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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report NL-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-20-1329, 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-20-1312, 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-20-1086, 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 2024-07-03
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) NL-24-0170, Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report2024-04-25025 April 2024 Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report NL-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-23-0658, 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-23-0670, 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-23-0672, 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) 2024-07-03
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Text
Charles R.Pierce Southern Nuclear Regulatory Affairs.Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN COMPANY September 26, 2013 Docket Nos.: 50-425 NL-13-2036 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Unit 2 Sixteenth Maintenance / Refueling Outage Steam Generator Tube Inspection Reoort Ladies and Gentlemen:
In accordance with the requirements of Vogtle Electric Generating Plant Technical Specification 5.6.10, Southern Nuclear Operating Company submits this report of the steam generator tube inspections performed during the Unit 2 sixteenth maintenance / refueling outage (2R16). Entry into Mode 4 occurred on March 31, 2013.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted, C. R. Pierce Regulatory Affairs Director CRP/RMJ/Iac
Enclosure:
2R16 Steam Generator Tube Inspection Report cc: Southern Nuclear Operatinq Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. 0. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. E. Tynan, Vice President - Vogtle Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R, E. Martin, NRR Senior Project Manager - Vogtle Mr. L. M. Cain, Senior Resident Inspector - Vogtle A* (
Mr.uecAII &nRset
Vogtle Electric Generating Plant - Unit 2 Sixteenth Maintenance/ Refueling Outage Steam Generator Tube Inspection Report Enclosure 2R16 Steam Generator Tube Inspection Report
Enclosure to NL-13-2036 2R1 6 Steam Generator Tube Inspection Report Introduction The Vogtle 2R16 outage was conducted after cumulative steam generator (SG) service equivalent to approximately 21.3 effective full power years (EFPY); the Cycle 16 power generation was approximately 1.4 EFPY. Analyses, based on conservative assumptions used in the Condition Monitoring and Operational Assessments, demonstrated that there were no tubes that exceeded the Reg. Guide 1.121 or NEI-97-06 Revision 3 criteria for tube integrity during Cycle 16. The eddy current inspections were performed by the Steam Generator Maintenance Services Group of the Westinghouse Nuclear Services Division. Secondary data analysis was performed by NDE Technology under direct contract with Southern Nuclear. One tube (R56C82) in SG 3 was plugged due to 41% through wall (TW) anti-vibration bar (AVB) wear that exceeded the Technical Specifications (TS) plugging criteria. One tube (R15C60) was stabilized and plugged in SG 2 due to a single circumferential outer diameter stress corrosion crack (ODSCC) signal at the hot leg top of tubesheet. Criteria for in-situ testing were not met for either tube. Permanent H* Alternate Repair Criteria was approved by the NRC for implementation. Therefore, tube end +Point inspections below top of tubesheet (TTS) -15.2 inches were omitted, and the TTS inspections ranged from TTS +3 inches to TTS -15.2 inches.
2R16 SG Primary Side Base Scope The scope for 2R16 involved the scheduled inspections listed below. The inspection program, required by Revision 7 of the EPRI PWR SG Examination Guidelines, addressed the known degradation mechanisms observed in Vogtle Unit 2 in prior inspections, as well as those regarded as potential degradation mechanisms.
- 100% Bobbin examination of tubes in SGs 2 and 3 full length except for Rows 1 and 2, which are inspected from tube end to tube support plate (TSP) #7 from both hot leg (HL) and cold leg (CL).
- 100% +Point examination of Row 1 and Row 2 U-bends from the top TSP on the HL to the top TSP on the CL in SGs 2 and 3.
- +Point examination of Special Interest, HL and CL, of bobbin possible flaw locations including U-bends.
- 100% +Point examination at HL tubes in SGs 2 and 3 from TTS + 3 inches to the licensed Permanent Alternative Repair Criteria (ARC) depth for H* (tubesheet region on HL side (TSH) +3/-15.2 inches). This inspection captured the U-S BLG / OXP populations, as defined below, along with the required periodic sample specified in the regulatory approval of ARC.
- BLG = differential mix diameter discontinuity signal within the tubesheet of 18 volts or greater as measured by bobbin coil probe;
- OXP = a tube diameter deviation within the tubesheet of 1.5 mils or greater as measured by bobbin coil profile analysis.
0 100% +Point examination of total dents and dings > 2 volts in SGs 2 and 3 HL straight lengths and U-bends.
0 100% Visual inspection of tube plugs in SGs 2 and 3.
= Visual inspection in SGs 2 and 3 of channel head primary side HL and CL in accordance with Westinghouse Letter NSAL 12-1, "Steam Generator Channel Head Degradation".
E-1
Enclosure to NL-1 3-2036 2R16 Steam Generator Tube Inspection Report Inspection Expansion Based on the confirmation of a single indication of ODSCC at the HL tubesheet expansion transition in SG 2, an expansion of the eddy current program was conducted in SG l and 4 in accordance with the EPRI PWR SG Examination Guidelines. The following inspection scope listed below was conducted during 2R16 for SG 1 and SG 4:
- 20% +Point examination at HL tubes in SGs 1 and 4 from TTS +3 inches to the licensed Permanent ARC depth for H* (TSH +3/-15.2 inches).
- 100% Visual inspection of tube plugs in SGs 1 and 4.
. Visual inspection in SGs 1 and 4 of channel head primary side HL and CL in accordance with Westinghouse Letter NSAL 12-1, "Steam Generator Channel Head Degradation".
2R16 SG Secondary Side Activities TTS Sludge Lancing in all 4 SGs.
- Foreign Object Search and Retrieval (FOSAR) in all 4 SGs.
o Annulus and tubelane region including periphery tubes, o Possible loose parts (PLP) calls from eddy current tube inspections, and o Legacy items.
Damage Mechanisms Found and NDE Techniques Utilized Based on SG eddy current and visual inspection results, a new degradation mechanism to Unit 2 was identified. The existing degradation mechanisms in the Vogtle Unit 2 are:
- (New) ODSCC at the hot leg tubesheet expansion transitions. A single circumferential ODSCC indication was identified in SG 2.
o + Point and Ghent probe techniques were used to analyze the indication.
- Mechanical Wear due to Foreign Objects o +Point and bobbin techniques were used to evaluate the wear indications.
- Mechanical Wear at AVB Supports.
o Bobbin techniques were used to evaluate wear indications.
- Mechanical Wear and Wall loss from Secondary Side Cleaning Activities.
o Bobbin techniques were used to evaluate the wear indications.
E-2
Enclosure to NL-13-2036 2R1 6 Steam Generator Tube Inspection Report Service Induced Indication Descriptions ForeignObject Wear Foreign objects have been reported as the cause for tube wear at Vogtle Unit 2 during prior inspections; therefore, wear due to foreign objects is classified as an existing degradation mechanism and has been addressed in the SG inspections during 2R16. For the tubesheet locations given in Table 1, all surrounding open tubes were examined for 3 inches above the top of the tubesheet as part of the HL TTS +Point program.
Tube location SG 1 R47C85 was visually inspected as part of the planned secondary side inspection in SG 1 during 2R16. No change in the tube wear indication is observed visually and no objects were noted in the adjacent areas between the 2R15 and 2R16 outage inspections.
This tube location, SG 1 R47C85, and surrounding area was +Point tested again in 2R1 6 as part of the eddy current expansion program. A newly reported 10% TW tube wear indication was observed on SG1 R47C84. A history review of tube SG 1 R47C84 found this indication was present during 2R1 5 with no apparent growth. The historical PLPs at tubes SG 1 R48C86 and R49C86 were also inspected during 2R16 with no foreign objects found. The visual inspection information combined with the evaluation of the 2R16 and historical eddy current
+Point data for these wear indications show there has been no growth and no foreign objects in the area.
There was one set of adjacent PLP indications in SG 2 at the top of the HL tubesheet at R31C49, R32C49, R32C50, and R33C50 observed during 2R16. These tubes were boxed in with +Point inspection and visual confirmation was performed after sludge lancing with no further indications of a foreign object. The historical PLP indication in SG 2 at RIC1 18 was visually inspected. A sludge rock was identified, added to the foreign object log, and evaluated.
No PLPs or tube wear indications were identified from the eddy current inspections in SG 3 during 2R16.
A historical tube wear indication is located in SG 4 at R12C57 just above the HL TTS. This indication was measured at 20% through-wall during 2R16 and 19% TW in 2R1 5. The TW measurement variation for this historical wear call is inside the uncertainty range for the applied
+Point sizing technique. No PLP indications were identified in SG 4 during the 2R16 inspection.
Based on the final inspection results, the observed indications did not exceed the condition monitoring limits and did not require in-situ proof of pressure and leakage testing to demonstrate tube integrity.
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Enclosure to NL-13-2036 2R16 Steam Generator Tube Inspection Report Table 1: Vogte 2 PLP/PCT for 2R16 SG Row Column Indication %TWD Location 1 49 86 PLP TSH+0.41 inch 1 48 86 PLP TSH +0.47 inch 1 48 86 PLP - TSH +0.21 inch 1 47 85 POT 9 TSH +0.07 inch 1 47 84 PCT 10 TSH +0.16 inch 2 1 118 PLP - TSH +0.09 inch 2 33 50 PLP - TSH +0.11 inch 2 32 50 PLP - TSH +0.59 inch 2 32 49 PLP - TSH +1.23 inches 2 32 49 PLP - TSH +0.83 inch 2 31 49 PLP - TSH +1.7 inches 4 12 57 PCT 20 TSH +0.4 inch
%TWD - Percent Through-wall Depth PLP - Possible Loose Part TSH - Tubesheet region on HL side PCT - Foreign Object Wear Mechanical Wear and Wall Loss from Secondary Side Cleaning Volumetric indications associated with secondary side cleaning activities have been reported in the Vogtle Unit 2 SGs during previous inspections. They have been reported to visually resemble tube oxide removal patterns. The only indication tested during 2R16, identified in Table 2, was SG 3 at R1C112 at TSC+18.15 inches. The TW measurement variation for this historical wear call is inside the uncertainty range for the applied +Point sizing technique; therefore, no apparent growth of this indication has occurred between the 2R14 and 2R16 inspections. Based on the inspection data, the indication did not exceed the condition monitoring limits and did not require in-situ proof of pressure and leakage testing to demonstrate tube integrity.
Table 2: Vogtle 2 Tube Wear and Wall Loss from Secondary Side Cleaning for 2R16 SG Row Column Volts Indication %TWD Location 3 1 112 0.26 PCT 24 TSC+18.15 TSC - Tubesheet region on CL side Anti-Vibration Bar (A VB) Wear AVB wear continued to be identified in Vogtle 2R16 in SG2 and SG3. AVB wear identified is provided in Table 3 (SG 2) and Table 4 (SG 3). All AVB locations have been examined in SG 2 and SG 3; only one wear location, SG 3 R56C82, exceed the technical specification plugging criteria of 40% TW. None of the indications exceeded the condition monitoring limits and therefore did not require in-situ pressure and leakage testing to demonstrate tube integrity.
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Enclosure to NL-1 3-2036 2R1 6 Steam Generator Tube Inspection Report Table 3: Vogtle 2R16 SG2 AVB Wear Indications Row Col Location' 2R16 % TWO Row Col Location1 2R16% TWO 12 121 AV6 10 39 44 AV3 15 28 115 AV1 13 39 44 AV5 10 28 115 AV6 17 39 44 AV6 5 29 10 AV5 10 39 52 AV4 14 30 10 AV5 10 39 88 AV4 13 34 12 AV3 6 39 107 AV2 9 36 14 AV4 6 40 48 AV4 22 36 16 AV5 11 40 48 AV5 13 36 16 AV6 12 40 52 AV3 22 36 106 AV3 9 40 52 AV5 14 36 106 AV4 13 .40 54 AV3 12 36 106 AV5 11 40 57 AV3 11 36 106 AV6 10 40 63 AV3 16 37 54 AV5 13 40 64 AV4 10 38 15 AV2 9 40 73 AV3 12 38 15 AV3 9 40 73 AV5 14 38 39 AV2 8 40 73 AV6 12 38 39 AV3 12 42 19 AV2 11 38 39 AV4 12 42 19 AV3 11 38 39 AV5 18 42 19 AV4 12 38 45 AV1 12 42 19 AV5 12 38 74 AV1 9 42 50 AV2 13 38 74 AV2 12 42 50 AV3 10 38 74 AV3 16 42 50 AV4 10 38 74 AV4 16 42 74 AV2 32 38 74 AV5 10 42 74 AV3 29 38 74 AV6 6 42 74 AV4 11 38 81 AV2 13 42 74 AV5 11 38 81 AV3 10 42 74 AV6 11 38 81 AV5 13 42 88 AV2 13 38 81 AV6 14 43 20 AV1 10 38 100 AV3 12 43 20 AV2 13 39 43 AV2 22 43 64 AV1 15 39 43 AV3 20 43 73 AV4 22 39 43 AV4 14 44 72 AV5 18 39 43 AV5 16 45 49 AV3 12 39 43 AV6 12 48 56 AV3 12 39 44 AV2 11 49 32 AV4 11 AV# - Location of AVB intersection with the tube (there are up to 6)
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Enclosure to NL- 13-2036 2R1 6 Steam Generator Tube Inspection Report ThbIA ~ (c~nntinuAd~~ VocitlA 2RIR ~2 AVA WARr Indir~ntinnR Row Col Location ' 2R16 % TWD Row Col Location' 2R16% TWD 49 66 AV2 16 51 91 AV4 15 49 66 AV3 15 51 91 AV5 26 49 74 AV3 24 .51 91 AV6 15 49 91 AV2 22 52 52 AV3 8 49 91 AV3 13 52 91 AV4 15 50 70 AV4 17 53 52 AV3 9 50 89 AV3 10 53 88 AV4 14 50 89 AV4 14 53 88 AV5 20 50 89 AV5 11 53 90 AV4 11 50 89 AV6 12 53 90 AV6 10 50 91 AV4 9 54 86 AV4 12 51 71 AV6 9 55 74 AV5 10 51 72 AV2 11 55 84 AV1 8 51 72 AV3 10 55 84 AV4 11 51 72 AV4 10 56 41 AV3 11 51 72 AV5 11 56 43 AV2 10 151 74 AV2 11 56 43 AV6 12 51 74 AV3 24 56 52 AV3 11 51 74 AV4 14 56 82 AV5 11 51 74 AV5 9 57 49 AV6 14 51 74 AV6 9 57 62 AV1 10 51 87 AV2 29 57 62 AV2 10 51 87 AV3 30 57 64 AV3 15 51 87 AV4 22 57 64 AV4 14 51 87 AV5 30 57 72 AVI 12 51 89 AV3 12 57 72 AV3 12 51 89 AV4 32 57 79 AV3 9 51 89 AV5 29 57 79 AV4 11 51 89 AV6 17 58 70 AV2 11 51 90 AV4 19 59 56 AV4 13 51 90 AV5 15 59 66 AV2 14 51 91 AV3 12 1 AV# - Location of AVB intersection with the tube (there are up to 6)
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Enclosure to NL-13-2036 2R16 Steam Generator Tube Inspection Report Table 4: Vogtle 2R16 SG3 AVB Wear Indications Row Col Location' 2R16 % TWD Row Col Location' 2R16% TWD 12 121 AVI 10 43 82 AV5 14
,30 112 AV5 12 44 23 AV3 11 32 12 AV2 13 44 64 AV4 6 32 12 AV5 21 44 68 AV3 6 34 13 AVI1 11 45 62 AV4 10 34 13 AV2 10 46 62 AV4 12 34 13 AV4 12 48 37 AV3 15 34 13 AV5 20 50 29 AV4 12 34 13 AV6 12 50 48 AV4 12 35 64 AV4 5 50 48 AV5 14 39 72 AV2 19 50 48 AV6 11 39 72 AV3 24 50 95 AV5 9 39 72 AV4 27 51 38 AV5 9 40 44 AV2 12 52 83 AV2 18 41 19 AV4 13 52 83 AV3 33 41 77 AV2 14 52 83 AV4 27 41 77 AV3 10 52 83 AV5 26 41 77 AV4 24 53 62 AV3 12 41 77 AV5 22 53 62 AV5 6 41 82 AV2 11 54 38 AV5 14 41 82 AV3 10 54 62 AV2 5 41 82 AV4 9 56 82 AV2 27 42 20 AV3 15 56 82 AV3 41 42 20 AV4 13 56 82 AV4 22 42 53 AV2 11 57 48 AV4 15 42 53 AV4 8 57 48 AV5 14 42 64 AVI 6 57 48 AV6 16 42 64 AV2 24 57 49 AV4 8 42 64 AV3 20 57 62 AV4 13 42 64 AV4 33 57 78 AV2 10 42 64 AV5 21 58 49 AVi 14 43 62 AV4 8 58 49 AV5 14 43 82 AV2 10 _58 49 AV6 10
'AV# - Location of AVB intersection with the tube (there are up to 6)
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Enclosure to NL-13-2036 2R16 Steam Generator Tube Inspection Report ODSCC A single circumferential ODSCC indication was found at the top of tubesheet hot leg expansion transition in SG2 R15C60. Criteria for in-situ proof testing and leak testing were not met; therefore, in-situ testing was not required to be performed to demonstrate tube integrity. The tube was stabilized and plugged based on detection of circumferential ODSCC.
Table 5: Voc te Single Circumferential ODSCC for 2R16 SG Row Column Indication Crack Max. Stabilized?
Angle Depth (%)
(degrees) 2 15 60 SO0 47 33% Yes SCI - Single circumferential indication Number of Tubes Plugged Table 6 presents a summary list of all SG tubes plugged in 2R16 and the related degradation mechanism.
Table 6: 2R16 Plugged Tubes
=SG Row Column Indication Degradation Mechanism 2 15 60 SCI ODSCC 3 56 82 PCT AVB Wear Total plugging in the SGs after 2R16 is as follows:
SG 1- 6 tubes for a total of 0,11% tubes plugged SG 2- 15 tubes for a total of 0.27% tubes plugged SG 3- 5 tubes for a total of 0.09% tubes plugged SG 4- 22 tubes for a total of 0.39% tubes plugged Total tubes plugged for all Unit 2 SGs: 48, 0.21%
Tube Axial Displacement (Slippage) Monitoring Bobbin data collected from SG2 and SG3 has been screened for large amplitude tubesheet indications of greater than 50 volts with a phase angle between 25 and 50 degree, indicative of a severed tube. No tube severance indications were reported; therefore, no tube slippage was identified. There was no SG primary to secondary leakage present during Cycle 16. The calculated accident induced leakage rate is zero; therefore, the performance criteria for Cycle 16 with respect to the H* permanent alternate repair criteria have been satisfied.
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Enclosure to NL- 13-2036 2R1 6 Steam Generator Tube Inspection Report Condition Monitoring Conclusions Based on the final Vogtle 2R1 6 inspection data, no tubes exhibited degradation that required in-situ pressure testing to demonstrate structural and leakage integrity. There was no reported primary-to-secondary leakage prior to the end of the SG inspection interval. No secondary side tube degradation attributable to foreign objects in excess of the Vogtle Unit 2 Condition Monitoring limits has been identified from the FOSAR and visual inspections. The Condition Monitoring limits and correspondingly the SG Performance Criteria for operating leakage and structural integrity were satisfied for the preceding Vogtle Unit 2 SG operating interval. No operational leakage was reported during the previous cycle; therefore, the calculated accident induced leakage rate is zero.
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