Nonproprietary Sequoyah Units 1 & 2 SG Tube Plugging Criteria for Indications at Tube Support Plates
ML20045D7281993-04-30030 April 1993
Nonproprietary WCAP-13650, Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Sequoyah Nuclear Plants.
ML20127N5621992-11-30030 November 1992
Nonproprietary Sequoyah Units 1 & 2 W* Tube Plugging Criteria for SG Tubesheet Region of Wextex Expansions
ML20082S8361991-06-30030 June 1991
Heatup & Cooldown Limit Curves for Normal Operation, Sequoyah Unit 2
ML20082S8331991-06-30030 June 1991
Heatup & Cooldown Limit Curves for Normal Operation, Sequoyah Unit 1
ML20042G1451990-04-30030 April 1990
Eagle 21 Process Protection Sys Replacement Hardware Verification & Validation Final Rept
ML20042G1021990-03-30030 March 1990
Nonproprietary Summary Rept Process Protection Sys Eagle 21 Upgrade,Rtd Bypass Elimination,New Steam Line Break Sys, Medical Signal Selector,Environ Allowance Modifier & Trip Time Delay Implementation.
ML20042G0481990-02-28028 February 1990
Nonproprietary Rev 0 to WCAP-8587,Suppl 1 EQDP-ESE-69, Equipment Qualification Data Package,Eagle 21 Process Protection Sys (Environ & Seismic).
ML20012B3521989-10-31031 October 1989
Median Signal Selector for Foxboro Series Process Instrumentation.
ML20033E4411989-09-30030 September 1989
Nonproprietary Eagle-21 Microprocessor-Based Process Protection Sys
ML20246B6831989-06-30030 June 1989
Unit 2 Evaluation for Tube Vibration Induced Fatigue
ML20042G0491988-07-31031 July 1988
Nonproprietary WCAP-11896, Noise,Fault,Surge & Radio Frequency Interference Test Rept for Westinghouse Eagle 21 Process Protection Upgrade Sys
ML20205C2871987-01-31031 January 1987
Row 1 & Row 2 Heat Treatment for Sequoyah Units 1 & 2
ML20094B1081984-04-30030 April 1984
Analysis of Capsule T from TVA Sequoyah,Unit 2 Reactor Vessel Radiation Surveillance Program
ML20038C0191981-10-31031 October 1981
Nonproprietary Version of Clasix Computer Program for Analysis of Reactor Plant Containment Response to Hydrogen Release & Deflagration.
ML20027A7081972-11-0101 November 1972
Rev 1 to Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants
1999-08-25
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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
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
ML20212F4761999-09-23023 September 1999
Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively
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
ML20210L4451999-07-31031 July 1999
Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20216E3781999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20210G6631999-07-28028 July 1999
Cycle 9 90-Day ISI Summary Rept
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20211F9031999-06-30030 June 1999
Cycle 9 Refueling Outage
ML20209H3831999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With
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
ML20204C3111999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20205B6631999-02-28028 February 1999
Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
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
ML20196C4091998-11-19019 November 1998
Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively
ML20196B0231998-11-19019 November 1998
Safety Evaluation Supporting Amends 239 & 229 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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