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Category:Code Relief or Alternative
MONTHYEARML23150A0802023-05-30030 May 2023 Acceptance Review - Vogtle Units 1 and 2 - Proposed LAR and Relief Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23095A2962023-04-14014 April 2023 Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds (Vegp 3&4-Isi1- Alt-17) ML22259A1822022-09-22022 September 2022 Request for Proposed Inservice Testing Alternative ALT-VR-01 ML22118A0762022-05-13013 May 2022 Cover Letter for Vogtle Electric Generating Plant, Units 3 and 4 Request for Alternative Requirements for Inservice Test Interval Code Edition (VEGP 3&4-IST-ALT-01R2) ML22021A0012022-01-24024 January 2022 Relief Request for Proposed Alternative Requirements for the Repair of Reactor Vessel Head Penetrations for the Fourth 10-Year Inservice Inspection Interval, VEGP-ISI-ALT-04-05, Version 1.0 ML21154A2122021-06-0303 June 2021 Enclosure 1 - Vogtle Electric Generating Plant (VEGP) Unit 3 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1): Alternative Requirements for ASME Section III Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16) ML21154A2132021-06-0303 June 2021 Enclosure 2 - Vogtle Electric Generating Plant (VEGP) Unit 3 CB&I Procedure Qualification Record 14162(VEGP 3-ALT-16) ND-21-0392, Enclosure 3 - Vogtle Electric Generating Plant (VEGP) Unit 3 CB&I Procedure Qualification Record 14163 (VEGP 3-ALT-16)2021-06-0303 June 2021 Enclosure 3 - Vogtle Electric Generating Plant (VEGP) Unit 3 CB&I Procedure Qualification Record 14163 (VEGP 3-ALT-16) ML21040A1652021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2): Alternative Requirements for ASME Section XI Examination Coverage of Weldolet Branch Connection Welds ML20352A1552021-01-11011 January 2021 Proposed Relief Request for Alternative VEGP-ISI-ALT-04-04 to the Requirements of the ASME Code ML20307A1412020-11-12012 November 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal NL-20-1262, Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion2020-10-30030 October 2020 Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion ML20216A3992020-08-0606 August 2020 Relief Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20143A2332020-06-0303 June 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal (EPID L-2020-LLR-0074 (COVID-19)) ML20132A1532020-05-14014 May 2020 ASME Code Alternative - May 14, 2020 Presubmittal Technical Exchange for Preservice Inspection (PSI) Alternative ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ND-20-0083, Revision to Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01R1)2020-02-0606 February 2020 Revision to Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01R1) ND-19-1294, Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01)2019-10-31031 October 2019 Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01) ML18320A0192018-11-30030 November 2018 Relief Request Regarding Examination Coverage for Certain ASME Code Class 2 Category Welds (VEGP-ISI-RR-05) ML18296A7172018-10-31031 October 2018 Relief Request Regarding Examination Coverage for Certain Pressurizer and Steam Generator Welds (VEGP-ISI-RR-03) ND-18-1158, Revision to Request for Alternative: Alternative Requirements for Preservice Examination Volumetric Surface Configuration Requirements (VEGP 3&4-PSI/ISI-ALT-10R1)2018-08-30030 August 2018 Revision to Request for Alternative: Alternative Requirements for Preservice Examination Volumetric Surface Configuration Requirements (VEGP 3&4-PSI/ISI-ALT-10R1) NL-18-0428, Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-12018-04-0909 April 2018 Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-1 ML18054A0652018-03-0505 March 2018 Cover Letter - Vogtle Electric Generating Plant - Request for Alternative (ALT-9) ML17171A1022017-06-27027 June 2017 Inservice Inspection Alternative Regarding Category B-N-2 and B-N-3 Welds (VEGP ISI ALT 13) ML17061A2022017-03-17017 March 2017 Request for Alternative RR-PR-03 Regarding Nuclear Service Cooling Water Pump Instrument Accuracy ML17037D0502017-02-17017 February 2017 and 2; Request to Use Asme Code Case OMN-18 as an Alternative to Inservice Testing Requirements (CAC Nos. MF8188 and MF8189) NL-17-0101, Proposed Alternative VEGP-ISI-AL T-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend B-N-2 and B-N-3 Inservice Inspection Examinations Schedule2017-01-26026 January 2017 Proposed Alternative VEGP-ISI-AL T-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend B-N-2 and B-N-3 Inservice Inspection Examinations Schedule ML17006A1092017-01-26026 January 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads Inflange Inspection ML16326A0442016-12-0808 December 2016 Alternative for Pump and Valve Inservice Testing Program ML16264A3212016-10-14014 October 2016 Alternatives for Pumps and Valves Inservice Testing Program ML14030A5702014-03-20020 March 2014 Request for Alternatives VEGP-ISI-ALT-06 ML13123A1602013-05-0707 May 2013 (VEGP) - Safety Evaluation of Relief Request VEGP-ISI-ALT-09, Version 2.0, Regarding Leakage Tests for Reactor Coolant Pressure Boundary Components ML13032A1062013-02-0707 February 2013 Safety Evaluation of Relief Request VEGP-ISI-ALT-08, Version 1, Regarding Installation of a Mechanical Clamp on a Class 1 Valve - Fourth 10-Year Interval ML1009001292010-06-11011 June 2010 Relief Requests VEGP-ISI-ALT-04 (Units 1 and 2) and VEGP-ISI-RR-01 (Unit 2) Inservice Inspection Alternatives for Third and Subsequent Inservice Inspection Intervals (TAC Nos. ME2226, ME2227, and ME1134) ML1012000882010-04-30030 April 2010 Acceptance of Vogtle Relief Request (VEGP-ISI-ALT-03) Dated April 7, 2010 NL-09-1410, VEGP-ISI-RR-01, Version 1.0, Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)2009-09-0909 September 2009 VEGP-ISI-RR-01, Version 1.0, Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii) ML0731004352007-11-15015 November 2007 Third 10-Year Interval, Inservice Program Relief Request RR-V-1 (Tac Nos. MD5409 and MD5410) ML0627703592006-09-29029 September 2006 Evaluation of Relief Request ISI-GEN-ALT-06-02 NL-06-1713, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays2006-08-10010 August 2006 Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays ML0510301992005-04-25025 April 2005 RR, ISI Program Intervals for Alternative Alignment of Iwe/Iwl Inspection Program (Tac No. MC4870, MC4871, MC4872, MC4873, MC4874, MC4875) ML0332800372003-11-21021 November 2003 Safety Evaluation Re. Request to Use ASME Code Case N-661 ML0225904572002-09-16016 September 2002 Code Relief, Relief Request for the Second Ten-Year Interval Inservice Testing Program 2023-05-30
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-22-0778, Refueling Outage 2R22 Steam Generator Tube Inspection Report2022-09-30030 September 2022 Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-22-0512, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R222022-07-0101 July 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R22 ML22180A2612022-06-29029 June 2022 Proposed Inservice Testing Alterative ALT-VR-01 ND-22-0254, Submittal of Inservice Testing Program Plan - 1st Interval, Version 2.02022-04-0707 April 2022 Submittal of Inservice Testing Program Plan - 1st Interval, Version 2.0 ND-22-0253, Submittal of Preservice Test Plan - Version 4.02022-04-0707 April 2022 Submittal of Preservice Test Plan - Version 4.0 NL-22-0227, Refueling Outage 1R23 Steam Generator Tube Inspection Report2022-04-0101 April 2022 Refueling Outage 1R23 Steam Generator Tube Inspection Report NL-21-1130, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1 R232022-01-0303 January 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1 R23 NL-21-0767, Proposed Alternative Requirements for the Repair of Reactor Vessel Head Penetrations for the 4th 10-Year Inservice Inspection Internal (VEGP-ISI-ALT-04-05, Version 1.0)2021-09-10010 September 2021 Proposed Alternative Requirements for the Repair of Reactor Vessel Head Penetrations for the 4th 10-Year Inservice Inspection Internal (VEGP-ISI-ALT-04-05, Version 1.0) NL-21-0381, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R212021-04-26026 April 2021 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R21 NL-20-1312, Response to Request for Additional Information Related to Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.02020-11-23023 November 2020 Response to Request for Additional Information Related to Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.0 NL-20-1329, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1 R222020-11-23023 November 2020 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1 R22 NL-20-1086, Refueling Outage 1R22 Steam Generator Tube Inspection Report2020-09-17017 September 2020 Refueling Outage 1R22 Steam Generator Tube Inspection Report NL-20-1011, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.02020-09-0909 September 2020 Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.0 ND-20-0645, Submittal of Preservice Test Plan - Version 3.02020-06-0303 June 2020 Submittal of Preservice Test Plan - Version 3.0 ND-20-0601, Submittal of Inservice Testing Program Plan - 1st Interval2020-05-21021 May 2020 Submittal of Inservice Testing Program Plan - 1st Interval ND-19-1416, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report2019-12-0909 December 2019 Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report NL-19-1094, Refueling Outage 2R20 Steam Generator Tube Inspection Report2019-09-10010 September 2019 Refueling Outage 2R20 Steam Generator Tube Inspection Report ND-19-0747, Preservice Test Plan, Version 2.02019-07-24024 July 2019 Preservice Test Plan, Version 2.0 NL-19-0712, Submittal of Inservice Inspection Program Owner'S Activity Report for Outage 2R202019-06-26026 June 2019 Submittal of Inservice Inspection Program Owner'S Activity Report for Outage 2R20 NL-19-0204, R21 Steam Generator Tube Inspection Report2019-03-21021 March 2019 R21 Steam Generator Tube Inspection Report NL-18-1571, Proposed ISI Alternative VEGP-ISI-ALT-19-01 for Tendon Inservice Inspection Extension2019-02-18018 February 2019 Proposed ISI Alternative VEGP-ISI-ALT-19-01 for Tendon Inservice Inspection Extension NL-18-1565, Inservice Inspection Program Owner'S Activity Report for Outage 1R212019-01-0303 January 2019 Inservice Inspection Program Owner'S Activity Report for Outage 1R21 ND-18-1504, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report2018-12-0707 December 2018 Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report ND-18-1401, Request for Alternative: Alternative Requirements for Preservice Testing of Explosively Actuated Valves (VEGP 3&4-PST-Alt-01)2018-11-29029 November 2018 Request for Alternative: Alternative Requirements for Preservice Testing of Explosively Actuated Valves (VEGP 3&4-PST-Alt-01) ND-18-1185, Request for Alternative: Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI/ISI-ALT-06)2018-10-19019 October 2018 Request for Alternative: Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI/ISI-ALT-06) ND-18-1014, Request for Alternative: Alternative Requirements for Preservice Examination Volumetric Surface Configuration Requirements (VEGP 3&4 - PSI/ISI-ALT-10)2018-07-26026 July 2018 Request for Alternative: Alternative Requirements for Preservice Examination Volumetric Surface Configuration Requirements (VEGP 3&4 - PSI/ISI-ALT-10) NL-17-2128, Inservice Inspection Program Owner'S Activity Report for Outage 2R192017-12-21021 December 2017 Inservice Inspection Program Owner'S Activity Report for Outage 2R19 NL-17-1197, Fourth Ten-Year Interval Lnservice Testing Program Update2017-10-23023 October 2017 Fourth Ten-Year Interval Lnservice Testing Program Update NL-17-1641, Submittal of 1R20 Steam Generator Tube Inspection Report2017-09-27027 September 2017 Submittal of 1R20 Steam Generator Tube Inspection Report NL-17-1157, Transmittal of 1R20 ISI Report Summary2017-06-30030 June 2017 Transmittal of 1R20 ISI Report Summary NL-17-0659, Response to Request for Additional Information Re VEGP-ISI-ALT-13 Category B-N-2 and B-N-3 Examination Extension from 10 to 20 Years2017-04-20020 April 2017 Response to Request for Additional Information Re VEGP-ISI-ALT-13 Category B-N-2 and B-N-3 Examination Extension from 10 to 20 Years NL-17-0101, Proposed Alternative VEGP-ISI-AL T-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend B-N-2 and B-N-3 Inservice Inspection Examinations Schedule2017-01-26026 January 2017 Proposed Alternative VEGP-ISI-AL T-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend B-N-2 and B-N-3 Inservice Inspection Examinations Schedule NL-16-1609, Refueling Outage 2R18 Steam Generator Tube Inspection Report2016-09-13013 September 2016 Refueling Outage 2R18 Steam Generator Tube Inspection Report NL-16-1329, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.02016-08-0404 August 2016 Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.0 NL-16-1242, Submittal of the Inservice Testing Program Relief Request and Alternatives for Pumps and Valves - Fourth Ten-Year Interval2016-07-28028 July 2016 Submittal of the Inservice Testing Program Relief Request and Alternatives for Pumps and Valves - Fourth Ten-Year Interval NL-16-0927, 2R18 Lnservice Inspection Report Summary2016-06-27027 June 2016 2R18 Lnservice Inspection Report Summary NL-16-0081, Submittal of 1R19 Inservice Inspection Report Summary2016-01-20020 January 2016 Submittal of 1R19 Inservice Inspection Report Summary NL-15-0058, 2R17 Inservice Inspection Report Summary2015-01-12012 January 2015 2R17 Inservice Inspection Report Summary NL-14-1276, Snubber Inspection Plan Submittal in Accordance with ASME OM Code2014-10-31031 October 2014 Snubber Inspection Plan Submittal in Accordance with ASME OM Code NL-14-1081, R18 Inservice Inspection Report Summary2014-07-11011 July 2014 R18 Inservice Inspection Report Summary NL-13-2036, Sixteenth Maintenance / Refueling Outage Steam Generator Tube Inspection Report2013-09-26026 September 2013 Sixteenth Maintenance / Refueling Outage Steam Generator Tube Inspection Report ML13184A2692013-07-0202 July 2013 R16 Inservice Inspection Report Summary NL-13-0090, 1R17 Inservice Inspection Report Summary2013-01-16016 January 2013 1R17 Inservice Inspection Report Summary ML12314A4192012-11-15015 November 2012 Review of the 2011 Steam Generator Tube Inservice Inspection Report ML12249A1932012-09-11011 September 2012 Review of the 2011 Refueling Outage Steam Generators Tube Inservice Inspection Report NL-12-0067, Unit 2 - 2R15 Inservice Inspection Report Summary2012-01-10010 January 2012 Unit 2 - 2R15 Inservice Inspection Report Summary 2024-01-29
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
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A Southern Nuclear Charles R. Pierce Regulatory Affairs Director 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 7872 tel 205 992 7601 fax crpierce@southernco.com JAN 2 6 2017 Docket Nos.: 50-424 NL-17-0101 50-425 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant, Units 1 and 2 Proposed Alternative VEGP-ISI-ALT-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend 8-N-2 and 8-N-3 lnservice Inspection Examinations Schedule Ladies and Gentlemen:
In accordance with the provisions of 10 CFR 50.55a(z)(2), Southern Nuclear Operating Company (SNC) hereby requests Nuclear Regulatory Commission (NRC) approval of Vogtle Electric Generating Plant (VEGP) Alternative VEGP-ISI-ALT-13. This Alternative requests an extension of the Third Inspection Interval for VEGP Unit 1 and Unit 2 Category 8-N-2 and 8-N-3 examinations (visual examinations of the reactor vessel interior attachments beyond the beltline region and the core support structure) from 10 to 20 years. As part of this alternative, if there is an opportunity to perform examinations due to removal of the core barrel from the reactor vessel prior to the next scheduled Category 8-A and 8-D weld examinations, the code required VT-3 examinations will be performed on the core support structure and interior reactor vessel attachments in order to fulfill the exam requirements for the extended interval.
To allow the finalization of the work activities and associated outage planning and preparation needed to prepare for 2R19, NRC approval is requested by August 1, 2017.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.
Rc~~it!
C. A. Pierce Regulatory Affairs Director CRP/RMJ
Enclosure:
Alternative VEGP-ISI-ALT-13
U.S. Nuclear Regulatory Commission NL-17-0101 Page2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. D. R. Madison, Vice President- Fleet Operations Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. B. J. Adams, Vice President - Engineering Mr. D. D. Sutton, Regulatory Affairs Manager- Vogtle 1 & 2 RType: CVC7000 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manager- Vogtle 1 & 2 Mr. M. F. Endress, Senior Resident Inspector- Vogtle 1 & 2
Vogtle Electric Generating Plant, Units 1 and 2 Proposed Alternative VEGP-ISI-ALT-13 in Accordance with 10 CFR 50.55a(z)(2) to Extend B-N-2 and B-N-3 lnservice Inspection Examinations Schedule Enclosure Alternative VEGP-ISI-ALT-13
Enclosure to NL-17-0101 Alternative VEGP-ISI-ALT-13 Plant Site - Unit:
Vogtle Electric Generating Plant (VEGP) - Units 1 and 2 Interval-Interval Dates:
Third Inspection Interval, May 31, 2007 through May 30, 2017 Requested Date for Approval and Basis:
Approval is requested by August 1, 2017 for an extension of the Third Inspection Interval for VEGP Unit 1 and Unit 2, Category B-N-2 and B-N-3 examinations from 10 to 20 years. The VEGP- Unit 2 191h Refueling Outage {2R19) is scheduled to start in September of 2017. The requested approval date of August 1, 2017 is needed to allow the finalization of the work activities and associated outage planning and preparation needed to prepare for Refueling Outage 2R19.
ASME Code Components Affected:
The affected components are the reactor vessel interior attachments beyond the beltline region and the core support structure at VEGP- Units 1 and 2. The identified examinations are the ASME Code,Section XI, Examination Category B-N-2 and B-N-3, Item Numbers 813.60 and B13.70 examinations.
Examination Item Category No. Description B-N-2 813.60 Interior Attachments Beyond Beltline Region B-N-3 813.70 Removable Core Support Structures VEGP - Unit 1 Components:
Component ID Description 11201-V6-001-W41 Core Support Lug at 0 Degrees 11201-V6-001-W42 Core Support Lug at 60 Degrees 11201-V6-001-W43 Core Support Lug at 120 Degrees 11201-V6-001-W44 Core Support Lug at 180 Degrees 11201-V6-001-W45 Core Support Lug at 240 Degrees 11201-V6-001-W46 Core Support Lug at 300 Degrees 11201-V6-001-CSS-01 Core Support Structure VEGP- Unit 2 Components:
Component ID Description 21201-V6-001-W41 Core Support Lug at 0 Degrees 21201-V6-001-W42 Core Support Lug at 60 Degrees 21201-V6-001-W43 Core Support Lug at 120 Degrees 21201-V6-001-W44 Core Support Lug at 180 Degrees 21201-V6-001-W45 Core Support Lug at 240 Degrees 21201-V6-001-W46 Core Support Lug at 300 Degrees 21201-V6-001-CSS-01 Core Support Structure E-1
Enclosure to NL-17-01 01 Alternative VEGP-ISI-ALT-13
Applicable Code Edition and Addenda
The applicable Code edition and addenda is ASME Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," 2001 Edition with Addenda through 2003.
Applicable Code Requirements:
IW8-2412, Inspection Program 8, requires visual examination of the reactor vessel interior attachments and core support structure identified in Table IW8-2500-1, Examination Categories 8-N-2 and 8-N-3, to be performed once each inspection interval. The VEGP - Unit 1 and 2 Third Inspection interval is currently scheduled to conclude on May 30, 2017.
IWA-2430(d)(1) allows the inspection interval to be reduced or extended by as much as one year therefore the existing Code allows the inspection interval to be extended to May 30, 2018.
Approval is requested to extend the duration of the Third Inspection Interval for Examination Categories 8-N-2 and 8-N-3, Item Numbers 813.60 and 813.70, visual examinations from 10 to 20 years. Please note that the NRC granted a five-month deferral of the required Unit 1 examinations on November 23, 2016, such that these examinations are now scheduled to be performed during 1R21 (fall 2018).
Background and Reason for Request:
IW8-2412, Inspection Program 8, requires that the visual examinations of the reactor vessel interior attachments and the core support structure, required by Examination Categories 8-N-2 and 8-N-3, be performed once every inspection interval. These visual examinations are typically performed at the end of the interval with the core barrel removed with the reactor vessel volumetric examinations of Category 8-A and 8-D welds. However, Southern Nuclear Operating Company (SNC) has previously submitted and received approval to extend examination of the reactor vessel Category 8-A and 8-D welds from 10 years to 20 years for VEGP- Units 1 and 2. As a result, VEGP has no other requirements or activities that require removing the core barrel prior to next Category 8-A and 8-D weld examinations except for the Category 8-N-2 and 8-N-3 visual examinations. Correspondence related to the extension of the Category 8-A and 8-D weld examinations is contained in SNC letters dated August 29, 2012, November 25, 2013, and January 31, 2014 (Agency Document Access and Management System (ADAMS) Accession Numbers ML12243A248, ML13329A494, and ML14031A429 respectively) and in Nuclear Regulatory Commission letter dated March 20, 2014 (ADAMS Accession Number ML14030A570).
Examination Category 8-N-2 and 8-N-3 visual examinations require removal of the core barrel from the reactor vessel to gain access to the reactor vessel interior attachments and the core support structure. The core barrel is restrained at the bottom by the clevis inserts/support lugs with a close tolerance fit to the corresponding core barrel radial keys. To remove and reinstall the core barrel requires implementation of detailed planning and precision lifts to ensure that the core barrel and/or reactor vessel are not damaged. In addition, the core barrel is extremely radioactive which adds to the complexity when lifting the core barrel in and out of the reactor vessel. The removal and reinstallation of the core barrel and the performance of the category 8-N-2 and 8-N-3 visual examinations are performed with all fuel removed from the reactor vessel.
Performing these Examination Category 8-N-2 and 8-N-3 visual examinations and the Examination Category 8-A and 8-D examinations during the same refueling outage results in E-2
Enclosure to NL-17-0101 Alternative VEGP-ISI-ALT-13 significant savings in outage duration since the same equipment and personnel used for examination of the reactor pressure vessel shell, lower head, and nozzle welds from the reactor pressure vessel interior can implement the examinations of reactor pressure vessel interior attachment welds and core support structure surfaces. Additionally, removing the reactor pressure vessel internals once instead of twice during the proposed 20-year inspection interval to perform these related examinations would result in significant savings in radiation exposure and the avoidance of an infrequently performed lift of a heavy, close fit component that has some potential for inflicting damage to itself, reactor vessel surfaces, and refueling floor structures/liners for the sole purpose of performing the 8-N-2 and 8-N-3 visual examinations.
Proposed Alternative and Basis for Use:
SNC proposes to extend the Third Inspection Interval for the category B-N-2 interior attachment welds beyond the reactor vessel beltline region and the category 8-N-3 reactor vessel core support structure surfaces to coincide with the end of the Fourth Inspection Interval which is scheduled to be May 30, 2027. Pending approval of this proposed alternative, the proposed alternative inspection would enable the subject examinations to be performed with the risk-informed extension of the inservice inspection interval for category B-A reactor vessel pressure-retaining welds and category 8-D nozzle-to-vessel and inner radius section welds.
The visual examinations of the reactor vessel interior attachments and the core support structure have been performed twice per unit at VEGP. No relevant indications were noted during the First Inspection Interval for the category 8-N-2 and B-N-3 examinations on either VEGP unit. No relevant indications were noted during the Second Inspection Interval for the category 8-N-2 and 8-N-3 examinations on Unit 2. Indications were noted in the Second Inspection Interval for the category 8-N-2 and B-N-3 examinations during Unit 1 Refueling Outage 1R 13 in 2006.
During the Second Inspection Interval visual examinations on Unit 1 in Refueling Outage 1R 13 in 2006 a thin object of approximately 0.375 inch length was observed to be adhered to the bottom surface, on the right-hand side, of the upper core plate clevis insert at the 90-degree location. The foreign object was dislodged in one piece and some slightly disrupted material was noticed on the outside bottom edge of the clevis insert. In addition, a similar indication was observed on the corresponding area on the left-hand side of the same clevis insert.
Corresponding slightly disrupted material was observed on the core barrel on both sides of the clevis which matched the locations on the upper core plate clevis insert. These indications were clearly not service related and in fact likely due to core barrel/reactor vessel close fit tolerance for removal and insertion as discussed above. The indications were assessed and determined not to affect the structural integrity of the reactor internals.
SNC personnel actively participate in key industry groups such as Nuclear Energy Institute, PWR Materials Reliability Program (MRP), and the PWR Owner's Group (PWROG)
Subcommittee associated with PWR reactor vessel internals to assess industry operating experience for applicability to VEGP - Units 1 and 2. Two aging management issues are currently a challenge for PWR reactor internals. The two issues are: (1) reactor internals lower support clevis cap screw degradation, and (2) baffle-to-former bolting degradation.
Reactor internals lower support clevis cap screw degradation was discovered at one United States Westinghouse NSSS plant. The industry sponsored evaluations and assessments, documented in a proprietary PWROG report show that the ability of the lower radial support system to perform its intended safety function is unrelated to the integrity of the cap screws E-3
Enclosure to NL-17-0101 Alternative VEGP-ISI-ALT-13 used to hold the clevis insert in place. That is, failure of a cap screw is not expected to result in the complete failure of the lower radial support system. A series of cascading failures would need to occur prior to the safety functions becoming potentially affected.
The VEGP Unit 1 and Unit 2 reactors contain six core support lugs fabricated from Alloy 600 base material which are attached to the RPV wall with alloy 82/132/182 welds. The inlay pad is alloy 82 material, the attachment weld is 132/82, and a lug tie-in weld is alloy 182. The finished lugs and attachment welds received post-weld heat treatment with the entire reactor vessel at the fabricator (Combustion Engineering), which relieves the stresses from the welding operation. SNC is unaware of any industry operating experiencing (OE) related to primary water stress corrosion cracking for similar vessel attachment welds.
The VEGP Unit 1 and Unit 2 six core support lug locations described above have one-piece Alloy 600 (S8-166) clevis inserts interference fit and fastened to the lugs with eight S8-637 Grade 688, type 2 (alloy X-750) cap screws and two alloy 600 dowel pins.
Degradation of baffle-to-former bolting in the United Sates has been limited to downflow reactor designs with Type 347 bolts. VEGP- Units 1 and 2 are standard upflow reactor designs with Type 316 strain-hardened bolts which based on industry assessment of the operating experience are considered the least susceptible (tier 4) plant designs to have baffle-to-former bolting d~gradation. Although the susceptibility assessment clearly indicates a low potential for VEGP, detection of degradation similar to the recent operating experience does not require removal of the core barrel in unlikely event of occurrence.
WCAP-17435-NP, Revision 1, "Results of the Reactor Internals Operating Experience Survey Conducted under PWROG Project Authorization PA-MSC-0568," dated March 15, 2013, for information, indicated no inspection indications for the Category 8-N-2 and 8-N-3 components for the domestic fleet of RPVs.
As part of this alternative, if there is an opportunity to perform examinations due to removal of the core barrel from the reactor vessel prior to the next scheduled Category 8-A and 8-D weld examinations, the code required VT-3 examinations will be performed on the core support structure and interior reactor vessel attachments in order to fulfill the exam requirements for the extended interval.
Therefore, in accordance with 10CFR50.55a(z)(2), SNC requests approval to extend the Third Inspection Interval to May 30, 2027 for category 8-N-2 and 8-N-3 visual examinations because removal of the core barrel for the sole purpose of performing visual examinations results in a "hardship without a compensating increase in the level of quality or safety.
Duration of Proposed Alternative:
The proposed alternative would extend the duration of the Third Inspection Interval for Examination Categories 8-N-2 and 8-N-3, Item Numbers 813.60 and 813.70, visual examinations to May 30, 2027.
This extension will not affect the start of the Fourth Inspection Interval so it will not impact the overall schedule of other VEGP's lSI examinations.
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Enclosure to NL-17-0101 Alternative VEGP-ISI-ALT-13 Precedent:
First Energy Nuclear Operating Company submitted a similar request for Beaver Valley Power Station, Unit No. 2, proposing that the visual examinations for Category B-N-2 and B-N-3 components be performed consistent with the proposed inspection interval for Category B-A and B-D volumetric examinations. By letter dated December 27, 2016 (ADAMS Accession Number ML16190A133), the NRC staff authorized use of the alternative.
Status:
A similar request was approved by the NRC staff for Beaver Valley Power Station Unit 2 by letter dated December 27, 2016 (ADAMS Accession Number ML16190A133).
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