Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217D2721999-10-12012 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
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
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)
ML20206G3751999-05-0404 May 1999
Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively
ML20205N0361999-04-12012 April 1999
Safety Evaluation Supporting Amend 234 to License DPR-79
ML20204E8211999-03-16016 March 1999
Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively
ML20206U4331999-02-0909 February 1999
Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively
ML20198C0211998-12-16016 December 1998
Safety Evaluation Supporting Amends 241 & 231 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
ML20196B0231998-11-19019 November 1998
Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively
ML20195G3271998-11-17017 November 1998
Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively
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
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
ML20236S4081998-07-0101 July 1998
Safety Evaluation Supporting Amends 233 & 223 to Licenses DPR-77 & DPR-79,respectively
ML20248L1961998-06-0808 June 1998
Safety Evaluation Supporting Amends 232 & 222 to Licenses DPR-77 & DPR-79,respectively
ML20217K4471998-04-27027 April 1998
Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05
ML20216E4701998-03-0909 March 1998
Safety Evaluation Approving Exemption from Updated FSAR Requirements of 10CFR50.71(e)(4) for Sequoyah Nuclear Plant,Units 1 & 2
ML20203K6811998-02-20020 February 1998
Safety Evaluation Supporting Amends 231 & 221 to Licenses DPR-77 & DPR-79,respectively
ML20198P9171998-01-13013 January 1998
Safety Evaluation Supporting Amend 230 to License DPR-77
ML20217D7881997-09-29029 September 1997
Safety Evaluation Supporting Amends 229 & 220 to Licenses DPR-77 & DPR-79,respectively
ML20211G2061997-09-23023 September 1997
Safety Evaluation Supporting Amends 228 & 219 to Licenses DPR-77 & DPR-79,respectively
ML20210J5951997-08-12012 August 1997
Safety Evaluation Supporting Amends 227 & 218 to Licenses DPR-77 & DPR-79,respectively
ML20151L7981997-07-14014 July 1997
Safety Evaluation Supporting Amends 226 & 217 to Licenses DPR-77 & DPR-79,respectively
ML20148S0581997-07-0101 July 1997
Safety Evaluation Supporting Amends 225 & 216 to Licenses DPR-77 & DPR-79,respectively
ML20140F0311997-06-10010 June 1997
Safety Evaluation Supporting Amends 224 & 215 to Licenses DPR-77 & DPR-79,respectively
ML20138D2581997-04-28028 April 1997
Safety Evaluation Authorizing Licensee Proposed Alternative to Use 1989 Edition of ASME Boiler & Pressure Vessel Code, Section XI for Performance of Containment Repair & Replacement Activities Until 970909
ML20137Y8911997-04-21021 April 1997
Safety Evaluation Supporting Amends 223 & 214 to Licenses DPR-77 & DPR-79,respectively
ML20101M5761996-04-0303 April 1996
Safety Evaluation Supporting Amend 211 to License DPR-79
ML20100N5711996-03-0404 March 1996
Safety Evaluation Supporting Amends 220 & 210 to Licenses DPR-77 & DPR-79,respectively
ML20097D4191996-02-0707 February 1996
Safety Evaluation Supporting Amends 218 & 208 to Licenses NPF-77 & NPF-79,respectively
ML20095F9891995-12-11011 December 1995
Safety Evaluation Supporting Amends 216 & 206 to Licenses DPR-77 & DPR-79,respectively
ML20094N5341995-11-21021 November 1995
Safety Evaluation Supporting Amends 215 & 205 to Licenses DPR-77 & DPR-79,respectively
ML20094D2451995-10-30030 October 1995
Safety Evaluation Supporting Amend 204 to License DPR-79
ML20093E1191995-10-11011 October 1995
Safety Evaluation Supporting Amend 214 to License DPR-77
ML20093B9471995-10-0404 October 1995
Safety Evaluation Supporting Amends 213 & 203 to Licenses DPR-77 & DPR-79,respectively
ML20092N0711995-10-0202 October 1995
Safety Evaluation Supporting Amends 212 & 202 to Licenses DPR-77 & DPR-79,respectively
ML20092H0811995-09-15015 September 1995
Safety Evaluation Supporting Amends 211 & 201 to Licenses DPR-77 & DPR-79,respectively
ML20092G7071995-09-13013 September 1995
Safety Evaluation Supporting Amends 210 & 200 to Licenses DPR-77 & DPR-79
ML20087L4671995-08-22022 August 1995
Safety Evaluation Supporting Amends 207 & 197 to Licenses DPR-77 & DPR-79,respectively
ML20086C2861995-06-29029 June 1995
Safety Evaluation Supporting Amends 205 & 195 to Licenses DPR-77 & DPR-79,respectively
ML20085G5811995-06-13013 June 1995
Safety Evaluation Supporting Amends 203 & 193 to Licenses DPR-77 & DPR-79,respectively
ML20085G5091995-06-13013 June 1995
Safety Evaluation Supporting Amends 202 & 192 to Licenses DPR-77 & DPR-79,respectively
ML20083L1931995-05-10010 May 1995
Safety Evaluation Supporting Amends 198 & 189 to Licenses DPR-77 & DPR-79,respectively
ML20087J3291995-04-28028 April 1995
Safety Evaluation Supporting Amends 197 & 188 to Licenses DPR-77 & DPR-79,respectively
ML20082E4291995-04-0404 April 1995
Safety Evaluation Supporting Amends 196 & 187 to Licenses DPR-77 & DPR-79,respectively
ML20078M8441995-02-0909 February 1995
Safety Evaluation Supporting Amends 195 & 186 to Licenses DPR-77 & DPR-79,respectively
1999-09-23
[Table view]
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
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 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
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
ML20199G3641998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With
ML20198S7301998-12-31031 December 1998
Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
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
ML20198C0211998-12-16016 December 1998
Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively
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
ML20195G3271998-11-17017 November 1998
Safety Evaluation Supporting Amends 237 & 227 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
1999-09-30
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