IR 05000424/2021005
From kanterella
| ML21237A291 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/25/2021 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2021005 | |
| Download: ML21237A291 (5) | |
Similar Documents at Vogtle | |
|---|---|
Category:Letter
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024
[Table view]Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) ML24120A2832024-04-30030 April 2024 Project Manager Reassignment 2024-09-09 Category:Report MONTHYEARML24297A6482024-10-23023 October 2024
[Table view]5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML23325A2022024-01-16016 January 2024 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, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 12022-10-31031 October 2022 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 ML20290A2762022-08-0101 August 2022 10CFR52.103(g) Basis Document ML22214A0072022-08-0101 August 2022 Archives 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) 2024-10-23 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, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 12022-10-31031 October 2022 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 ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary ML21280A3052021-10-0707 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 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 ML0732405722007-11-0505 November 2007 Vegp Groundwater Calculation Package Addendum. 2024-01-12 |
Inspection Report - Vogtle - 2021005 | |
|---|---|