ML23184A047
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| ML23184A047 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/03/2023 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML23184A047 (1) | |
Similar Documents at Vogtle | |
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Category:Graphics incl Charts and Tables
MONTHYEARML23289A2302023-10-16016 October 2023
[Table view]Discrimination Allegations Received Sept - 2023 ML23289A2292023-10-16016 October 2023 Allegations Substantiated with Regulatory Response - Sept 2023 ML23289A2272023-10-16016 October 2023 Allegations Substantiated - September 2023 ML23289A2232023-10-16016 October 2023 Allegations Received from All Sources External to the NRC - Sept 2023 ML23289A2212023-07-28028 July 2023 Allegations Open - Sept 2023 ML22348A0872023-07-25025 July 2023 Enclosure - VEGP Unit 4 - 103g - Final Memorandum Table ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23093A0862023-04-0303 April 2023 Dashboard Report 4-3-2023 ML22214B4932023-02-0808 February 2023 Enclosure 2 - Licensing Actions Status Table ML22214B4902023-02-0808 February 2023 Enclosure 1 - Operational Program Inspection Status Table ML23038A0082023-02-0707 February 2023 Construction Reactor Oversight Process Resources Report February 7, 2023 ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22230C5162022-08-18018 August 2022 Dashboard Report 8-18-2022 ML22208A0242022-08-0101 August 2022 103g - Final Memorandum - Enclosure ML22206A1682022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22206A1712022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22201A0442022-07-20020 July 2022 Voices Dashboard Report for Vogtle Unit 3 as of July 20, 2022 ML22186A0332022-07-0505 July 2022 Dashboard Report 7-5-2022 ML22186A0342022-07-0505 July 2022 Dashboard Report 7-5-2022 ML22173A0122022-06-22022 June 2022 Dashboard Report 6-22-2022 ML22144A0492022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22144A0502022-05-24024 May 2022 Dashboard Report 5-24-2022 ND-22-0242, Request for Alternative: Alternative Requirements for Main Turbine System Valve Testing (VEGP 3&4-IST-ALT-02)2022-04-0808 April 2022 Request for Alternative: Alternative Requirements for Main Turbine System Valve Testing (VEGP 3&4-IST-ALT-02) ML22091A3162022-04-0101 April 2022 NRC Initial Test Program and Operational Programs Inspection Reports 05200025/2022002, 05200026/2022002 ML22087A0962022-03-28028 March 2022 Dashboard Report 3-28-2022 ML21277A0762021-10-0404 October 2021 Vog 4 Dashboard 10-4-2021 ML21215A0072021-08-0303 August 2021 Dashboard Report 8-2-2021 ML21215A0062021-08-0303 August 2021 Dashboard Report 8-2-2021 ML21160A0382021-06-0909 June 2021 Construction Reactor Oversight Process Resources Report June 2021 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21008A0042021-01-0404 January 2021 Dashboard Report 1-4-2021 ML20343A0742020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20281A3872020-10-0101 October 2020 Dashboard Report 10-1-2020 ML20281A4002020-10-0101 October 2020 Dashboard Report 10-1-2020 ML20183A0902020-09-24024 September 2020 Initial Commission Memo Regarding Status of ITAAC Closure, Inspection, and Licensing Activities for Vogtle Electric Generating Plant, Unit 3 ML20191A3982020-08-14014 August 2020 Table 2 - Vogtle, Units 3 and 4, Resident Inspector Inspection Samples and Hours ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ML20121A2902020-04-30030 April 2020 Construction Reactor Oversight Process Resources 1st Quarter CY2020 ML20038A3072020-02-0707 February 2020 Construction Reactor Oversight Process Resources. Quarterly Update. 1st Quarter 2020 ML20035C5542020-02-0404 February 2020 Attachment 1 - Targeted ITAAC Listing for Vogtle Electric Generating Plant Units 3 and 4 ML20035C5612020-02-0404 February 2020 Attachment 2 - Targeted ITAAC Family Listing for Vogtle Electric Generating Plant Units 3 and 4 ML20035C5702020-02-0404 February 2020 Attachment 3 - Targeted ITAAC Changes for Vogtle Electric Generating Plant Units 3 and 4 ML20007D9042020-01-0808 January 2020 Table of Proposed ROP Baseline Samples for Vogtle Site ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15106A3612015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Example Vogtle 1 and 2, Change Justification Matrix ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T ML14078A6202014-04-0101 April 2014 Enclosure 2 - SAMG Entry Flowcharts 2023-07-03 Category:Report MONTHYEARML23325A2022024-01-16016 January 2024
[Table view]CFR Part 52 Construction Lessons-Learned Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ND-23-0025, Compliance with Order EA-12-0492023-08-21021 August 2023 Compliance with Order EA-12-049 ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML22348A0882023-07-25025 July 2023 VEGP Unit 4 - 103g - Basis Document ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23003A0412023-01-0303 January 2023 Construction Reactor Oversight Process Resources Report January 3, 2023 ND-22-0817, Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection2022-11-0404 November 2022 Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML20290A2762022-08-0101 August 2022 10CFR52.103(g) Basis Document NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 ML22179A1462022-06-15015 June 2022 Tier 1, Revision 10, Updated Through 04/22/2022 ML22159A1712022-06-0808 June 2022 Construction Reactor Oversight Process Resources Report June 8, 2022 ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ML22089A0412022-03-30030 March 2022 Construction Reactor Oversight Process Resources Report March 30 2022 ND-22-0003, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2022-01-0606 January 2022 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21277A0762021-10-0404 October 2021 Vog 4 Dashboard 10-4-2021 ND-21-0848, Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised)2021-10-0101 October 2021 Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised) IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML21179A0972021-06-15015 June 2021 to Tier 1 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 ND-21-0342, Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 42021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 4 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21040A1672021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Westinghouse Non-Proprietary Technical Description of the Flaw Tolerance Evaluation Conducted on the Subject Weldolet Branch Connections ML20358A1822020-12-31031 December 2020 LTR-SDA-20-096-NP, Revision 1, Flaw Tolerance Evaluation to Assess Lack of Inspection Coverage of AP1000 14 X 4 Stainless Steel Weldolets to Pipe Welds ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ND-20-1220, Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan2020-10-21021 October 2020 Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20274A2582020-09-10010 September 2020 Wp on Uswc for AP1000_Revised, Reactor Oversight Process Whitepaper - Modification of the Description of Unplanned Scrams with Complications Performance Indicator to Reflect AP1000 Design ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ND-20-0561, Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report2020-07-10010 July 2020 Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report ML20189A4292020-07-0707 July 2020 Construction Reactor Oversight Process Resources July 2020 ML20136A4562020-04-30030 April 2020 Updated Flex Plan Nuclear Regulatory Commission Order EA-12-049 Strategies for Beyond Design Basis External Events NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections.2019-12-31031 December 2019 EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections. ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 2024-01-08 Category:Miscellaneous MONTHYEARNL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024
[Table view]Correction of Technical Specification Typographical Error ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) ND-18-1500, CFR 50.46 Thirty Day Report2018-12-18018 December 2018 CFR 50.46 Thirty Day Report ML18152B7852018-10-12012 October 2018 Summary of Nuclear Regulatory Commission Vendor Inspections Affecting Inspections, Tests, Analyses, and Acceptance Criteria ND-18-1047, Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule2018-08-0808 August 2018 Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule NL-18-0670, Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements2018-05-24024 May 2018 Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements NL-17-1889, NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information2017-12-0505 December 2017 NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information NL-17-0777, Flooding Focused Evaluation Summary Report2017-06-30030 June 2017 Flooding Focused Evaluation Summary Report NL-17-0218, Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment2017-03-27027 March 2017 Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment NL-15-2276, Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20142015-12-23023 December 2015 Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ND-14-2009, 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-12-17017 December 2014 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample NL-14-1899, Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20132014-12-0808 December 2014 Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 ML14279A3522014-11-0606 November 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14169A5992014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14049A3542014-02-24024 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML13162A5342013-06-10010 June 2013 Initial Exam 2013-301 Final SRO Written Exam NL-13-0173, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NL-12-0324, Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-00062012-02-16016 February 2012 Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-0006 NL-11-0626, Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-0062011-03-29029 March 2011 Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-006 NL-10-1536, Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-0062010-08-18018 August 2010 Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-006 ML1015903342010-06-0808 June 2010 Audit of Steam Generator H Amendment Reference Documents ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants NL-09-1449, Submittal of Emergency Response Data System (Eros) Data Point Library Modification2009-09-24024 September 2009 Submittal of Emergency Response Data System (Eros) Data Point Library Modification NL-09-1375, Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.102009-08-25025 August 2009 Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.10 NL-08-1405, Report of Unsatisfactory Performance Testing2008-09-12012 September 2008 Report of Unsatisfactory Performance Testing NL-08-0343, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment2008-03-18018 March 2008 Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment NL-07-1777, Supplemental Response to NRC Generic Letter 2004-022008-02-28028 February 2008 Supplemental Response to NRC Generic Letter 2004-02 NL-08-0275, Response to 01/28/2008 Request for Additional Information2008-02-27027 February 2008 Response to 01/28/2008 Request for Additional Information ML0732405912007-11-0505 November 2007 Land Management Plan ML0732407392007-11-0505 November 2007 Stratigraphy and Depositional Environments of Sediments from Five Cores from Screven and Burke Counties, Georgia ML0732403812007-11-0505 November 2007 10 CFR 50.75(g) Leak/Spill Decommissioning Record, Figure 1, for 1980s and 1990s, NMP-EN-002, Version 1.0 2024-01-12 |
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