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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
Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway Birmingham, AL 35243 January 28, 2019 Docket Nos.: 52-025 ND-19-0007 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 Supplement to Request for Alternative:
Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI/ISI-ALT-06S1)
Ladies and Gentlemen:
By letter dated October 19, 2018, Southern Nuclear Operating Company (SNC) submitted a request for an alternative to the requirements of Section XI, IWB-2500, of the ASME Boiler and Pressure Vessel (B&PV) Code, 2007 Edition through 2008 Addenda (code of record) for Vogtle Electric Generating Plant (VEGP) Units 3 and 4 in accordance with 10 CFR 50.55a
[ML18292A789]. The proposed request for alternative is applicable to preservice and inservice inspection (PSI/ISI) of specific valve-to-pipe welds listed in Section XI Table IWB-2500-1 Examination Category B-J and Table IWC-2500-1 Examination Category C-F-1, and ASME Class 3 valve-to-pipe welds treated as Class 2 due to leak-before-break (LBB) criteria. On December 13, 2018, the Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) [ML18347B589].
The responses to the RAI questions are included in the Enclosure 5. This supplement does not impact the original scope of the Code alternative.
Additionally, per this letter, the duration of the proposed Alternative is revised to include the Second Inservice Inspection Interval. The revised duration of the request includes ASME Section XI Preservice Examinations and the First and Second Inservice Inspection Intervals.
This letter, including enclosures, has been reviewed and confirmed to not contain security-related information. This letter contains no regulatory commitments. Should you have any questions, please contact Mr. Corey Thomas at (205) 992-5221.
U.S. Nuclear Regulatory Commission ND-19-0007 Page 2 of 4 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 281h day of January 2019.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY Amy G. Aughtman Licensing Manager ND Regulatory Affairs Enclosures 1 - 4: (previously submitted with the original code alternative, VEGP 3&4-PSI-ALT-06, in SNC letter ND-18-1185) : Vogtle Electric Generating Plant (VEGP) Units 3 and 4 - Response to Request for Additional Information Regarding Preservice and lnservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI-ALT-06S1)
U.S. Nuclear Regulatory Commission ND-19-0007 Page 3 of 4 cc:
Southern Nuclear Operating Company / Georgia Power Company Mr. S. E. Kuczynski (w/o enclosure)
Mr. D. G. Bost (w/o enclosure)
Mr. M. D. Meier (w/o enclosure)
Mr. D. H. Jones (w/o enclosure)
Mr. J. B. Klecha Mr. G. Chick Mr. D. L. McKinney (w/o enclosure)
Mr. T. W. Yelverton (w/o enclosure)
Mr. B. H. Whitley Ms. C. A. Gayheart Mr. C. R. Pierce Ms. A. G. Aughtman Mr. D. L. Fulton Mr. M. J. Yox Mr. C. T. Defnall Mr. J. Tupik Mr. W. A. Sparkman Ms. A. C. Chamberlain Mr. S. Leighty Mr. E. Riffle Ms. K. Roberts Document Services RTYPE: VND.LI.L00 File AR.01.02.06 Nuclear Regulatory Commission Mr. W. Jones (w/o enclosure)
Ms. J. Dixon-Herrity Mr. C. Patel Ms. J. M. Heisserer Mr. B. Kemker Mr. G. Khouri Ms. S. Temple Mr. F. Brown Mr. C. J. Even Mr. A. Lerch Mr. S. Walker State of Georgia Mr. R. Dunn
U.S. Nuclear Regulatory Commission ND-19-0007 Page 4 of 4 Oglethorpe Power Corporation Mr. M. W. Price 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)
Mr. T. Rubenstein (w/o enclosure)
Mr. M. Corletti Mr. M. L. Clyde 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 NDDocumentinBox@duke-energy.com, Duke Energy Mr. S. Franzone, Florida Power & Light
Southern Nuclear Operating Company ND-19-0007 Enclosure 5 Vogtle Electric Generating Plant (VEGP) Units 3 and 4 Response to Request for Additional Information Regarding Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI-ALT-06S1)
(Enclosure consists of 4 pages, including this cover page.)
ND-19-0007 Vogtle Electric Generating Plant (VEGP) Units 3 and 4 - Response to Request for Additional Information Regarding Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI-ALT-06S1)
The following are questions provided by the NRC Staff on December 13, 2018 (ADAMS Accession Number ML18347B589) regarding the review of Southern Nuclear Operating Company (SNC) Proposed Alternative VEGP 3&4-PSI-ALT-06 in accordance with 10 CFR 50.55a(z)(1) - Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (ADAMS Accession Number ML18292A789) submitted on October 19, 2018.
Responses are provided below for each RAI question.
RAI Question ALT-06-1-1:
By letter dated October 19, 2018, Southern Nuclear Operating Company, Inc. (SNC), submitted Request for Alternative No. VEGP 3&4-PSI/ISI-ALT-06 to the U.S. Nuclear Regulatory Commission (NRC) for Vogtle Electric Generating Plant (VEGP) Units 3 and 4 (ADAMS Accession No. ML18292A787) in accordance with 10 CFR 50.55a(z)(1) which permits the approval of alternatives to the requirements of the American Society of Mechanical Engineers (ASME) Code based on the licensee demonstrating that the proposed alternative would provide an acceptable level of quality and safety. 10 CFR 50.55a(g)(3)(i) and (ii) states that components classified as ASME Code Class 1, 2, and 3 must be designed and be provided with access to satisfy the preservice examination requirements set forth in ASME Section III and Section XI. The Vogtle Units 3 and 4 UFSAR (Section 5.2.4.2) states that components and welds requiring inservice inspection (and by default preservice inspection) are designed to allow for the application of the required inservice inspection methods (and preservice inspection methods). Therefore, the welds and adjacent base material are required to be inspected in accordance with ASME Code Section III and Section XI. The alternative requests NRC approval to use an alternative to the requirements of IWB-2500 to Section XI of the ASME Code, 2007 Edition through 2008 Addenda to eliminate the requirement for a volumetric examination of the valve material in specific valve-to-pipe welds during preservice and inservice inspection.
Staff of the Materials and Chemical Engineering Branch in the Office of New Reactors reviewed and evaluated the information provided by the licensee, and has determined that the following information is needed to ensure the integrity of the valve-to-pipe welds based on inspection and operational experience.:
The request states that the 2008 Addenda of Section XI of the ASME BP&V Code removed the volumetric examination requirement for the welds in valve bodies. There is no information provided concerning the operating experience of these types of valve-to-pipe welds. The staff cannot approve this alternative to not inspect the valve material without operating experience.
Discuss how the basis for removing the volumetric examination for the welds in the valve bodies applies to the piping welds in this alternative which are thinner (less margin) and may have different stresses. This should include the operating experience of similar types of valve-to-pipe welds in the discussion.
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ND-19-0007 Vogtle Electric Generating Plant (VEGP) Units 3 and 4 - Response to Request for Additional Information Regarding Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI-ALT-06S1)
SNC Response to RAI Question ALT-06-1-1:
The proposed code alternative seeks to remove the volumetric examination of the valve base material. However, essentially 100% of the weld material and piping base metal will be examined as required by ASME Section XI, including ASME Section XI Appendix VIII.
First, a review was performed and operating experience was documented in the NRC issued Grimes letter [ML003717179] for valve body cracks operating experience. The review included the Sequence Coding and Search System (SCSS), the Nuclear Plant Reliability Data System (NPRDS) database, and foreign event files for thermal fatigue. The SCSS search covered the years from 1979 to 1999, and the NPRDS search covered 1987 to 1996. Ten valve body indications were identified over this time period. Of that 10, 5 failures were associated with stainless steel valve bodies. The 5 events were attributed to wall thinning, transgranular stress corrosion cracking, thermal stratification, indeterminate, and preferential corrosion at a weld repair. It should be noted that none of the events resulted in catastrophic failure of the valve, rather through-wall leaks were identified per leak detecting sensors. This review provides assurance that the operating experience associated with stainless steel valve bodies was exemplary for the time period from 1979 to 1999.
Second, a review for the time period of January 1, 2000 to January 7, 2019 was conducted to identify operating experience for indications in valve-to-pipe welds. A search was performed of Licensee Event Reports (LERs) that contain the following sets of keywords: 1) valve, weld, body, indication; and 2) valve, weld, body, crack. Additional industry searches using all of the following keywords: weld, crack, leak, and valve body. The search resulted in 70 instances of operating experience, with 23 deemed to be relevant to valve-to-pipe welds. In summary, two failures were a result of a valve body defect but neither were associated with a valve to pipe weld interface, one failure was deemed attributable to valve thinning, one failure was due to outer diameter stress corrosion cracking due to chloride contamination at a valve-to-pipe weld, and all others were located in small bore locations that are not required to be ultrasonically examined by ASME Section XI. One instance of operating experience was identified for valve to piping welds that are in the scope of ASME Section XI to be ultrasonically examined, but this failure originated from the outer diameter, while Section XI ultrasonic examinations are performed on the inner diameter.
No operating experience was identified for valve to piping welds that are in the scope of ASME Section XI to be ultrasonically examined.
The reviews documented encompass operating experience of valve body failures at valve-to-pipe weld interfaces for 2400 reactor-years of operating U.S. PWRs and 1300 reactor-years for operating U.S. BWRs. Per this review, there has been only one identified valve-to-piping weld failure subject to volumetric examination per ASME Section XI and this was due to a failure mode that was initiated from the outer diameter of the material which is not the location for which ASME Section XI volumetric exams are conducted for valve-to-pipe welds. This review provides high assurance that there are no adverse trends related to valve-to-piping weld failures on the valve body side that would suggest that volumetric examination of the valve body volume currently required to be inspected per ASME Section XI is warranted. This review also provides high assurance that the operational experience for large bore valve to piping welds (i.e.,
valve-to-piping welds that require volumetric examination in accordance with ASME Section XI) is excellent.
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ND-19-0007 Vogtle Electric Generating Plant (VEGP) Units 3 and 4 - Response to Request for Additional Information Regarding Preservice and Inservice Inspection Requirements for Specific Valve-to-Pipe Welds (VEGP 3&4-PSI-ALT-06S1)
Additionally, the flaw analyses conducted in the Grimes letter [ML003717179] and in Attachment 3 of the Alternative Request demonstrated acceptable flaw tolerance margins based on fracture mechanics evaluation for postulated flaw sizes. The Grimes letter demonstrated a very conservative 1.35 in. long through-wall crack is necessary before catastrophic failure would occur. This analysis, which was based on the R6 Failure Assessment Diagram (FAD) used conservative lower bound fracture toughness in the evaluation to demonstrate high flaw-tolerance of severely aged valve materials. The flaw tolerance in Attachment 3 of the Alternative Request also evaluated flaw stability for stainless steel valves under design normal / upset / emergency /
test / faulted conditions in accordance with ASME Section XI. The fatigue crack growth evaluation demonstrated insignificant amounts of crack growth under normal operating conditions, which aligns with operating experience for stainless steel components in general. Thus, the flaw tolerance evaluations are conservative and limiting; furthermore, when coupled with operating experience, these analyses agree well with the fact that there has been a very limited number of operating concerns for valves.
RAI Question ALT-06-1-2:
The request states that this alternative is not recommending any additional visual examinations.
Please clarify this statement by confirming that the visual examinations required by Table IWB-2500-1, Category B-M-2 in Section XI of the ASME BP&V Code will still be performed as part of the ISI program. If these visual examinations are not performed, provide the basis for removing the internal visual inspection which provides continued assurance of the structural integrity of the valve.
SNC Response to RAI ALT-06-1-2:
The visual examinations required by Table IWB-2500-1, Category B-M-2 in Section XI of the ASME B&PV Code will still be performed as part of the ISI program. The proposed alternative does not seek to make any changes to these examinations.
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