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MONTHYEARML22213A0102022-08-0101 August 2022 NRR E-mail Capture - Acceptance Review - Vogtle, Units 1 and 2 - Exemption Request from 10 CFR 50.68 to Allow Use of 6-Weight Percent Enriched Fuel Rods in 4 LTAs (L-2022-LLE-0022) Project stage: Acceptance Review ML22224A1272022-08-12012 August 2022 Dashboard Report 8-12-2022 Project stage: Request NL-22-0583, Request for Fee Exemption for NRC Review Fees for the Licensing Amendment and 10 CFR 50.68 Exemption Submitted for Lead Test Assemblies with Increased Enrichment2022-08-12012 August 2022 Request for Fee Exemption for NRC Review Fees for the Licensing Amendment and 10 CFR 50.68 Exemption Submitted for Lead Test Assemblies with Increased Enrichment Project stage: Request ML22228A2122022-08-12012 August 2022, 29 September 2022 Request for a Fee Exemption for NRC Review Fees for the Licensing Amendment Submitted for Lead Test Assemblies with Increased Enrichment Project stage: Request ML22234A0692022-09-15015 September 2022 Request for Withholding Info from Public Disclosure LAR and Exemptions to Allow Use of LTAs for ATF - Enclosure 1, Evaluation of the Proposed Change (Proprietary) EPID L-2022-LLA-0097, LLE-0020, LLE-0021, LLE-0022 Project stage: Approval ML22266A0492022-09-28028 September 2022 Request for Withholding Info from Public Disclosure LAR and Exemptions to Allow Use of LTAs for ATF - Encl. 1, SNC Response to Requests for Additional Info Attachment 2 Proprietary Response to Questions 2-6 EPID L-2022-LLA-0097 Project stage: Approval ML22228A2202022-09-29029 September 2022 Request for Fee Exemption for NRC Review Fees for the Licensing Amendment for Lead Test Assemblies with Increased Enrichment Project stage: Other ML23017A0922023-01-17017 January 2023 NRR E-mail Capture - Revised Estimated Hours - Vogtle, Units 1 and 2 - Exemption Request from 10 CFR 50.68 to Allow Use of 6-Weight Percent Enriched Fuel Rods in 4 LTAs (L-2022-LLE-0022) Project stage: Other ML23094A1192023-08-0101 August 2023 Exemption from the Requirements of 10 CFR Part 50, Section 68, Criticality Accident Requirements (EPID L-2022-LLE-0022)- Letter Project stage: Approval ML23094A1142023-08-0101 August 2023 Exemption from the Requirements of 10 CFR Part 50, Section 68, Criticality Accident Requirements (EPID L-2022-LLE-0022)- Exemption Project stage: Approval ML23094A0992023-08-0202 August 2023 Exemption from the Requirements of 10 CFR Part 50, Section 68, Criticality Accident Requirements (EPID L-2022-LLE-0022)- FRN Project stage: Approval 2022-09-28
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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
[Table view] Category:Response to Request for Additional Information (RAI)
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-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-23-0695, 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-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0339, 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-23-0467, 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-23-0196, 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-23-0010, 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-23-0013, 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 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 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 ND-22-0328, Enclosuvogtle Electric Generating Plant, Units 3 & 4 - Fukushima Response NEI 12-01 On-Shift Staffing Analysis Phase 2 Report, Revision 3.0, Standard Emergency Plan Annex, Revision 6.02022-06-29029 June 2022 Enclosuvogtle Electric Generating Plant, Units 3 & 4 - Fukushima Response NEI 12-01 On-Shift Staffing Analysis Phase 2 Report, Revision 3.0, Standard Emergency Plan Annex, Revision 6.0 NL-22-0055, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2022-02-28028 February 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System NL-21-1015, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System2022-01-13013 January 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System ND-21-0618, Response to Request for Additional Information Regarding Request for Alternative: Alternative Requirements for ASME Section Ill Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16)2021-07-0202 July 2021 Response to Request for Additional Information Regarding Request for Alternative: Alternative Requirements for ASME Section Ill Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16) NL-21-0208, Response to Request for Additional Information Related to Refueling Outage 1R22 Steam Generator Tube Inspection Report2021-03-0202 March 2021 Response to Request for Additional Information Related to Refueling Outage 1R22 Steam Generator Tube Inspection Report NL-20-1417, Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-1912020-12-17017 December 2020 Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-191 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-20-1273, Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for2020-11-20020 November 2020 Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for ND-20-1005, Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1)2020-09-18018 September 2020 Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1) NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request ND-19-1097, Response to Request for Additional Information - LAR-19-013R12019-11-0101 November 2019 Response to Request for Additional Information - LAR-19-013R1 NL-19-1183, Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown2019-10-17017 October 2019 Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown ND-19-1023, Enclosure 7 - Response to Draft Request for Additional Information (LAR-19-005R1)2019-10-10010 October 2019 Enclosure 7 - Response to Draft Request for Additional Information (LAR-19-005R1) 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-19-1177, Supplement to Request for License Amendment and Exemption: Addition of In-Containment Refueling Water Storage Tank to Radiation Analyses (LAR-19-003S1)2019-10-0303 October 2019 Supplement to Request for License Amendment and Exemption: Addition of In-Containment Refueling Water Storage Tank to Radiation Analyses (LAR-19-003S1) NL-19-0709, Core Operating Limits Report, Cycle 21, Version 1, SNC Response to NRC Request for Additional Information2019-06-17017 June 2019 Core Operating Limits Report, Cycle 21, Version 1, SNC Response to NRC Request for Additional Information NL-19-0498, License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable SNC Response to NRC Request for ...2019-04-30030 April 2019 License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable SNC Response to NRC Request for ... ND-19-0289, Enclosure 1 - Revised Response to Request for Additional Information Question 1b Related to Request for Exemption from Operator Written Examination and Operating Test2019-04-16016 April 2019 Enclosure 1 - Revised Response to Request for Additional Information Question 1b Related to Request for Exemption from Operator Written Examination and Operating Test ND-19-0178, Supplement to Request for Exemption: 10 CFR Part 26 Visitor Access Requirements (Supplement 1)2019-03-0808 March 2019 Supplement to Request for Exemption: 10 CFR Part 26 Visitor Access Requirements (Supplement 1) ND-19-0216, Response to Request for Additional Information Related to Request for Exemption from Operator Written Examination and Operating Test2019-03-0404 March 2019 Response to Request for Additional Information Related to Request for Exemption from Operator Written Examination and Operating Test NL-18-1514, Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift.2019-01-31031 January 2019 Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift. ND-19-0007, Supplement to Request for Alternative: Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI/ISI-ALT-06S1)2019-01-28028 January 2019 Supplement to Request for Alternative: Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI/ISI-ALT-06S1) ND-18-1439, Revised Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017R1)2018-12-0303 December 2018 Revised Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017R1) NL-18-1181, Relief Requests VEGP-ISI-RR-05 and VEGP-ISI-RR-06, SNC Response to NRC Request for Additional Information2018-10-17017 October 2018 Relief Requests VEGP-ISI-RR-05 and VEGP-ISI-RR-06, SNC Response to NRC Request for Additional Information ND-18-1058, Supplement to Request for License Amendment and Exemption: Containment Pressure Analysis (LAR-17-043S1)2018-09-28028 September 2018 Supplement to Request for License Amendment and Exemption: Containment Pressure Analysis (LAR-17-043S1) NL-18-1130, Units 1 and 2 - Relief Request VEGP-ISI-RR-03: SNC Response to NRC Request for Additional Information2018-09-26026 September 2018 Units 1 and 2 - Relief Request VEGP-ISI-RR-03: SNC Response to NRC Request for Additional Information NL-18-1179, Response to NRC Request for Additional Information Tornado Missile Risk Evaluator SNC Supplemental2018-09-14014 September 2018 Response to NRC Request for Additional Information Tornado Missile Risk Evaluator SNC Supplemental 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-18-1040, Supplement to the Request for License Amendment: Technical Specification Changes to Support Operability During Mode 5 Vacuum Fill Operations (LAR-18-009S1)2018-08-10010 August 2018 Supplement to the Request for License Amendment: Technical Specification Changes to Support Operability During Mode 5 Vacuum Fill Operations (LAR-18-009S1) ND-18-1049, Supplement to Request for License Amendment: Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes (LAR-17-024S4)2018-08-0909 August 2018 Supplement to Request for License Amendment: Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes (LAR-17-024S4) NL-18-0815, Tornado Missile Risk Evaluator: SNC Response to NRC Request for Additional Information2018-07-26026 July 2018 Tornado Missile Risk Evaluator: SNC Response to NRC Request for Additional Information NL-18-0915, Enclosures 1, 3, 4 & 5 - Introduction and Overall Summary, Risk Quantification, Defense-in-Depth & Safety Margin and Supplemental Response to NRC Generic Letter 2004-022018-07-10010 July 2018 Enclosures 1, 3, 4 & 5 - Introduction and Overall Summary, Risk Quantification, Defense-in-Depth & Safety Margin and Supplemental Response to NRC Generic Letter 2004-02 ND-18-0646, Supplement to Request for License Amendment and Exemption: Changes to Tier 2* Departure Evaluation Process (LAR-17-037S3)2018-06-18018 June 2018 Supplement to Request for License Amendment and Exemption: Changes to Tier 2* Departure Evaluation Process (LAR-17-037S3) L-16-016, Response to NRC Rais Regarding Generic Letter 2016-012018-05-31031 May 2018 Response to NRC Rais Regarding Generic Letter 2016-01 ND-18-0643, Supplement to Request for License Amendment and Exemption Regarding Ventilation System Changes (LAR-16-030R1S2)2018-05-18018 May 2018 Supplement to Request for License Amendment and Exemption Regarding Ventilation System Changes (LAR-16-030R1S2) 2024-01-22
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Regulatory Affairs 3535 Colonnade Parkway Birmingham AL 35243 205 992 5000 WITHHOLD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390 (DECONTROLLED UPON REMOVAL OF ENCLOSURE 2 ATTACHMENT 1)
January 20, 2023 NL-23-0012 Docket Nos.: 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Units 1 and 2 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel By letter dated June 30, 2022, Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to allow for the use of lead test assemblies (LTAs) to demonstrate operating characteristics for accident-tolerant fuel (ATF). On August 1, 2022, the U.S. Nuclear Regulatory Commission (NRC) staff notified SNC that requests for additional information (RAIs) were necessary early in their review. By letter dated September 13, 2022, SNC responded to the RAIs. In December 2022, NRC staff conducted an audit and requested additional information. In response, SNC provides the following information. provides additional (non-proprietary) information to demonstrate that the LTA program does not significantly impact radiation source terms. provides additional (both proprietary in Attachment 1 and non-proprietary in ) information pertaining to coated cladding emissivity. provides the Westinghouse Affidavit, CAW-23-, for Withholding Proprietary Information from Public Disclosure. The affidavit sets forth the basis upon which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that the information that is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commission's regulations.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW-23- and should be addressed to Camille T. Zozula, Manager, Regulatory Compliance & Corporate Licensing, Westinghouse Electric Company, 1000 Westinghouse Drive, Suite 165, Cranberry Township, Pennsylvania 16066.
U. S. Nuclear Regulatory Commission NL-23-0012 Page 2 The conclusions of the No Significant Hazards Consideration Determination Analysis and Environmental Consideration contained in the LAR have been reviewed and are unaffected by these responses.
This letter contains no NRC commitments.
In accordance with 10 CFR 50.91, SNC is notifying the state of Georgia of this license amendment VXSSOHPHQW by transmitting a copy of this letter to the designated state official.
If you have any questions, please contact Ryan Joyce at 205.992.6468.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January 0, 2023.
C. A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company CAG/efb/cbg : Response to NRC Audit Questions Related to HBHE LTA - Core Sources Comparison (Non-Proprietary) : Response to NRC Audit Questions Related to HBHE LTA - Chromium Coated Cladding Emissivity Attachment 1 - Proprietary Attachment 2 - Non-Proprietary : Affidavit cc: Regional Administrator, Region ll NRR Project Manager - Vogtle 1&2 Senior Resident Inspector - Vogtle 1&2 State of Georgia Environmental Protection Division RType: CVC7000
Vogtle Electric Generating Plant - Units 1 and 2 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel ENCLOSURE 1 Response to NRC Audit Questions Related to HBHE LTA - Core Sources Comparison (Non-Proprietary)
Westinghouse Non-Proprietary Class 3 Page 1 of 6
Subject:
Vogtle Unit 2 High Burnup High Enrichment (HBHE) Lead Test Assemblies (LTA) - Core Sources Comparison During the virtual audit of the Vogtle ATP LTA LAR (ML22181B156) on December 8, 2022, NRC staff observed that parallel work on the Alternate Source Term (AST) (ML22181B066) transition and the transition to a fuel cycle featuring High Burnup High Enrichment (HBHE) Lead Test Assemblies (LTAs) was potentially confusing. Specifically, which analysis of record (AOR) core inventory is used as the basis to show that the LTA program does not significantly impact radiation source terms.
Table 1 shows the comparison using the AST core inventory. Table 2 shows the same comparison using the current AOR, consistent with Table 15A-3 of the Vogtle UFSAR.
From the comparisons contained in Tables 1 and 2, it is shown that the core inventory used in the current AOR and the core inventory used for the AST submittal are bounding with respect to the nuclides that contribute significantly to dose consequence evaluations.
© 2023 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 Page 2 of 6 Table 1 Comparison between AST Core Source Term (Including 10% Fuel Design Margin (FDM) added to the nominal activity) and Core Source Term for Fuel Cycle Implementing LTAs AST+10% Source LTA Fuel Cycle Group Group Name Nuclide Ratio (Ci) Source (Ci)
Kr-83m 1.29E+07 1.16E+07 0.90 Kr-85 1.12E+06 1.01E+06 0.90 Kr-85m 2.74E+07 2.45E+07 0.89 Kr-87 5.40E+07 4.81E+07 0.89 Kr-88 7.23E+07 6.43E+07 0.89 1 Noble Gases Xe-131m 1.42E+06 1.29E+06 0.91 Xe-133 2.15E+08 1.95E+08 0.91 Xe-133m 6.83E+06 6.23E+06 0.91 Xe-135 5.10E+07 4.59E+07 0.90 Xe-135m 4.59E+07 4.20E+07 0.92 Xe-138 1.87E+08 1.70E+08 0.91 Br-82 3.41E+05 3.20E+05 0.94 Br-83 1.28E+07 1.15E+07 0.90 Br-84 2.32E+07 2.07E+07 0.89 I-130 2.04E+06 1.90E+06 0.94 2 Iodine I-131 1.07E+08 9.79E+07 0.91 I-132 1.57E+08 1.43E+08 0.91 I-133 2.20E+08 2.00E+08 0.91 I-134 2.47E+08 2.24E+08 0.91 I-135 2.10E+08 1.91E+08 0.91 Cs-134 1.67E+07 1.56E+07 0.93 Cs-134m 4.50E+06 4.26E+06 0.95 Cs-135 4.51E+01 4.06E+01 0.90 Cs-136 5.37E+06 5.01E+06 0.93 3 Cesium Cs-137 1.18E+07 1.06E+07 0.90 Cs-138 2.04E+08 1.85E+08 0.91 Rb-86 2.07E+05 1.94E+05 0.93 Rb-88 7.36E+07 6.55E+07 0.89 Rb-89 9.64E+07 8.57E+07 0.89
Westinghouse Non-Proprietary Class 3 Page 3 of 6 Table 1 Comparison between AST Core Source Term (Including 10% Fuel Design Margin (FDM) added to the nominal activity) and Core Source Term for Fuel Cycle Implementing LTAs AST+10% Source LTA Fuel Cycle Group Group Name Nuclide Ratio (Ci) Source (Ci)
Sb-124 7.92E+04 7.63E+04 0.96 Sb-125 8.59E+05 7.89E+05 0.92 Sb-126 5.11E+04 4.70E+04 0.92 Sb-127 9.75E+06 9.03E+06 0.93 Sb-129 3.03E+07 2.80E+07 0.92 Te-125m 1.82E+05 1.67E+05 0.92 Te-127 9.55E+06 8.82E+06 0.92 Te-127m 1.58E+06 1.44E+06 0.91 4 Tellurium Te-129 2.84E+07 2.62E+07 0.92 Te-129m 5.44E+06 5.01E+06 0.92 Te-131 9.10E+07 8.31E+07 0.91 Te-131m 2.07E+07 1.90E+07 0.92 Te-132 1.53E+08 1.40E+08 0.91 Te-133 1.17E+08 1.07E+08 0.91 Te-133m 1.03E+08 9.39E+07 0.91 Te-134 1.96E+08 1.77E+08 0.90 Sr-89 1.02E+08 9.11E+07 0.89 Sr-90 8.70E+06 7.77E+06 0.89 5 Strontium Sr-91 1.27E+08 1.14E+08 0.89 Sr-92 1.37E+08 1.23E+08 0.90 Ba-137m 1.12E+07 1.01E+07 0.90 Ba-139 1.95E+08 1.77E+08 0.91 6 Barium Ba-140 1.89E+08 1.71E+08 0.91 Ba-141 1.75E+08 1.59E+08 0.91 Mo-99 2.00E+08 1.82E+08 0.91 Pd-109 3.49E+07 3.33E+07 0.95 Rh-103m 1.69E+08 1.56E+08 0.92 Rh-105 1.07E+08 9.96E+07 0.93 Rh-106 6.16E+07 5.76E+07 0.94 7 Ruthenium Ru-103 1.69E+08 1.56E+08 0.92 Ru-105 1.18E+08 1.10E+08 0.94 Ru-106 5.39E+07 5.03E+07 0.93 Tc-99 1.48E+03 1.33E+03 0.90 Tc-99m 1.77E+08 1.61E+08 0.91
Westinghouse Non-Proprietary Class 3 Page 4 of 6 Table 1 Comparison between AST Core Source Term (Including 10% Fuel Design Margin (FDM) added to the nominal activity) and Core Source Term for Fuel Cycle Implementing LTAs AST+10% Source LTA Fuel Cycle Group Group Name Nuclide Ratio (Ci) Source (Ci)
Ce-141 1.79E+08 1.62E+08 0.91 Ce-143 1.65E+08 1.49E+08 0.90 Ce-144 1.34E+08 1.21E+08 0.90 Np-237 3.44E+01 3.13E+01 0.91 Np-238 4.27E+07 4.04E+07 0.94 Np-239 2.07E+09 1.94E+09 0.93 8 Cerium Pu-238 3.02E+05 2.81E+05 0.93 Pu-239 3.09E+04 2.84E+04 0.92 Pu-240 4.50E+04 4.02E+04 0.89 Pu-241 1.30E+07 1.23E+07 0.94 Pu-242 2.06E+02 1.91E+02 0.93 Pu-243 4.22E+07 4.17E+07 0.99
Westinghouse Non-Proprietary Class 3 Page 5 of 6 Table 1 Comparison between AST Core Source Term (Including 10% Fuel Design Margin (FDM) added to the nominal activity) and Core Source Term for Fuel Cycle Implementing LTAs AST+10% Source LTA Fuel Cycle Group Group Name Nuclide Ratio (Ci) Source (Ci)
Am-241 1.28E+04 1.17E+04 0.91 Am-242 7.06E+06 6.83E+06 0.97 Am-243 2.53E+03 2.40E+03 0.95 Cm-242 3.69E+06 3.56E+06 0.97 Cm-244 3.71E+05 3.70E+05 1.00 Eu-154 6.80E+05 6.26E+05 0.92 Eu-155 2.87E+05 2.65E+05 0.92 Eu-156 2.46E+07 2.32E+07 0.94 La-140 1.96E+08 1.79E+08 0.91 La-141 1.76E+08 1.60E+08 0.91 La-142 1.70E+08 1.54E+08 0.91 La-143 1.63E+08 1.48E+08 0.90 Nb-95 1.84E+08 1.66E+08 0.90 Nb-95m 2.09E+06 1.89E+06 0.90 Nb-97 1.83E+08 1.66E+08 0.91 Nb-97m 1.73E+08 1.57E+08 0.91 Nd-147 7.08E+07 6.43E+07 0.91 9 Lanthanum Pm-147 1.77E+07 1.59E+07 0.90 Pm-148 1.93E+07 1.77E+07 0.92 Pm-148m 4.01E+06 3.64E+06 0.91 Pm-149 6.53E+07 6.00E+07 0.92 Pm-151 2.06E+07 1.90E+07 0.92 Pr-143 1.61E+08 1.45E+08 0.90 Pr-144 1.35E+08 1.22E+08 0.90 Pr-144m 1.88E+06 1.70E+06 0.90 Sm-151 4.47E+04 4.04E+04 0.90 Sm-153 4.93E+07 4.59E+07 0.93 Y-90 9.08E+06 8.13E+06 0.89 Y-91 1.34E+08 1.20E+08 0.89 Y-91m 7.39E+07 6.60E+07 0.89 Y-92 1.38E+08 1.24E+08 0.90 Y-93 1.57E+08 1.41E+08 0.90 Y-95 1.72E+08 1.56E+08 0.90 Zr-95 1.82E+08 1.64E+08 0.90 Zr-97 1.82E+08 1.65E+08 0.91
Westinghouse Non-Proprietary Class 3 Page 6 of 6 Table 2 Comparison between Measurement Uncertainty Recapture (MUR) Core Source Term and Core Source Term for Fuel Cycle Implementing LTAs MUR Program LTA Fuel Nuclide Source Cycle Source Ratio (Ci/Core) (Ci/Core)
I-131 1.03E+08 9.79E+07 0.95 I-132 1.50E+08 1.43E+08 0.95 I-133 2.10E+08 2.00E+08 0.95 I-134 2.26E+08 2.24E+08 0.99 I-135 1.95E+08 1.91E+08 0.98 Kr-85m 2.68E+07 2.45E+07 0.91 Kr-85 1.04E+06 1.01E+06 0.97 Kr-87 4.93E+07 4.81E+07 0.98 Kr-88 7.02E+07 6.43E+07 0.92 Xe-131m 7.13E+05 1.29E+06 1.82 Xe-133m 3.01E+07 6.23E+06 0.21 Xe-133 2.12E+08 1.95E+08 0.92 Xe-135m 4.18E+07 4.20E+07 1.01 Xe-135 4.65E+07 4.59E+07 0.99 Xe-138 1.69E+08 1.70E+08 1.00
Vogtle Electric Generating Plant - Units 1 and 2 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel ENCLOSURE 2 Response to NRC Audit Questions Related to HBHE LTA - Chromium Coated Cladding Emissivity Attachment 1 - Proprietary Attachment 2 - Non-Proprietary
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Information pertaining to coated cladding emissivity under LOCA conditions was discussed with NRC staff during the regulatory audit identified in Reference 1 and is provided herein. Figure 1 illustrates chromium coated cladding oxidation generated during simulated large break loss-of-coolant accident (LBLOCA) conditions for the Vogtle Accident Tolerant Fuel (ATF) lead test assemblies (LTAs). Figure 2 shows the emissivity of the resulting chromium oxide at the peak cladding temperature (PCT) time is
[ ]a,c to the emissivity of zirconium oxide for uncoated cladding. Details of Figures 1 and 2 are described further in the following discussion.
The orange line on Figure 1 shows the limiting LBLOCA cladding temperature in °C at the peak cladding temperature (PCT) elevation for the Vogtle LTAs; the LBLOCA PCT of [ ]a,c occurs at [
a,c
] . The blue line on Figure 1 shows the chromium oxide thickness in microns corresponding to the limiting LTA temperature transient. The oxide thickness is based on chromium oxidation kinetics derived from Westinghouse high temperature steam oxidation testing performed on chromium coated cladding. At the PCT time of [ ]a,c, the estimated chromium oxide thickness is approximately a,c
[ ] , as illustrated by the green dashed line on Figure 1.
Figure 2 compares the chromium oxide emissivity at the time of PCT to the emissivity modeled in the LTA evaluation, which reflects the emissivity of zirconium oxide for uncoated cladding. The cladding emissivity of oxidized zirconium modeled during the LBLOCA ranges from 0.6 (lower bound) to [
]a,c and is represented by the black line on Figure 2. Reference 2 provides emissivity data for oxidized chromium at various oxide-film thicknesses and temperatures. Using the data for the maximum temperature available (800°C), the emissivity for a chromium oxide film thickness of
[ ]a,c is estimated to be [ ]a,c. This emissivity is [ ]a,c, as shown by the green dashed line on Figure 2. Based on the Reference 2 data, chromium oxide emissivity increases with temperature; therefore, it is likely that the emissivity for [ ]a,c chromium oxide thickness will be higher at [ ]a,c compared to 800°C. The green dashed line in Figure 2, along with the red arrow indicating the emissivity would be higher at the higher temperatures, shows the estimated emissivity at the time of PCT for chromium coated cladding is [ ]a,c to that of uncoated cladding.
References
- 1. VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REGULATORY AUDIT IN SUPPORT OF REVIEW OF THE APPLICATION TO ALLOW USE OF LEAD TEST ASSEMBLIES FOR ACCIDENT-TOLERANT FUEL (EPID L-2022-LLA-0097), October 2022 (NRC ADAMS Accession Number ML22103A253).
- 2. Zhorov, G.A., Yagunov, K.A., Effect of thickness of oxide film on the emissivity and reflectivity of heat-resistant metals and alloys, Journal of Engineering Physics 34, 20-23 (1978).
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a,c a,c a,c Figure 1: Cladding Temperature at PCT Elevation and Cr Oxide Thickness
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a,c a,c Figure 2: Zirconium Oxide Emissivity Model and Cr Oxide Emissivity at PCT Time
Vogtle Electric Generating Plant - Units 1 and 2 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel ENCLOSURE 3 Affidavit
Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-23-001 Page 1 of 3 Commonwealth of Pennsylvania:
County of Butler:
(1) I, Anthony Schoedel, Manager, eVinci Licensing & Configuration Management, 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 Enclosure 2 to NL-23-0012 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 others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-23-001 Page 2 of 3 (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.
(6) The attached documents are bracketed and marked to indicate the bases for withholding. The justification for withholding 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 (5)(a) through (f) of this Affidavit.
Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-23-001 Page 3 of 3 I declare that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief. I declare under penalty of perjury that the foregoing is true and correct.
Executed on: 1/18/2023 _____________________________
Signed electronically by Anthony Schoedel