Letter Sequence Response to RAI |
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Category:Letter type:ND
MONTHYEARND-24-0019, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2024-02-0101 February 2024 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0912, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2024-01-0202 January 2024 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0881, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-12-0404 December 2023 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0817, (Vegp), Units 3 and 4 - Report of UFSAR Chapter 14 Changes to the Initial Test Program in Accordance with License Condition 2.D.(7)(a)2023-11-17017 November 2023 (Vegp), Units 3 and 4 - Report of UFSAR Chapter 14 Changes to the Initial Test Program in Accordance with License Condition 2.D.(7)(a) ND-23-0823, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-11-0303 November 2023 Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0723, (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-10-0404 October 2023 (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0697, (Vegp), Unit 4, Submittal of Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-09-0505 September 2023 (Vegp), Unit 4, Submittal of Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0669, (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-08-0707 August 2023 (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0205, (Vegp), Unit 3 - Combined License (COL) License Condition 2.D.(5)(d) Completion of Power Ascension Tests2023-07-28028 July 2023 (Vegp), Unit 3 - Combined License (COL) License Condition 2.D.(5)(d) Completion of Power Ascension Tests ND-23-0618, Resubmittal of ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.07c.ii.a (Index Number 797)2023-07-20020 July 2023 Resubmittal of ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.07c.ii.a (Index Number 797) ND-23-0609, Notification of Completion of All ITAAC2023-07-20020 July 2023 Notification of Completion of All ITAAC ND-23-0608, ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72) ND-23-0607, ITAAC Closure Notification on Completion of ITAAC 2.1.02.02a (Index Number 13)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.02.02a (Index Number 13) ND-22-0796, ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813) ND-23-0459, ITAAC Closure Notification on Completion of ITAAC 2.6.01.04d (Index Number 587)2023-07-19019 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.01.04d (Index Number 587) ND-23-0162, ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165)2023-07-19019 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165) ND-23-0575, ITAAC Closure Notification on Completion of ITAAC 2.6.01.04e (Index Number 588)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.01.04e (Index Number 588) ND-23-0439, ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265) ND-23-0552, Southern Nuclear Operating Company, Vogtle Electric Generating Plant, Unit 4, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02c (Index Number 624)2023-07-18018 July 2023 Southern Nuclear Operating Company, Vogtle Electric Generating Plant, Unit 4, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02c (Index Number 624) ND-23-0483, ITAAC Closure Notification on Completion of ITAAC 2.1.01.04 (Index Number 4)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.01.04 (Index Number 4) ND-23-0586, ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159)2023-07-17017 July 2023 ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159) ND-23-0610, ITAAC Closure Notification on Completion of ITAAC Item 2.6.03.04c (Index Number 603)2023-07-17017 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.6.03.04c (Index Number 603) ND-23-0573, ITAAC Closure Notification on Completion of 2.4.02.02a (Index Number 497)2023-07-16016 July 2023 ITAAC Closure Notification on Completion of 2.4.02.02a (Index Number 497) ND-23-0406, ITAAC Closure Notification on Completion of ITAAC Item 2.4.02.02b (Index Number 498)2023-07-16016 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.4.02.02b (Index Number 498) ND-22-0816, ITAAC Closure Notification of Completion of ITAAC 2.1.02.05a (Index Number 19)2023-07-15015 July 2023 ITAAC Closure Notification of Completion of ITAAC 2.1.02.05a (Index Number 19) ND-23-0603, ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831) ND-23-0446, ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250) ND-23-0594, ITAAC Closure Notification on Completion of ITAAC 2.6.05.02.ii (Index Number 629)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.05.02.ii (Index Number 629) ND-23-0601, ITAAC Closure Notification on Completion of ITAAC Item 2.7.05.02.i (Index Number 719)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.7.05.02.i (Index Number 719) ND-23-0606, ITAAC Closure Notification on Completion of ITAAC 2.5.04.02.i (Index Number 557)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.5.04.02.i (Index Number 557) ND-23-0476, ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355) ND-23-0499, ITAAC Closure Notification on Completion of ITAAC 2.7.01.14 (Index Number 700)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.7.01.14 (Index Number 700) ND-23-0588, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78) ND-23-0121, ITAAC Closure Notification on Completion of ITAAC C.2.6.09.07 (Index Number 667)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC C.2.6.09.07 (Index Number 667) ND-23-0122, ITAAC Closure Notification on Completion of ITAAC C.2.6.09.08a (Index Number 668)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC C.2.6.09.08a (Index Number 668) ND-23-0597, ITAAC Closure Notification on Completion of ITAAC 2.5.02.06a.ii (Index Number 530)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.5.02.06a.ii (Index Number 530) ND-23-0002, ITAAC Closure Notification on Completion of ITAAC 2.2.05.07c (Index Number 270)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.05.07c (Index Number 270) ND-23-0111, ITAAC Closure Notification on Completion of ITAAC 2.6.09.05c (Index Number 646)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.09.05c (Index Number 646) ND-22-0980, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.06.i (Index Number 75)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.06.i (Index Number 75) ND-23-0587, ITAAC Closure Notification on Completion of ITAAC 2.6.02.02c (Index Number 595)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.02.02c (Index Number 595) ND-23-0461, ITAAC Closure Notification on Completion of ITAAC 2.6.09.13a (Index Number 652)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.09.13a (Index Number 652) ND-23-0543, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02a (Index Number 622)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02a (Index Number 622) ND-23-0394, ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703) ND-23-0592, ITAAC Closure Notification on Completion of 2.7.06.03.i (Index Number 726)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of 2.7.06.03.i (Index Number 726) ND-23-0589, ITAAC Closure Notification on Completion of ITAAC 2.6.03.04a (Index Number 601)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.03.04a (Index Number 601) ND-23-0581, ITAAC Closure Notification on Completion of ITAAC 2.2.04.02a (Index Number 220)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.04.02a (Index Number 220) ND-23-0486, ITAAC Closure Notification on Completion of ITAAC 2.2.01.11a.iv (Index Number 117)2023-07-11011 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.01.11a.iv (Index Number 117) ND-23-0559, CFR26.719(c)(1) 30-Day Report for a Blind Sample Analysis Error2023-07-11011 July 2023 CFR26.719(c)(1) 30-Day Report for a Blind Sample Analysis Error ND-23-0443, ITAAC Closure Notification on Completion of ITAAC 2.3.10.07a.ii (Index Number 444)2023-07-0808 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.3.10.07a.ii (Index Number 444) ND-23-0183, ITAAC Closure Notification on Completion of ITAAC Item 2.3.11.03b (Index Number 454)2023-07-0808 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.3.11.03b (Index Number 454) 2024-02-01
[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
[Table view] |
Text
B. H. Whitley Southern Nuclear Director Operating Company, Inc.
Regulatory Affairs 42 Inverness Center Parkway Birmingham, AL 35242 Tel 205.992.7079 Fax 205.992.5296 March 8, 2018 Docket Nos.: 52-025 ND-18-0279 52-026 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4 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-07S2)
Ladies and Gentlemen:
By letter dated July 6, 2017, Southern Nuclear Operating Company (SNC) submitted a request for an alternative in accordance with 10 CFR 50.55a for preservice inspection of the Reactor Vessel Nozzle Inner Radius Sections [ML17192A125]. On October 30, 2017, the Nuclear Regulatory Commission (NRC) staff issued a draft request for additional information (RAI)
[ML17303A270]. The responses to the RAI questions were provided on December 8, 2017
[ML17342A826]. The NRC provided a second draft RAI on February 6, 2018 and additional clarification was provided during the February 15, 2018 public meeting. On February 23, 2018, the RAI was issued [ML18054A672]. The responses to the RAI questions are included in .
The supplemental information provided in this letter does not impact the scope or conclusions of the original alternative.
This letter contains no regulatory commitments. This letter has been reviewed and determined not to contain security related information.
Should you have any questions, please contact Mr. Corey Thomas at (205) 992-5221.
U.S. Nuclear Regulatory Commission ND-18-0279 Page 2 of4 I declare under penalty of pe~ury that the foregoing is true and correct. Executed on the 81h of March 2018.
Respectfully submitted, Brian H. Whitley Director, Regulatory Affairs Southern Nuclear Operating Company
Enclosures:
- 1) - 2) (previously submitted with the original code alternative, VEGP 3&4-PSI-ALT-07, in SNC letter ND-17-1121)
- 3) (previously submitted in VEGP 3&4-PSI-ALT-07S1, in SNC letter ND-17-2032)
- 4) 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-07S2)
U.S. Nuclear Regulatory Commission ND-18-0279 Page 3 of 4 cc:
Southern Nuclear Operating Company / Georgia Power Company Mr. S. E. Kuczynski (w/o enclosure)
Mr. M. D. Rauckhorst Mr. D. G. Bost (w/o enclosure)
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U.S. Nuclear Regulatory Commission ND-18-0279 Page 4 of 4 Oglethorpe Power Corporation Mr. M. W. Price Mr. K. T. Haynes Ms. A. Whaley Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Mr. L. Oriani (w/o enclosure)
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Mr. M. Corletti Mr. M. L. Clyde Ms. L. Iller Mr. D. Hawkins Mr. J. Coward Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. A. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.
Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham Mr. R. Grumbir, APOG NDDocumentinBox@duke-energy.com, Duke Energy Mr. S. Franzone, Florida Power & Light
Southern Nuclear Operating Company ND-18-0279 Enclosure 4 Vogtle Electric Generating Plant (VEGP) Units 3 and 4 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-07S2)
(This Enclosure consists of 4 pages, including this cover page)
ND-18-0279 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-07S2)
The following are questions provided by the NRC Staff on February 23, 2018 (ADAMS Accession Number ML18054A672) regarding the review of Southern Nuclear Operating Company (SNC) Proposed Alternative VEGP 3&4-PSI-ALT-07 in accordance with 10 CFR 50.55a(z)(1) - Application of VT-1 Visual Examination Methodology for Preservice Inspection of the Reactor Vessel Nozzle Inner Radius Sections (ADAMS Accession Number ML17303A270) submitted on October 30, 2017 and Response to Request for Additional Information (RAI)
Regarding Application of VT-1 Visual Examination Methodology for Preservice Inspection of the Reactor Vessel Nozzle Inner Radius Sections (VEGP 3&4-PSI-ALT-07S1, ADAMS Accession Number ML17342A826) submitted on December 8, 2017. Responses are provided below for each RAI question.
RAI Question 11:
In RAI Question 1.a, the NRC staff requested confirmation that the alternative examinations will be performed in accordance with the ASME Code as conditioned in § 50.55a of Title 10 of the Code of Federal Regulations (10 CFR). The NRC staff requests confirmation that the proposed remote VT-1 visual examination will be performed in accordance with ASME Code,Section XI, as conditioned in 10 CFR 50.55a, which requires that a visual examination performed instead of an ultrasonic examination has a magnification that has a resolution sensitivity to resolve 0.044 inch (1.1 mm) lower case characters without an ascender or descender (e.g., a, e, n, v).
SNC Response to RAI Question 11:
The proposed remote VT-1 visual examination will be performed in accordance with ASME Code,Section XI, as conditioned in 10 CFR 50.55a, which requires that a visual examination performed instead of an ultrasonic examination has a magnification that has a resolution sensitivity to resolve 0.044 inch (1.1 mm) lower case characters without an ascender or descender (e.g., a, e, n, v).
RAI Question 12:
In RAI Question 1.b.ii, the NRC staff requested a description of the alternative examinations.
The NRC staff requests confirmation that the proposed remote VT-1 visual examination will cover essentially 100 percent of the examination volume for the inlet, outlet, and DVI nozzles as defined in ASME Code,Section XI, Figure IWB-2500-7(b). If not, then provide sketches or some other means detailing the examination volume for the inlet, outlet, and DVI nozzles that will be covered by the proposed remote VT-1 visual examination.
SNC Response to RAI Question 12:
The proposed remote VT-1 visual examination will cover essentially 100 percent of the ASME Code,Section XI, Figure IWB-2500-7(b) section M-N surface area for the inlet, outlet, and DVI nozzles.
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ND-18-0279 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-07S2)
RAI Question 13:
In the letter dated December 8, 2017, SNC stated that the stresses at the nozzle corner region for the Advanced Passive 1000 (AP1000) are similar to the operating fleet. In order to determine whether the operational experience from the current operating fleet applies, the NRC staff requests the following information:
- a. The design stress state and operating stresses at the nozzle corner region from the AP1000 reactor pressure vessel design report for each inlet, outlet, and DVI nozzle. In addition, these stresses should specifically include any thermal cycling and stratification loading for each inlet, outlet, and DVI nozzle.
- b. An evaluation that compares the design stress state and operating stresses at the nozzle corner region for each inlet, outlet, and DVI nozzle of the AP1000 provided in (a) above to the design stress state and operating stresses in the nozzle corner region of similar designed nozzles for the current operating fleet. This should include a discussion of why each inlet, outlet, and DVI nozzle is similar to the operating fleet nozzle designs.
SNC Response to RAI Question 13:
The pressure stresses in the AP1000 nozzle corner regions are similar to operating vessels of a similar size and geometry. However, the stresses from the thermal transients would be different for the AP1000 design. It is for this reason that the fracture analyses documented in Section 5.0 of the Alternative Request (ML17192A125) were performed using AP1000 specific stress data.
The fracture evaluation results discussed in the technical basis for Code Case N-648-1 (Reference 1) were calculated using stresses in the nozzle corner regions for the operating fleet. Thus, the fracture analyses results for the AP1000 provided in the Alternative Request are directly comparable to those for the operating fleet. Conversely, the stress information requested by the NRC staff is not easily obtained, nor would it provide a better comparison than the fracture analyses results already provided. Stress data by itself would not provide context or acceptance criteria without also performing the facture analyses to determine acceptable flaw sizes considering the operating life of the plant. Therefore, the following text which further explains the fracture analyses results documented in the Alternative Request (ML17192A125), is provided as an alternative to the data requested by the NRC staff:
The technical basis for Code Case N-648-1 (Reference 1) included a fracture evaluation that demonstrated tolerance for flaws greater than 3 inches in the reactor vessel inner radii for the operating fleet with a 40 year design life. This result provided assurance that visual examination methods would be sufficient for detecting flaws within the inner radii that are well below the acceptable size calculated using ASME Section XI methods. Likewise, the analyses presented in Section 5.0 of the Alternative Request (ML17192A125) reached a similar conclusion: that the AP1000 nozzle inner radii are tolerant of flaws greater than 3 inches in depth, considering a 60 year design life (see Table 2 of ML17192A125). The main difference between the two analyses is that the allowable flaw sizes for the operating fleet were calculated using linear elastic fracture mechanics (LEFM) only, but the analyses results presented for the AP1000 used both LEFM and elastic plastic fracture mechanics (EPFM) methods. Both calculations were performed using ASME Section XI methodology.
The fracture evaluation guidelines of ASME Section XI, Appendix A (Reference 2) were used in the initial approach for evaluation of flaw tolerance for AP1000 nozzle corners. The Appendix A Page 3 of 4
ND-18-0279 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-07S2) methods are based on LEFM and are more conservative than EPFM methods such as those provided in Section XI Appendix K or Code Case N-749 (Reference 3). This more conservative LEFM approach is similar to the calculation methods used to determine the allowable flaw sizes for the operating fleet in (Reference 1). The LEFM results in the Alternative Request are smaller compared to the 3 inch allowable flaw size calculated for the operating fleet. As shown in Table 2 of the Alternative Request, the fatigue crack growth (FCG) results show that the maximum initial flaw sizes that will not grow beyond the allowable end of evaluation period flaw sizes are less than 1 inch considering 10 and 60 year operating periods. Although the allowable flaw sizes are less than 3 inches, they are considered to be acceptable because they are less than the flaw size that may have been placed into service considering the acceptance criteria of NB-2545 for magnetic partial examination (0.094 inch depth - see Section 5 of the Alternative Request).
Because the LEFM flaw evaluations produced notably smaller allowable flaws for the AP1000 nozzle designs than for the operating fleet, a second set of calculations were performed using the EPFM method provided in Code Case N-749. The Code Case is a valid approach for evaluating the AP1000 nozzles for flaw tolerance as discussed in the Alternative Request and previous RAI responses. The EPFM fracture analysis results listed in Table 2 of the Alternative Request show that the allowable flaw sizes for the inlet, outlet and DVI nozzles are all over 3 inches, which is the same conclusion reached in (Reference 1) for the operating fleet nozzles. This conclusion also provides assurance that flaws large enough to be of concern within the AP1000 nozzle corner regions would be detected by the VT-1 examination proposed in the Alternative Request.
Given this discussion, the NRC staff is requested to consider the results presented in Table 2 of the Alternative Request (ML17192A125) as a comparison to the results presented in the technical basis for Code Case N-648-1 (Reference 1) in lieu of the stress data requested in the RAI. The results in Table 2 of the Alternative Request (ML17192A125) provide a direct comparison of ASME Section XI fracture mechanics results for the operating fleet and the AP1000. The final conclusion reached is that both the operating fleet and the AP1000 design are tolerant of flaws greater than 3 inches in depth within the reactor vessel inner radii regions, which provides assurance that any flaws detected by visual examination would be well below the acceptable size based on ASME Section XI fracture evaluation methods.
References:
- 1. W. H. Bamford, D. Kurek, B. A. Bishop, N. Closky, G. Stevens, L. Becker, S. Ranganath, Technical Basis for Elimination of Reactor Vessel Nozzle Inner Radius Inspections, 2001 Pressure Vessel and Piping Conference Proceeding, American Society of Mechanical Engineers.
- 2. ASME Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda, Rules for Inservice Inspection of Nuclear Power Plant Components, American Society of Mechanical Engineers.
- 3. ASME Boiler and Pressure Vessel Code, Case N-749: Alternative Acceptance Criteria for Flaws in Ferritic Steel Components Operating in the Upper Shelf Temperature Range Section XI, Division 1, March 16, 2012.
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