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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:Legal-Affidavit
MONTHYEARNL-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-22-0609, Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2022-09-13013 September 2022 Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel ML22255A2032022-09-0202 September 2022 AMS Affidavit for SNC Slides - Pre-Submittal Meeting on September 13, 2022 - Vogtle Online Monitoring LAR ND-22-0219, Technical Specifications Setpoint Report2022-08-11011 August 2022 Technical Specifications Setpoint Report ND-22-0654, Licensee Guarantees of Payment of Deferred Premiums2022-08-10010 August 2022 Licensee Guarantees of Payment of Deferred Premiums NL-22-0549, Responses to NRC Request for Additional Information for Refueling Outage 1R23 Steam Generator Tube Inspection Report2022-07-19019 July 2022 Responses to NRC Request for Additional Information for Refueling Outage 1R23 Steam Generator Tube Inspection Report NL-22-0288, License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2022-06-30030 June 2022 License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel ML22179A1202022-06-15015 June 2022 Enclosure 5 List of UFSAR and Tier 1 Figures & Sections Containing Security-Related or Proprietary Information, Enclosure 6 SNC Affidavit, and Enclosure 7 Westinghouse Application for Withholding Proprietary Information & Affidavit NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update ND-21-0843, Enclosure 4: Westinghouse Electric Company - Affidavit for Withholding of Enclosure 52021-10-0101 October 2021 Enclosure 4: Westinghouse Electric Company - Affidavit for Withholding of Enclosure 5 ND-21-0070, (Vegp), Units 3 and 4, Affidavit2021-02-0909 February 2021 (Vegp), Units 3 and 4, Affidavit ML21040A1682021-02-0303 February 2021 (Vegp), Units 3 and 4, Affidavit ND-20-1414, (VEGP) Units 3 and 4 - Affidavit from Southern Nuclear Operating Company for Withholding Under 10 CFR 2.390 (CAW-20-5130) (VEGP 3&4 PSI/ISI-ALT-15)2020-12-23023 December 2020 (VEGP) Units 3 and 4 - Affidavit from Southern Nuclear Operating Company for Withholding Under 10 CFR 2.390 (CAW-20-5130) (VEGP 3&4 PSI/ISI-ALT-15) ML20358A1832020-12-16016 December 2020 (VEGP) Units 3 and 4 - Affidavit from Westinghouse for Withholding Under 10 CFR 2.390 (CAW-20-5130) (VEGP 3&4 PSI/ISI-ALT-15) ND-21-0084, (VEGP) Unit 3 - Affidavits of Brian H. Whitley & Zachary S. Harper2020-12-11011 December 2020 (VEGP) Unit 3 - Affidavits of Brian H. Whitley & Zachary S. Harper ND-20-0164, Affidavit2020-05-15015 May 2020 Affidavit ND-20-0092, Revision to Request for License Amendment: Removal of the Preoperational Passive Residual Heat Removal Heat Exchanger Natural Circulation Test (LAR-19-017R1)2020-01-31031 January 2020 Revision to Request for License Amendment: Removal of the Preoperational Passive Residual Heat Removal Heat Exchanger Natural Circulation Test (LAR-19-017R1) ML20020A0082020-01-20020 January 2020 Westinghouse - Submittal of WCAP-18461-P and WCAP-18461-NP, Common Q Platform and Component Interface Module System Elimination of Technical Specification Surveillance Requirements ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification ...2019-10-0707 October 2019 Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification ... ND-19-0947, Enclosure 5 - Westinghouse Proprietary Information Notice, Copyright Notice and CAW-19-4936, Transmittal of the Draft of Westinghouse LAR-226 (LAR-19-017)2019-09-0505 September 2019 Enclosure 5 - Westinghouse Proprietary Information Notice, Copyright Notice and CAW-19-4936, Transmittal of the Draft of Westinghouse LAR-226 (LAR-19-017) ND-19-0855, Request for License Amendment: Tornado Missile Protection for Main Steam Vent Stacks and Wall 11 (LAR-19-014) - Without Proprietary Enclosure 32019-08-16016 August 2019 Request for License Amendment: Tornado Missile Protection for Main Steam Vent Stacks and Wall 11 (LAR-19-014) - Without Proprietary Enclosure 3 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 ND-19-0119, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2019-02-0808 February 2019 Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule 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-18-1456, Transmittal of Licensing Planning Meetings Material2018-12-12012 December 2018 Transmittal of Licensing Planning Meetings Material ND-18-0635, Response to Request for Additional Information Regarding Application of VT-1 Visual Examination Methodology for Preservice Inspection of the Reactor Vessel Nozzle Inner Radius Sections (VEGP 3&4-PSI-ALT-07S3)2018-08-31031 August 2018 Response to Request for Additional Information Regarding Application of VT-1 Visual Examination Methodology for Preservice Inspection of the Reactor Vessel Nozzle Inner Radius Sections (VEGP 3&4-PSI-ALT-07S3) ND-18-0826, Enclosure 2 to ND-18-0826, Request for License Amendment: Crediting Previously Completed First Plant and First Three Plant Tests2018-08-0303 August 2018 Enclosure 2 to ND-18-0826, Request for License Amendment: Crediting Previously Completed First Plant and First Three Plant Tests NL-18-0915, Vogtle Electric Generating Plant, Units 1 & 2 - Supplemental Response to NRC Generic Letter 2004-022018-07-10010 July 2018 Vogtle Electric Generating Plant, Units 1 & 2 - Supplemental Response to NRC Generic Letter 2004-02 ND-18-0837, Transmittal of Proprietary Presentation Slides for NRC Public Meeting on May 31, 2018 Update on Air Baffle Program Discussion2018-06-19019 June 2018 Transmittal of Proprietary Presentation Slides for NRC Public Meeting on May 31, 2018 Update on Air Baffle Program Discussion ND-18-0425, Supplement to Request for License Amendment and Exemption: Consistency and Clarification Changes to Annex Building, Auxiliary Building and Basemat ITAAC (LAR-17-040S1)2018-04-0606 April 2018 Supplement to Request for License Amendment and Exemption: Consistency and Clarification Changes to Annex Building, Auxiliary Building and Basemat ITAAC (LAR-17-040S1) ND-18-0030, Transmittal of Proprietary Presentation Slides for NRC Public Meeting Scheduled for March 8, 2018 Regarding License Amendment Request for Crediting China First of a Kind Testing2018-03-0101 March 2018 Transmittal of Proprietary Presentation Slides for NRC Public Meeting Scheduled for March 8, 2018 Regarding License Amendment Request for Crediting China First of a Kind Testing ND-18-0300, Westinghouse Electric Co., Application for Withholding Proprietary Information from Public Disclosure2018-02-27027 February 2018 Westinghouse Electric Co., Application for Withholding Proprietary Information from Public Disclosure ND-17-1955, Request for License Amendment and Exemption: Tier and Tier 2* Editorial and Consistency Changes (LAR-17-042)2017-11-30030 November 2017 Request for License Amendment and Exemption: Tier and Tier 2* Editorial and Consistency Changes (LAR-17-042) NL-15-0188, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52015-02-13013 February 2015 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 NL-08-0015, Correction to Information Contained in Request to Change Licensed Maximum Power Level2008-01-18018 January 2008 Correction to Information Contained in Request to Change Licensed Maximum Power Level 2024-01-22
[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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~ Southern Nuclear Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5316 tel 205 992 7601 fax cagayhea@ southernco.com JAN 0 3 2019 Docket Nos.: 50-424 NL-18-1565 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant- Unit 1 lnservice Inspection Program Owner's Activity Report for Outage 1R21 Ladies and Gentlemen:
ASME Section XI Code Case N-532-5 OAR-1 Owner's Activity Report for the 1R21 Refueling Outage is provided as Enclosure 1 to this letter. Table 1, "Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service," lists evaluations performed for continued service, and is provided as Enclosure 2. Table 2, "Abstract of Repairs, Replacement or Corrective Measures Required for Continued Service," lists repair/replacement activities, and is provided as Enclosure 3.
The flaw evaluation of the Unit 1 boron injection tank line nozzle weld overlay is provided as . This enclosure contains proprietary information as defined by 10 CFR 2.390.
Westinghouse Electric Company LLC ('Westinghouse"), as the owner of the proprietary information, has executed the enclosed affidavit, which identifies that the enclosed proprietary information has been withheld from public disclosure. The proprietary information was provided to Southern Nuclear (SNC) in a Westinghouse transmittal which included the affidavit included in Enclosure 5 to this letter. The proprietary information has been faithfully reproduced in the enclosed documentation, such that, the affidavit remains applicable. Westinghouse hereby requests that the enclosed proprietary information provided in Enclosure 4 to this letter be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390.
This report is for the first period of the 41h Interval lSI activities (Interval 4, Period 1, Outage 1).
This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at (205) 992-6611.
Enclosure 4 to this letter contains Proprietary Information to be withheld from public disclosure per 10 CFR 2.390. When separated from Enclosure 4 this transmittal document is decontrolled.
U. S. Nuclear Regulatory Commission NL-18-1565 Page2 Respectfully submitted, CAG/kgl/sm
Enclosures:
- 1. 1R21 Form OAR-1 Owner's Activity Report, (Non-Proprietary)
- 2. 1R21 Form OAR-1 Owner's Activity Report, Table 1, Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service, (Non-Proprietary)
- 3. 1R21 Form OAR-1 Owner's Activity Report, Table 2, Abstract of Repairs, Replacement or Corrective Measures Required for Continued Service, (Non-Proprietary)
- 4. Flaw evaluation of the Unit 1 boron injection tank line nozzle weld overlay, (PROPRIETARY)
- 5. CAW-18-4839, "Application for Withholding Proprietary Information from Public Disclosure," (Non-Proprietary)
Cc: Regional Administrator NRR Project Manager- Vogtle 1 & 2 Senior Resident Inspector- Vogtle 1 & 2 RType: CVC7000 to this letter contains Proprietary Information to be withheld from public disclosure per 10 CFR 2.390. When separated from Enclosure 4 this transmittal document is decontrolled.
Vogtle Electric Generating Plant - Unit 1 lnservice Inspection Program Owner's Activity Report for Outage 1R21 Enclosure 1 1R21 Form OAR-1 Owner's Activity Report, (Non-Proprietary)
FORM OAR*1 OWNER'S ACTIVITY REPORT Report Number 1-4-1-1 (Unit 1. 4 1h Interval. 151 Period. 151 Report)
Plant Alvin W. Vogtle Electric Generating Plant Unit No. 1 Commercial service date Ma~ 31, 1987 Refueling outage no. 1R21 (if applicable)
Current inspection interval 4111 {Also includes 3n1 Interval activities Qerformed after refueling outage 1R20}
(1st, 2nd, 3rd. 4th, other)
Current inspection period 151 (Also includes 3n1 Period activities Qerformed after refueling outage 1R20}
(1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans: The 2001 Edition through 2003 Addenda is aQQiicable to the 3n1 lns~ction Interval. The 2007 Edition through 2008 Addenda is aQplicable to the 41h Inspection Interval.
Date and revision of inspection plans: 3n1 lnsQection lntervallnsoection Plans- Volume 1 - 03/01/2017 Nersion 10.0}, Volume 2-03/09/2017 {Version 8.Q}, Volume 3-03/09/2017 Nersion 4.0}, Volume 5-03/08/2017
{Version 9.0} and Volume 6-03/08/2017 Nersion 8.0}. 4111 Inspection Interval Inspection Plans- Volume 1-09/12/2018 Nersion 2.0}, Volume 3-09/1212018 Nersion 2.0}, Volume 4-12119/2018 Nersion 3.0}, and Volume 5- 10/10/2018 Nersion 3.0}. 1R21 Outage Plan- 09/13/2018 Nersion 1.0} with 1R21 Outage Plan Scope Change SC-001 -09/27/2018 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection plans: Same Code Cases used for inspection and evaluation: N-716-1 N-722-1 N-729-4 and N-770-2 (if applicable, including cases modified by Case N-532 and later revisions)
CERnFICATE OF CONFORMANCE I certify that (a) the statements made In this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of 1R21 conform to the requirements of Section Xi. (retuoling outage mmber)
Signed S. J. Kowals~~<o lskt Owner or Owner'S0'8signee. Trtle Enaineerina Director Date *L~Lzorj 11 CERnFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Companv of Hartford. CT. have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Jerome Barthelemy lnspectots Si~
~~ Commission NB15817 AI. N,l. R/GA-1192 (National Board Number and Endorsement)
Date IL'!>/ ;;Jo19
Vogtle Electric Generating Plant- Unit 1 lnservice Inspection Program Owner's Activity Report for Outage 1R21 Enclosure 2 1R21 Form OAR-1 Owner's Activity Report, Table 1, Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service, (Non-Proprietary)
Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category Item Description Evaluation Description and Item Number Code Case N-716-1 During the ultrasonic examination of weld 11204- An "Analytical Evaluation" was performed on this Examination Category R-A 246-35 (1.5" Pipe to 3" x 1.5" Reducer Weld), flaw in accordance with IWB-3640 "Evaluation Item Number R.1 1 ultrasonic reflectors were recorded in the reducer Procedures and Acceptance Criteria for Flaws in side of the weld close to the fusion line of the weld. Austenitic and Ferritic Piping" and determined to This is the high head safety injection piping be acceptable for continued service. The connected to the Loop 4 Reactor Coolant System Analytical Evaluation is limited to one refueling Cold Leg. This component was inspected under cycle.
the MRP-146 surveillance for thermal fatigue cracking only. The indications were evaluated to Per the requirements of IWB-3640, specific details the applicable ASME acceptance standard (Table are provided to the Nuclear Regulatory IWB-3514-2) and determined to be rejectable. Commission in Enclosure 4 "Flaw evaluation of the Unit 1 boron injection tank line nozzle weld overlay".
Vogtle Electric Generating Plant- Unit 1 lnservice Inspection Program Owner's Activity Report for Outage 1R21 Enclosure 3 1R21 Form OAR-1 Owner's Activity Report, Table 2, Abstract of Repairs, Replacement or Corrective Measures Required for Continued Service, (Non-Proprietary)
Table 2 Abstract of Repair I Replacement Activities Required for Continued Service Code Item Description Description of Work Date Repair I Replacement Class Completed Plan Number Code Case N-716-1 To eliminate this MRP-146 10/03/2018 969639-T1 Examination Category R-A thermal fatigue location the 2" Item Number R.11 H drain line pipe was removed and replaced with a plug that was During the ultrasonic (UT) inserted into the socket weld examination of weld 11201-046-3 branch and welded with a fillet (2" Elbow to Pipe Weld) a weld.
circumferential ultrasonic reflector was recorded in the heat affected zone of the weld in the elbow side.
This intermediate drain line is connected to the Loop 3 Reactor Coolant System Intermediate Leg.
This indication was found during the scheduled MRP-146 examinations for detection of thermal fatigue. This location was also selected for examination per Code Case N-716-1 ; Category Number R-A; Item Number R1 .11 H. The indication was evaluated to the applicable ASME acceptance standard (Table IW8-3514-2) and was determined to be rejectable.
Examination Category 8-Q, Mechanical plugs were installed 09/27/2018 854745-T1 Steam Generator 2 Tubing in applicable tubes due to (Location 11201 86002) degradation detected during eddy current examinations Examination Category 8-Q, Mechanical plugs were installed 09/29/2018 925521-T1 Steam Generator 4 Tubing in applicable tubes due to (Location 11201 86004) degradation detected during eddy current examinations
Vogtle Electric Generating Plant - Unit 1 lnservice Inspection Program Owner's Activity Report for Outage 1R21 Enclosure 5 CAW-18-4839, "Application for Withholding Proprietary Information from Public Disclosure,"
(Non-Proprietary)
Westinghouse Non-Proprietary Class 3
@Westinghouse Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-3382 Document Control Desk Direct fax: (724) 940-8542 11555 Rockville Pike e-mail: russpa@westinghouse.com Rockville, MD 20852 CAW-18-4839 November 20, 2018 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
Vogtle Unit 1 BIT Line Nozzle Weld Overlay Flaw Evaluation (Proprietary)
The Application for Withholding Proprietary Information from Public Disclosure is submitted by Westinghouse Electric Company LLC ("Westinghouse"), pursuant to the provisions of paragraph (b)(l) of Section 2.390 of the Nuclear Regulatory Commission's ("Commission's") regulations. It contains commercial strategic information proprietary to Westinghouse and customarily held in confidence.
The proprietary information for which withholding is being requested in the subject report is further identified in Affidavit CAW-18-4839 signed by the owner of the proprietary information, Wes~inghouse.
The Affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CPR Section 2.390 of the Commission's regulations.
The subject document was prepared and classified as Westinghouse Proprietary Class 2. It contains proprietary information throughout, for the reasons set forth in Sections 4(ii) (a) (b) and (f) of this Affidavit. Accordingly, a redacted version would be of no value to the public and a non-proprietary version will not be issued.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Southern Nuclear.
Correspondence with respect to the proprietary aspects of the Application for Withholding or the Westinghouse Affidavit should reference CAW-18-4839, and should be addressed to Camille T. Zozula, Manager, Infrastructure & Facilities Licensing, Westinghouse Electric Company, 1000 Westinghouse ec Drive, Building 2, Suite 259, Cranberry Township, Pennsylvania 1~0 .
/"? /)
\.Jtt~
Paul A. Russ, Director Licensing and Regulatory Mfairs
Enclosures:
- 1. Affidavit CAW- 18-4839
- 2. Proprietary Information Notice and Copyright Notice
- 3. Vogtle Unit 1 BIT Line Nozzle Weld Overlay Flaw Evaluation
© 2018 Westinghouse Electric Company LLC. All Rights Reserved.
CAW-18-4839 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF BUTLER:
I, Paul A. Russ, am authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC ("Westinghouse") and declare that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief.
Executed on: II (w /19 Paul A. Russ, Director Licensing and Regulatory Affairs
3 CAW-18-4839 (1) I am Director, Licensing and Regulatory Affairs, Westinghouse Electric Company LLC
("Westinghouse"), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Nuclear Regulatory Commission's ("Commission's") regulations and in conjunction with the Westinghouse Application for-Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and ha~ been held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connec~ion, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitute Westinghouse policy and provide the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of
4 CAW-18-4839 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage (e.g., by optimization or improved marketability).
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment. installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or COJillilercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(iii) There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
5 CAW-18-4839 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iv) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR. Section 2.390, is to be received in confidence by the Commission.
(v) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or ~ethod to the best of our knowledge and belief.
(vi) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in LTR-SDA-18-090, Rev. 0 P-Attachment, "Vogtle Unit 1 BIT Line Nozzle Weld Overlay Flaw Evaluation" (Proprietary), for submittal to the Commission, being transmitted by Southern Nuclear letter. The proprietary information as submitted by Westinghouse is that associated with fracture analyses pertaining to the Vogtle Unit 1 boron injection tank nozzle attached to the reactor vessel cold leg and weld overlay repair applied to the nozzle, and may be used only for that purpose.
(a) This information is part of that which will enable Westinghouse to perform future analyses of Vogtle Unit 1 boron injection tank nozzle and weld overlay repair.
(b) Further, this information has substantial commercial value as follows:
6 CAW-18-4839 (i) Westinghouse plans to sell the use of similar infonnation to its customers for the purpose of fracture analysis and weld overlay repair.
(ii) Westinghouse can sell support and defense of industry guidelines and acceptance criteria for plant-specific applications.
(iii) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar technical evaluation justifications and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the infonnation would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse 'effort and the expenditure of a considerable sum of money.
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and non-proprietary versions of a document, furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.
In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the Affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(l).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the tssuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.