|
---|
Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use 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-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 2024-01-29
[Table view] Category:Report
MONTHYEARML23325A2022024-01-16016 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, (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 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) ML21214A3182021-08-0202 August 2021 301 Comments 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 NL-20-0713, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-21021 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic 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-20-0034, Inservice Inspection Program Owner'S Activity Report for Outage 1R292020-01-17017 January 2020 Inservice Inspection Program Owner'S Activity Report for Outage 1R29 2024-01-08
[Table view] Category:Miscellaneous
MONTHYEARNL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 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 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) ML21214A3182021-08-0202 August 2021 301 Comments 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) NL-20-0034, Inservice Inspection Program Owner'S Activity Report for Outage 1R292020-01-17017 January 2020 Inservice Inspection Program Owner'S Activity Report for Outage 1R29 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-17-1713, Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure2018-04-0606 April 2018 Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure NL-17-2061, Special Report 2017-002-00, Nonfunctional Radiation Monitor R-60B2017-12-14014 December 2017 Special Report 2017-002-00, Nonfunctional Radiation Monitor R-60B 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-16-2541, Notification of 10 CFR 26.719(c) 30-Day Report for False Positive Drug Test Results2016-11-29029 November 2016 Notification of 10 CFR 26.719(c) 30-Day Report for False Positive Drug Test Results NL-16-0810, Submittal of Post Accident Monitoring Report2016-06-0909 June 2016 Submittal of Post Accident Monitoring Report NL-16-0683, Special Report No. 2016-002-00, Alternate AC Source Out of Service2016-06-0202 June 2016 Special Report No. 2016-002-00, Alternate AC Source Out of Service NL-16-0751, Special Report 2016-001-00, Nonfunctional Radiation Monitor R-60B and R-60C2016-05-23023 May 2016 Special Report 2016-001-00, Nonfunctional Radiation Monitor R-60B and R-60C ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report 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 NL-15-1489, 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-12082015-08-17017 August 2015 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-1208 ML15182A1752015-06-26026 June 2015 Completion of Required Action by NRC Order EA-12-051 Reliable Spent Fuel Pool Level Instrumentation ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis NL-15-0418, Revision 6, Pressure Temperature Limits Reports2015-03-0505 March 2015 Revision 6, Pressure Temperature Limits Reports NL-15-0080, Special Report 2015-001-002015-01-26026 January 2015 Special Report 2015-001-00 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 NL-14-1109, Third Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Reliable Spent Fuel Pool Instrumentation (EA-12-051)2014-08-26026 August 2014 Third Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Reliable Spent Fuel Pool Instrumentation (EA-12-051) 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 ML14128A0832014-06-0303 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 ML14101A1192014-04-16016 April 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 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 NL-14-0145, Proposed Alternative for the Fourth Lnterval Lnservice Inspection (FNP-ISI-ALT-14, Version 1.0)2014-02-18018 February 2014 Proposed Alternative for the Fourth Lnterval Lnservice Inspection (FNP-ISI-ALT-14, Version 1.0) 2024-01-12
[Table view] |
Text
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 Tel 205.992.7872 Fax 205.992.7601 SOUT ERN << \
NUCL AR A SOUTHERN COMPANY Docket Nos.: 50-348 50-424 NL-15-2276 50-364 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Ladies and Gentlemen:
Southern Nuclear Operating Company (SNC) is the licensed operator for the Joseph M. Farley Nuclear Plant (Farley) Units 1 and 2, and the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2. The requirements of 10 CFR 50.46(a)(3)(ii) include an annual report by licensees of changes to or errors in acceptable emergency core cooling system (ECCS) models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis. Accordingly, the reports required by 10 CFR 50.46(a)(3)(ii) for Farley and Vogtle are provided in Enclosures 1 and 2, respectively. The resulting peak cladding temperature (PCT) for Farley and Vogtle continue to meet the criterion of 10 CFR 50.46(b)(1) (i.e., s 2200°F).
Please note that the 2014 annual report for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, was previously sent by letter dated April 8, 2015.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted, cR.&
C. R. Pierce Regulatory Affairs Director CRP/RMJ/Iac
Enclosures:
- 1. Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014
- 2. Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President - Farley Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. M.D. Meier, Vice President- Regulatory Affairs Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley Mr. G. W. Gunn, Regulatory Affairs Manager- Vogtle 1 & 2 RType: Farley=CFA04.054; Vogtle=CVC7000 U.S. Nuclear Regulatory Commission Mr. L. D. Wert, Regional Administrator (Acting)
Mr. S. A. Williams, NRR Project Manager- Farley Mr. L. M. Cain, Senior Resident Inspector- Vogtle 1 & 2 Mr. P. K. Niebaum, Senior Resident Inspector- Farley Mr. R.E. Martin, NRR Project Manager- Vogtle 1 & 2
Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Enclosure 1 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 1 ASTRUM Best Estimate Large Break LOCA Evaluation Table 1-1a- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT °F)
None affecting PCT 0 Table 1-1b- Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-1 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 1 NOTRUMP Appendix K Small Break LOCA Evaluation Table 1-1c- Summary of Changes/Errors (2014}
Estimated Description Effect
(~ PCT 0 F)
None affecting PCT N/A Table 1-1d- Cumulative Impact of Changes/Errors
~IPCTI Description (oF}
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-2 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 2 ASTRUM Best Estimate Large Break LOCA Evaluation Table 1-2a- Summary of Changes/Errors {2014)
Estimated Description Effect
(~ PCT °F)
None affecting PCT 0 Table 1-2b - Cumulative Impact of Changes/Errors
~IPCTI Description eF>
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-3 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 2 NOTRUMP Appendix K Small Break LOCA Evaluation Table 1-2c- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT 0 F)
None affecting PCT N/A Table 1-2d - Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-4 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014
References:
- 1. Letter from C. R. Pierce to USNRC (NL-14-1899), "Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013," dated December 8 2014
- 2. Westinghouse Letter LTR-LIS-15-59, "J. M. Farley Units 1 and 2, 10 CFR 50.46 Annual Notification and Reporting for 2014," dated February 17, 2015 E1-5
Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Enclosure 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 1 BASH Large Break LOCA Evaluation Table 1-1a- Summary of Changes/Errors (2014)
Estimated Description Effect (L1 Pen (°F)
None affecting PCT N/A Table 1-1b- Cumulative Impact of Changes/Errors L1IPCTI Description (DF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 29 Cumulative Total 29 E2-1 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 1 Appendix K Small Break LOCA Evaluation Table 1-1c- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT)
None affecting PCT N/A Table 1-1d- Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Changes/Errors 2014 Calendar Year (Reference 2) 0 Cumulative Total 0 E2-2 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 2 BASH Large Break LOCA Evaluation Table 1-2a- Summary of Changes/Errors (2014)
Estimated Description Effect
<~Pen None affecting PCT N/A Table 1-2b - Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2} 29 Cumulative Total 29 E2-3 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 2 Appendix K Small Break LOCA Evaluation Table 1-2c- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT)
None affecting PCT N/A Table 1-2d - Cumulative Impact of Changes/Errors
~IPCTI Description (of)
- Changes/Errors Previously Reported (Reference 1) 0
- Changes/Errors 2014 Calendar Year (Reference 2) 0 Cumulative Total 0 E2-4
Enclosure 2 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report fOF 2014
References:
- 1. Letter from C. R. Pierce to USNRC (NL-14-1899), "Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013," dated December 8 2014
- 2. Westinghouse letter LTR-LIS-15-37, "A. W. Vogtle Units 1 and 210 CFR 50.46 Annual Notification and Reporting for 2014," dated February 19, 2015.
E2-5
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 Tel 205.992.7872 Fax 205.992.7601 SOUT ERN << \
NUCL AR A SOUTHERN COMPANY Docket Nos.: 50-348 50-424 NL-15-2276 50-364 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Ladies and Gentlemen:
Southern Nuclear Operating Company (SNC) is the licensed operator for the Joseph M. Farley Nuclear Plant (Farley) Units 1 and 2, and the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2. The requirements of 10 CFR 50.46(a)(3)(ii) include an annual report by licensees of changes to or errors in acceptable emergency core cooling system (ECCS) models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis. Accordingly, the reports required by 10 CFR 50.46(a)(3)(ii) for Farley and Vogtle are provided in Enclosures 1 and 2, respectively. The resulting peak cladding temperature (PCT) for Farley and Vogtle continue to meet the criterion of 10 CFR 50.46(b)(1) (i.e., s 2200°F).
Please note that the 2014 annual report for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, was previously sent by letter dated April 8, 2015.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted, cR.&
C. R. Pierce Regulatory Affairs Director CRP/RMJ/Iac
Enclosures:
- 1. Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014
- 2. Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President - Farley Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. M.D. Meier, Vice President- Regulatory Affairs Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley Mr. G. W. Gunn, Regulatory Affairs Manager- Vogtle 1 & 2 RType: Farley=CFA04.054; Vogtle=CVC7000 U.S. Nuclear Regulatory Commission Mr. L. D. Wert, Regional Administrator (Acting)
Mr. S. A. Williams, NRR Project Manager- Farley Mr. L. M. Cain, Senior Resident Inspector- Vogtle 1 & 2 Mr. P. K. Niebaum, Senior Resident Inspector- Farley Mr. R.E. Martin, NRR Project Manager- Vogtle 1 & 2
Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Enclosure 1 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 1 ASTRUM Best Estimate Large Break LOCA Evaluation Table 1-1a- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT °F)
None affecting PCT 0 Table 1-1b- Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-1 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 1 NOTRUMP Appendix K Small Break LOCA Evaluation Table 1-1c- Summary of Changes/Errors (2014}
Estimated Description Effect
(~ PCT 0 F)
None affecting PCT N/A Table 1-1d- Cumulative Impact of Changes/Errors
~IPCTI Description (oF}
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-2 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 2 ASTRUM Best Estimate Large Break LOCA Evaluation Table 1-2a- Summary of Changes/Errors {2014)
Estimated Description Effect
(~ PCT °F)
None affecting PCT 0 Table 1-2b - Cumulative Impact of Changes/Errors
~IPCTI Description eF>
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-3 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Joseph M. Farley Nuclear Plant - Unit 2 NOTRUMP Appendix K Small Break LOCA Evaluation Table 1-2c- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT 0 F)
None affecting PCT N/A Table 1-2d - Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 0 Cumulative Total 0 E1-4 to NL-15-2276 Joseph M. Farley Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014
References:
- 1. Letter from C. R. Pierce to USNRC (NL-14-1899), "Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013," dated December 8 2014
- 2. Westinghouse Letter LTR-LIS-15-59, "J. M. Farley Units 1 and 2, 10 CFR 50.46 Annual Notification and Reporting for 2014," dated February 17, 2015 E1-5
Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Enclosure 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 1 BASH Large Break LOCA Evaluation Table 1-1a- Summary of Changes/Errors (2014)
Estimated Description Effect (L1 Pen (°F)
None affecting PCT N/A Table 1-1b- Cumulative Impact of Changes/Errors L1IPCTI Description (DF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2) 29 Cumulative Total 29 E2-1 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 1 Appendix K Small Break LOCA Evaluation Table 1-1c- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT)
None affecting PCT N/A Table 1-1d- Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Changes/Errors 2014 Calendar Year (Reference 2) 0 Cumulative Total 0 E2-2 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 2 BASH Large Break LOCA Evaluation Table 1-2a- Summary of Changes/Errors (2014)
Estimated Description Effect
<~Pen None affecting PCT N/A Table 1-2b - Cumulative Impact of Changes/Errors
~IPCTI Description (oF)
- Changes/Errors Previously Reported (Reference 1) 0
- Summary of Changes/Errors (2014) (Reference 2} 29 Cumulative Total 29 E2-3 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 Vogtle Electric Generating Plant- Unit 2 Appendix K Small Break LOCA Evaluation Table 1-2c- Summary of Changes/Errors (2014)
Estimated Description Effect
(~ PCT)
None affecting PCT N/A Table 1-2d - Cumulative Impact of Changes/Errors
~IPCTI Description (of)
- Changes/Errors Previously Reported (Reference 1) 0
- Changes/Errors 2014 Calendar Year (Reference 2) 0 Cumulative Total 0 E2-4
Enclosure 2 to NL-15-2276 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report fOF 2014
References:
- 1. Letter from C. R. Pierce to USNRC (NL-14-1899), "Joseph M. Farley Nuclear Plant Units 1 and 2 Vogtle Electric Generating Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013," dated December 8 2014
- 2. Westinghouse letter LTR-LIS-15-37, "A. W. Vogtle Units 1 and 210 CFR 50.46 Annual Notification and Reporting for 2014," dated February 19, 2015.
E2-5
- - - - - - - - - - - -- ---- -