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Category:Legal-Affidavit
MONTHYEARRS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly ML22320A5592022-11-16016 November 2022 2022 Annual Report - Guarantees of Payment of Deferred Premiums RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds ML21307A0542021-11-0202 November 2021 Annual Report - Guarantees of Payment of Deferred Premiums ML21272A2772021-09-29029 September 2021 Update to Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21225A0062021-08-13013 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0 ML21182A1002021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML20310A1152020-11-0404 November 2020 Annual Report - Guarantees of Payment of Deferred Premiums RS-20-079, Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2020-07-10010 July 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections RS-20-058, Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-16016 April 2020 Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML19318G1702019-11-14014 November 2019 2019 Annual Report - Guarantees of Payment of Deferred Premiums RS-19-051, Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2019-05-30030 May 2019 Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies ML18316A0032018-11-0707 November 2018 Submittal of 2018 Annual Report - Guarantees of Payment of Deferred Premiums RS-18-129, Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2018-10-19019 October 2018 Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies ML18011A6242018-01-0808 January 2018 R. E. Ginna, Unit 1, Submittal of Annual Report of the Nuclear Advisory Committee RS-17-168, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1)2017-12-20020 December 2017 Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1) RS-17-168, Braidwood Station, Unit 2, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1)2017-12-20020 December 2017 Braidwood Station, Unit 2, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1) RS-17-039, Attachments 7 - 10, Affidavits2017-03-27027 March 2017 Attachments 7 - 10, Affidavits ML17010A0772017-01-19019 January 2017 Submittal of Annual Report of the Nuclear Advisory Committee RS-16-249, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy2016-12-16016 December 2016 Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval2016-11-0808 November 2016 Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds RS-16-060, Byron, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision2016-03-14014 March 2016 Byron, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision ML16074A4152016-03-14014 March 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Revision RS-16-061, Braidwood, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Revision2016-03-14014 March 2016 Braidwood, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Revision ML16074A4242016-03-14014 March 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision RS-16-045, Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-02-11011 February 2016 Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds ML16039A3032016-01-26026 January 2016 Transmittal of Radiological Emergency Implementing Procedure Revisions RS-15-155, Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2015-05-29029 May 2015 Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations ML14321A7052014-11-14014 November 2014 2014 Annual Report - Guarantees of Payment of Deferred Premiums RS-14-223, Enclosure C - Application for Withholding Proprietary Information from Public Disclosure Supporting the Following Set 31 RAI Response RAI 4.3.4-3a2014-07-24024 July 2014 Enclosure C - Application for Withholding Proprietary Information from Public Disclosure Supporting the Following Set 31 RAI Response RAI 4.3.4-3a RS-14-160, Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package2014-07-0202 July 2014 Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package ML14118A1412014-03-28028 March 2014 Independent Spent Fuel Storage Installation, Nine Mile Point Independent Spent Fuel Storage Installation, R.E. Ginna Independent Spent Fuel Storage Installation, Response to Request for Affidavit Supporting Request for Designation Of. RS-12-227, Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package2012-12-19019 December 2012 Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package RS-12-457, Attachment 4, Cameron International Corporation Affidavit Supporting Withholding of Information in Attachment 3 (Non-Proprietary)2012-06-0101 June 2012 Attachment 4, Cameron International Corporation Affidavit Supporting Withholding of Information in Attachment 3 (Non-Proprietary) ML1031904262010-11-0808 November 2010 Corp. - 2010 Annual Report - Guarantees of Payment of Deferred Premiums RS-07-022, Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification2007-02-15015 February 2007 Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification RS-05-017, Response to Information Request Regarding Significance Determination Process Risk-Informed Inspection Notebook2005-02-25025 February 2005 Response to Information Request Regarding Significance Determination Process Risk-Informed Inspection Notebook ML0428601382004-09-30030 September 2004 R. E. Ginna - Fracture Mechanics Analysis Per GDC-4 ML18143A0301978-04-26026 April 1978 R. E. Ginna - Request for Exemption from the Requirements of 10 C.F.R. Section 50.46 and 10 C.F.R. 50 Appendix K ML18142B9471978-01-0606 January 1978 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. 2024-05-28
[Table view] Category:Letter
MONTHYEARRS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24297A2702024-10-23023 October 2024 Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000455/2025002 IR 05000244/20243012024-10-22022 October 2024 Initial Operator Licensing Examination Report 05000244/2024301 ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 ML24286A0022024-10-11011 October 2024 Core Operating Limits Report Cycle 45, Revision 0 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24281A1502024-10-0707 October 2024 Request for Information for NRC Commercial Grade Dedication Inspection Report 05000454/2025010 and 05000455/2025010 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing RS-24-092, Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-09-25025 September 2024 Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000244/20245012024-09-24024 September 2024 LLC - Emergency Preparedness Biennial Exercise Inspection Report 05000244/2024501 ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary BYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024 Cycle 27 Core Operating Limits Report RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024 Relief Requests Associated with the Fifth Inservice Inspection Interval IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24250A1182024-09-0606 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable2024-09-0505 September 2024 Both Trains of Control Room Ventilation Temperature Control System Inoperable ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000244/20240052024-08-29029 August 2024 Updated Inspection Plan for R.E. Ginna Nuclear Power Plant (Report 05000244/2024005) IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) IR 05000454/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005) ML24234A0922024-08-21021 August 2024 Requalification Program Inspection IR 05000244/20240102024-08-19019 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000244/2024010 ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000454/20240112024-08-0808 August 2024 Phase 2 Post- Approval License Renewal Report 05000454/2024011 IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 IR 05000244/20240022024-08-0505 August 2024 LLC - Integrated Inspection Report 05000244/2024002 and Independent Spent Fuel Storage Installation Report 07200067/2024001 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter IR 05000454/20240022024-07-26026 July 2024 Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24170A3852024-07-16016 July 2024 R. E. Ginna Nuclear Power Plant - Alternative Associated with Inservice Testing of B Auxiliary Feedwater Pump - PR-03 ML24197A0302024-07-15015 July 2024 LLC - Operator Licensing Examination Approval RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter IR 05000244/20244022024-06-20020 June 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000244/2024402 ML24170A7652024-06-19019 June 2024 Confirmation of Initial License Examination RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24143A0752024-05-22022 May 2024 Re. Ginna Nuclear Power Plant and Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License ISFSI Casks ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes 2024-09-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24088A2042024-03-28028 March 2024 R. E. Ginna Nuclear Power Plant - Response to NRC Request for Additional Information Regarding Relief Request Associated with Inservice Testing of ‘B’ Auxiliary Feedwater Pump RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P ML21320A2422021-11-16016 November 2021 Stations - Response to Request for Additional Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML21320A0542021-11-15015 November 2021 R. E. Ginna Nuclear Power Plant - Response to Request for Additional Information - Request for Exemption from the Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, Section IV.F.2.c JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments ML21225A0062021-08-13013 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0 NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting ML21078A0022021-03-19019 March 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of R. E. Ginna Nuclear Power Plant, License Amendment Request to Modify the Steam Generator Tube Inspection Frequency RS-21-024, Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2021-03-16016 March 2021 Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-21-029, Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition2021-03-15015 March 2021 Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition RS-21-015, Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-182021-02-10010 February 2021 Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-18 RS-21-019, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2021-02-0909 February 2021 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 RS-20-150, Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements2020-12-0101 December 2020 Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements RS-20-147, Response to Request for Additional Information Related to Exemption from Part 26 Requirements2020-11-23023 November 2020 Response to Request for Additional Information Related to Exemption from Part 26 Requirements RS-20-143, Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating2020-11-20020 November 2020 Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating ML20248H3882020-09-0404 September 2020 Response to Request for Additional Information - License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System. RS-20-100, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections2020-08-19019 August 2020 Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information RS-20-057, Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-13013 April 2020 Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections ML20080N8892020-03-20020 March 2020 R. E. Ginna Nuclear Power Plant, Supplemental Information Associated with the License Amendment Request to Add a One-Time Note for Use of Alternate Residual Heat Removal Methods RS-20-012, Response to Request for Additional Information Regarding Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval2020-01-29029 January 2020 Response to Request for Additional Information Regarding Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 RS-19-100, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended.2019-10-0707 October 2019 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended. RS-19-088, Response to Request for Additional Information Regarding Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed...2019-09-0505 September 2019 Response to Request for Additional Information Regarding Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed... JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-19-051, Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2019-05-30030 May 2019 Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18338A2352018-12-0404 December 2018 R. E. Ginna Nuclear Power Plant - Relief Request ISI-18 to Extend the Reactor Pressure Vessel Inservice Inspection Interval RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements ML18243A1672018-08-29029 August 2018 R. E. Ginna Nuclear Power Plant - Response to Request for Additional Information - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Posit RS-18-095, Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-032018-07-31031 July 2018 Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-03 RS-18-094, Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-062018-07-31031 July 2018 Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-06 2024-08-09
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200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 RS-21-082 10 CFR 50.90 August 13, 2021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 R. E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244
Subject:
Response to Request for Additional Information Regarding License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0
References:
- 1) Letter from D. Gudger (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Application to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev. 1 and NSAL-15-1, Rev. 0,'" dated April 7, 2021 (ADAMS Accession No. ML21097A226)
- 2) Email from J. Wiebe (U. S. Nuclear Regulatory Commission) to J. Hodge (Exelon Generation Company, LLC), "Request for Additional Information -
Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs," dated July 8, 2021 (ADAMS Accession No. ML21189A160)
In Reference 1, Exelon Generation Company, LLC, (EGC) requested an amendment to the Technical Specifications (TSs) for Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and R. E. Ginna Nuclear Power Plant (Braidwood 1 and 2, Byron 1 and 2, and Ginna, Attachment 3 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 3, this document is decontrolled.
August 13, 2021 U. S. Nuclear Regulatory Commission Page 2 Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 respectively). The proposed amendment would modify Required Actions and Surveillance Requirements associated with TS 3.2.1, Heat Flux Hot Channel Factor (FQ(Z)). These revisions implement a series of more restrictive required actions and more thorough surveillance requirements that are used in instances where the transient heat flux hot channel factor, , is not within its operating limits.
In Reference 2, the U. S. Nuclear Regulatory Commission (NRC) requested additional information to complete its review of the proposed amendment. The RAI request in Reference 2 was discussed during a teleconference between Exelon and NRC representatives on July 21, 2021.
The response to this request is due no later than 45 days from the date of Reference 2 (i.e., by August 23, 2021). Attachments 1 through 4 provide the requested information. to this letter contains information proprietary to Westinghouse Electric Company LLC (Westinghouse) as defined by 10 CFR 2.390, "Public inspections, exemptions, requests for withholding." It is supported by an Affidavit signed by Westinghouse, the owner of the information.
The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the NRCs regulation.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.390 of the NRCs regulations.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-21-5210 and should be addressed to Anthony J. Schoedel, Manager, eVinci Licensing & Configuration Management, Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, Pennsylvania 16066. The Affidavit supporting the proprietary nature of the information in Attachment 3 is provided in .
EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment 1 of Reference 1. The additional information provided in this submittal does not affect the basis for concluding that the proposed license amendments do not involve a significant hazards consideration.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b),
a copy of this letter and its attachments are being provided to the designated States of Illinois and New York officials.
There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Jessie Hodge at (610) 765-5532.
Attachment 3 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 3, this document is decontrolled.
August 13, 2021 U. S. Nuclear Regulatory Commission Page 3 Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 13th day of August 2021.
Respectfully, David T. Gudger Sr Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments:
- 1) Response to Request for Additional Information (Non-Proprietary)
- 2) Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E.
Ginna Non-Proprietary Version for NRC (Non-Proprietary)
- 3) Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E.
Ginna Proprietary Version for NRC (PROPRIETARY)
- 4) Westinghouse Affidavit, CAW-21-5210 (Non-Proprietary) cc: NRC Regional Administrator - NRC Region I w/ attachments NRC Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood NRC Senior Resident Inspector - Byron NRC Senior Resident Inspector - Ginna NRC Project Manager, NRR - Braidwood and Byron NRC Project Manager, NRR - Ginna A. L. Peterson, NYSERDA Illinois Emergency Management Agency - Division of Nuclear Safety Attachment 3 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 3, this document is decontrolled.
Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 ATTACHMENT 1 Response to Request for Additional Information REQUEST FOR ADDITIONAL INFORMATION
1.0 INTRODUCTION
By application dated April 7, 2021, Exelon Generation (the licensee) requested changes to the Technical Specifications (TSs) for Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and R. E. Ginna Nuclear Power Plant (Braidwood 1 and 2, Byron 1 and 2, and Ginna, respectively) (Agencywide Document Access and Management System Accession No. ML21097A226). The proposed changes would revise Required Actions and Surveillance Requirements associated with TS 3.2.1, Heat Flux Hot Channel Factor (FQ(Z)). These revisions implement a series of more restrictive required actions and more thorough surveillance requirements that are used in instances where the transient heat flux hot channel factor, , is not within its operating limits.
Similar required actions and surveillance requirements had been administratively implemented at each facility under the auspices of NRC Administrative Letter (AL) 89-10, Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety. These actions had been implemented since Westinghouse notified its customers, including the licensee, that the existing required actions and surveillance requirements associated with TS 3.2.1 may not restore adequate operating margin to ensure that the FQ operating limit would prevent any of the facilities from exceeding the linear heat rate assumed in the plants emergency core cooling system (ECCS) evaluations.
2.0 REGULATORY REQUIREMENTS The performance requirements and design criteria applicable to the power distribution assumed in the safety analysis are those that pertain to accident and transient analysis. Primarily these include the requirements contained in 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, and General Design Criterion (GDC) 10, contained in Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR 50.
The requirements in 10 CFR 50.46 state, in part, that ECCS shall be designed such that an evaluation performed using an acceptable evaluation model demonstrates that acceptance criteria, set forth in 10 CFR 50.46(b), including peak cladding temperature, cladding oxidation, hydrogen generation, maintenance of coolable core geometry, and long-term cooling are met for a variety of hypothetical loss-of-coolant accidents (LOCAs), including the most severe hypothetical LOCA.
GDC 10, Reactor Design, states as follows:
The reactor and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not Page 1 of 2 Attachment 3 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 3, this document is decontrolled.
Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 ATTACHMENT 1 Response to Request for Additional Information exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
The requirements for TS are set forth in 10 CFR 50.36, Technical Specifications. Specific categories of TS are provided in 10 CFR 50.36(c). These include limiting conditions for operation (LCOs). If an LCO is not met, the facility must be shut down, or other acceptable remedial action must be taken. The licensee proposed a set of remedial actions, including reductions in the operating space defined by the combination of rated thermal power and axial flux difference (AFD) that would ensure that the margins continue to ensure that the plants continue to be operated in a manner bounded by the initial conditions assumed in the design basis accident and transient analyses. These actions should, therefore, continue to assure compliance with the requirements of 10 CFR 50.46 and GDC 10.
3.0 REQUEST The licensee stated that the required thermal power and axial flux difference (AFD) reductions, which were proposed to be relocated to the Core Operating Limits Report, would initially be those contained in Table 1 of Attachment 1 to the licensees April 7, 2021, submittal. These were based on interim, compensatory measures that had been recommended from Westinghouse when the current required actions and completion times were deemed inadequate. The technical basis for these reductions in thermal power and AFD is not apparent to the NRC staff. Provide information that demonstrates the proposed operating space reductions contained in Table 1 bring about the desired margin improvements, thus assuring compliance with 10 CFR 50.46 and GDC 10 requirements.
EGC Response:
The technical basis for NSAL-09-5, Revision 1, is provided in Attachments 2 and 3. Attachments 2 and 3 also capture the results of Westinghouse analyses to demonstrate that the proposed operating space reductions in thermal power and AFD are sufficient to restore required margin and protect limits at Braidwood 1 and 2, Byron 1 and 2, and Ginna. The Affidavit supporting the proprietary nature of the information in Attachment 3 is provided in Attachment 4.
Page 2 of 2 Attachment 3 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 3, this document is decontrolled.
ATTACHMENT 4 Westinghouse Affidavit, CAW-21-5210 (NON-PROPRIETARY) 3 pages follow contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 3, this document is decontrolled.
Westinghouse Non-Proprietary Class 3 CAW-21-5210 Page 1 of 3 COMMONWEALTH OF PENNSYLVANIA:
COUNTY OF BUTLER:
(1) I, Anthony J. Schoedel, have been specifically delegated and authorized to apply for withholding and execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse).
(2) I am requesting the proprietary portions of CE-20-392, Revision 1, Attachment 2 be withheld from public disclosure under 10 CFR 2.390.
(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 10 CFR 2.390, 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 has been held in confidence by Westinghouse and is not customarily disclosed to the public.
(ii) The information sought to be withheld is being transmitted to the Commission in confidence and, to Westinghouses knowledge, is not available in public sources.
(iii) Westinghouse notes that a showing of substantial harm is no longer an applicable criterion for analyzing whether a document should be withheld from public disclosure. Nevertheless, 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 information would enable
- This record was final approved on 8/6/2021 1:14:16 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 CAW-21-5210 Page 2 of 3 others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
(5) Westinghouse has policies in place to identify proprietary information. 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 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 commercial 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.
- This record was final approved on 8/6/2021 1:14:16 PM. (This statement was added by the PRIME system upon its validation)
Wcstin 'hOlbc Non -l'wpric1a1 1 Cla:;s 3 Ct\ \\'-:.? I - ~ 2 I 0 l'agc 3 11f 3 (6 ) "111c att:'lchcd documents arc bracketed and marked to indicate the bases for withholding. Th1.:
j usri.tication for withhokling is indicated in botl1 versions by mc*m
- of lower-case lcl!as (;.i) thn ugh (I) loc:atcd as a supascript immcdiatdy following the brackets enclosing each item of infom1atilm 1-x:ing idcntifo:d as proprietary or in the margin opposite sud1 infonnation. Tlu.:~c lowcr-G1sc krtcrs retcr to the types of information Wcstinghou *i.: customarily holds in confidcnc\; identified in Sections (5)(a) through (t) of this AtJidavit.
I dcdan: that the avcnncnts of fact ' Ct forth in this Affidavit arc trnc and correct to 1J1c bes! of my kmnvkdgc, infonrn1tion, and belief.
I declare under penalty of perjury that the foregoing is true and com;d.
Execuced on: f / *s/;;OJ_ I tl/fi#. .Id(
Anthony J. Schocdd, Manager eVinci Licensing & Configuration Management
- This record was final approved on 8/6/2021 1:14:16 PM. (This statement was added by the PRIME system upon its validation)