Letter Sequence Other |
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Results
Other: ML14006A201, ML15082A162, ML15210A510, 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), NL-13-1764, First Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049), NL-13-1767, First 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), NL-14-1111, 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), NL-15-0241, Fourth 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), NL-15-0245, Fourth Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)
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MONTHYEARNL-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) Project stage: Other ML13157A1762013-06-18018 June 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: RAI NL-13-1460, Response to Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-07-17017 July 2013 Response to Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Response to RAI NL-13-1764, First Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)2013-08-27027 August 2013 First Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049) Project stage: Other NL-13-1767, First 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)2013-08-27027 August 2013 First 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) Project stage: Other ML13280A3812013-11-0404 November 2013 Interim Staff Evaluation and Request for Additional Information - Vogtle Electric Generating Plant, Units 1 and 2 (VEGP) Regarding Overall Integrated Plan (OIP) for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) (TAC Nos. Project stage: RAI ML14006A2012014-01-0303 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Vogtle Electric Generating Plant, Units 1 and 2, TAC Nos.: MF0714 and MF0715 Project stage: Other ML13339A7812014-01-16016 January 2014 Interim Staff Evaluation and Audit Report Related to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies Project stage: Acceptance Review NL-14-1111, 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) Project stage: Other NL-15-0241, Fourth 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)2015-02-26026 February 2015 Fourth 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) Project stage: Other NL-15-0245, Fourth Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)2015-02-26026 February 2015 Fourth Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049) Project stage: Other ML15082A1622015-03-31031 March 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML15210A5102015-08-25025 August 2015 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other 2014-01-16
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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-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-23-0750, 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-23-0695, 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-23-0670, 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-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 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-23-0467, 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-23-0346, 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-23-0326, 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 NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 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 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
[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 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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8. L. "Pete" Ivey Southern Nuclear Vice President Operating Company, Inc.
Regulatory Affairs 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7619 Fax 205.992.521 7 February 27,2013 Docket Nos.: 50-424 NL-13-0173 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Units 1 and 2 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)
References:
- 1. NRC Order Number EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation dated March 12,2012
- 2. NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order EA-12-051, Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation, Revision 0, dated August 29,2012
- 3. NEI 12-02, Industry Guidance for Compliance with NRC Order EA-12-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, Revision 1, dated August 24, 2012
- 4. Southern Nuclear Operating Company letter NL-12-2152 to the NRC, Vogtle Electric Generating Plant - Units 1 and 2 Southern Nuclear Operating Company's Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), dated October 23, 2012 Ladies and Gentlemen:
On March 12,2012, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an order (Reference 1) to Southern Nuclear Operating Company (SI\lC). Reference 1 was immediately effective and directs SNC to have
U. Nuclear Commission NL-13-01 Page 2 a reliable indication of water level in aS~)OClaltm spent fuel pools.
Specific requirements are outlined in 2 of 1.
Reference 1 requires submission of an Overall Plan by February 201 NRC Interim Staff (ISG) (Reference 2) was '''''.'01..1 2 which endorses industry guidance document NEI 12-02, .... c\lIc.nn Qoto,.,onr'o 3) with and identified in I-lo*to ..':>n....*o Reference 3 provides direction regarding the content of this Overall Integrated Plan. Reference 4 provided Vogtle Generating (VEGP) initial status report regarding reliable fuel pool instrumentation, as required by Qoto",Qnr'o 1.
purpose of letter is to provide Overall Integrated Plan for VEGP pursuant to IV, Condition C.1, of Reference 1. letter confirms SNC has received 2 and an Overall Integrated Plan for VEGP developed in accordance with the guidance for purpose of ensuring a reliable of the water in associated fuel storage pools of supporting identification of required wide pool water level conditions by trained personnel.
The information in the Enclosure provides the VEGP Units 1 and 2 Overall Integrated Plan for reliable spent fuel pool instrumentation pursuant to Reference enclosed Integrated Plan is based on conceptual design information. Final details and procedure as well as revisions to the information contained in the Enclosure, will be provided in 6-month Integrated Plan by Reference 1.
SNC intends to fully implement requirements the Order of the Unit 1 Fall 2015 refueling outage and the Unit 2 Fall 2014 refueling outage Section IV, Condition A.2 of Reference 1. In accordance with Section IV, Condition C.3 of 1, SNC to submit notification to the NRC that full compliance of the Order has achieved within 60 of full implementation for each unit at letter contains no new regulatory commitments. If you any questions, please contact McElroy at (205) 992-7369.
U. S. l\Juclear Regulatory Commission NL-13-0173 Page 3 Respectfully subrnitted,
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B. L. Ivey Vice President - Regulatory Affairs BLl/CLN Mr. B. L. Ivey states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and , to the best of his knowledge and belief, the facts set forth in this letter are true.
Sworn to and subscribed before me this rJ. 7Wc day of Jdv~/ ,2013.
nHRtt(~~ #1~~1-rlr--/
tary Public My commission expires: :1MA c4"), 2, J-o j if .:
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.,..........~
Enclosure:
Vogtle Electric Generating Plant Units 1 and 2 Integrated Plan with Regard to Reliable Spent Fuel Pool Instrumentation cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. E. Tynan, Vice President - Vogtle Mr. B. J. Adams, Vice President - Fleet Operations Mr. C. R. Pierce, Director - Regulatory Affairs RType: CVC7000 U. S. Nuclear Regulatory Comrnission Mr. E. Leeds, Director of the Office of Nuclear Reactor Regulation Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Vogtle Mr. L. M. Cain, Senior Resident Inspector - Vogtle Mr. Blake A. Purnell, NRR/JLD/PMB, NRC Mr. Steven R. Jones, NRR/DSS/SBPB, NRC State of Georgia Mr. J. H. Turner, Environmental Director Protection Division
VogUe Electric Generating Plant - Units 1 2 Southern Nuclear Operating Company's Overall Integrated Plan In to March 12,2012 Commission Order Modifying licenses with
.......,"*.,.,. to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Enclosure Vogtle Electric Generating Plant Units 1 and 2 Integrated Plan with Regard to Reliable Fuel Pool Instrumentation
Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 1 & 2 Reliable Spent Fuel Pool Instrumentation Overall Integrated Implementation Plan Revision 0, February 27,2013 VEGP-1 & 2 RSFPI Integrated Plan Page 1 of 15 2/27/2013 12:21 PM
Table of Contents I. Introduction .... ............. .. ...... .......... .............. ................ ........... .... ............. ... ............. .... 3 II. Schedule ................... ................ ............... ............... .. .............. .......... ... ....................... 4 III. Identification of Spent Fuel Pool Water Levels ......... ... ........... ... ............................. .. ........ 5 IV. Instruments ....... .. ........... ... ............. ... ............................. ... ........... .... ............. .. ............ 5 V. Reliability....... .. ............. .. .................. .. ........ .. .............. ... ........... .. ............. .. ............. ..... 6 VI. Instrument Channel Design Criteria ............................ ............................. .. ... ....... .... ....... 6 A. Arrangement .... .... .... .. ... ... .. ... ... .. .. ... ...... .... ........... ............ ...... .. ....... ..... .. ... ... .. ... ........... ........... .. 6 B. Mounting '" ......... ....... .. ......... .......... ..... ... ....... .. .. ... ... .......... ... ........ ... .... ....... .... .......... .. ..... ....... ... 7 C. Qualification .... ..... ... .. .... ........ .. .. ... .... ......... .. ........ ... .... ... ...... .......... ...... ... ... ....... .... ........... ... .... ... 7 D. Independence ... .... ...... ....... .... ..... ........ ... ....... ............ .... .... .... .... ...... ............ ... ....... ... ........ .... ... ... 9 E. Power Supplies ...... ........ .... ..... ..... ...... .. ...... .. ...... ...... .. .... ......... ... ..... ....... .... .... .......... .. .. ........ .... .. 9 F. Accuracy .... ... .......... ..... .. ..... ..... .. .... .... ..... ....... ... ............. ..... .. ..... ........ ...... ... ... ..... .. ..... ........... ..... 9 G. Testing ... .. ..... ........ .. ...... .. ... ... ..... .. .. .... ..... ..... ...... ................. .... .. ..... ....... ............. .... .. .... ... ...... ..... 9 H. Display ... ..... ..... .. ...... .. .......... ... ...... .. ... ... .... .. ... ... ..... ... .... ... ... ....... .... ... ... .. ..... .. .. ....... ........ .. ........ 10 VII. Instrument Channel Program Criteria ......... ... ........ .. ........... .... ............ .. ........ .. ..... .. ....... 10 A. Training .. ...... .. ................. .. .... .... .......... .. ....... ..... ... ......... .. .... ...... .... .. ...... .. .. .... ...... .. .. ...... ......... .. 10 B. Procedures........ .... ...... ...... .... .. ....... ..... .... ..... ...... ....... ............ ... .... ..... ..... ..... ......... .. ...... ..... ....... 10 C. Testing and Calibration .. ......... ..... ........ ... ........ ... .. ...... .. ......... .. ....... ....... .... ... ..... .. ..... ........... ... .. 10 VIII . Need for Relief and Basis .................................. .. .......... ................... .... ............ .. ......... 10 IX. References ..................... .. ....................... .. ................... .. ............ .. ............................. 11 : Probe Location Sketch .... .... ............................................................................ .. 12 : Electrical Sketches ....... .............................................................. .... ............ ...... 13 VEGP-1 & 2 RSFPI Integrated Plan Page 2 of 15 2/27/2013 12:21 PM
I. Introduction The Regulatory Commission (NRC) issued Order EA-12-0S1, Issuance of Order to Modify with Regard to Spent Fuel Instrumentation, 1) on Ma 2012. The Order licensees to have reliable indication the water level in associated spent fuel pools capable of supporting identification of the following pool water level conditions by trained personnel: that is of normal fuel cooling system, (2) is adequate to provide su radiation shielding for a person standing on spent fuel pool operating deck, and (3) where fuel remains and actions to implement water addition should no longer Order also submittal of an integrated plan will provide a description of how the requirements of the Order will be achieved.
NEI Industry Guidance Compliance with NRC Order Modify Licenses with Regard to Reliable Fuel Poo/lnstrumentation," (Reference 4) provides an approach for complying with EA-12-0S1. NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order Reliable Poo/lnstrumentation, {Reference 3} that in conformance with the guidelines provided in NE112-02, specific to NEI 12-02 Section 3.4, the Order integrated provides the Generating Plant (VEGP) Units 1 2 approach for complying with Order EA-12-0S1 using methods described in NE112-02 with the and clarifications as in the sections. Six month progress will be provided consistent with the requirements of Order EA-12-0S1 and the in NEI 12-02.
VEGP-l & 2 RSFPI Integrated Plan 3 of 15 12:21 PM
II. Schedule Installation of reliable spent fuel pool (SFP) level instrumentation will be completed prior to startup from the second refueling outage per unit after submittal of this plan (the Second Refueling outage commencing at VEGP following February 28,2013 is Fall 2015 for Unit 1 and Fall 2014 for Unit 2), but no later than December 31,2016, (Reference 6) .
The following milestone schedule is provided . The dates are planning dates subject to change as design and implementation details are developed. Any changes to the following target dates will be reflected in the subsequent six (6) month status reports.
The current milestones are:
Original Target Activity Status Date {Include date changes in this columnl Oct. 2012 Submit 60 Day Status Report Complete Feb. 2013 Submit Overall Integrated Implementation Plan Complete 5
Apr2013 Unit 21 RFO Aug 2013 Submit 6 Month Status Report Dec 2013 Develop Modifications Unit 2 Feb. 2014 Submit 6 Month Status Report Apr2014 Unit 1 15 RFO Apr 2014 Receipt of Unit 2 SFP Instrument Channel June 2014 Develop Modifications Unit 1 302014 Complete Functional Test of Unit 2 SFP Instruments Aug. 2014 Submit 6 Month Status Report Dec 2014 Receipt of Unit 1 SFP Instrument Channel 302015 Complete Functional Test of Unit 1 SFP Instruments Oct 2014 Unit 2 Implementation Complete (2 0 0 RFO)*
Feb . 2015 Submit 6 Month Status Report Oct 2015 Unit 1 Implementation Complete (2 00 RFO)*
Dec 2015 Submit Completion Report
'Full compliance after second listed refueling outage VEGP-1 & 2 RSFPI Integrated Plan Page 4 of 15 2/27/2013 12:21 PM
Identification of Spent Fuel Pool Water Levels Each unit at Vogtle Generating Plant its own fuel pool. spent fuel pools are within the Seismic Category 1 handling building. The pool is approximately 41 ft constructed of and lined with a 1/4-in. plate.
Contiguous to each spent fuel pool is a short canal to the transfer The transfer canal is connected to the canal inside the containment by the fuel tube. All movement spent fuel transfer are underwater, and the waterways are of depth to maintain a nominal 10 ft of shielding water above active fuel. A metal gate with gasket assembly the spent fuel the fuel transfer This allows transfer to without with the water level in fuel pool (see Attachment 1).
- 1. Level adequate to support operation of the normal fuel pool cooling system - Fuel pool level when suction loss occurs can be conservatively defined as SFP cooling low level set point 2 which is above the elevation at top of fuel pool cooling suction line that is at approximately 214'-11" (References 11, 14 through
- 2. Level adequate to provide substantial radiation shielding for a person standing on spent fuel pool operating deck - Elevation 1/8" is approximately _0" above 1/8", the point of fuel both Unit 1 and 2 (plus or minus 1 (Reference 10 - FSAR Section 9.1.2.2 figure 9.1.2-1 (Sh. 1 of 2) and References 11 & 12).
- 3. Level where fuel remains covered - Elevation 1/8/J is the nominal of the fuel rack 10 FSAR Section 9.1.2.2 and 9.1.2-1 (Sh. 1 of 2)
References 11 &
IV. Instruments of the instruments will consistent with the of NRC JLD-ISG-2012-03 and NEI 12-02 with the exceptions and clarifications as
.. Primary and backup instrument channels will consist of components.
plan is for both to utilize Wave which functions to principle Time Domain Reflectometry (TOR). A of electromagnetic energy down the probe. Upon reaching the liquid the pulse is reflected and based upon reflection times, level is inferred.
.. The will be continuous from top of the spent fuel racks at elevation 9.1.2-1 10f and KPTPrp
.. Instrument level sensing components (probe) will located in SFP directly adjacent to the fuel. The module will of located in a non-harsh environment area VEGP-1 & 2 RSFPI Integrated Plan 5 of 15 2/27/2013 12:21 PM
- The display shall provide a continuous indication of spent fuel pool water level at the Display location. In the event the link to the Display is lost, a field accessible signal/Indication (remote to the Display location) will be available for determination of pool level.
- The electronic processing module and the Display will be installed in a location that will meet the criteria established in NEI12 -02 and endorsed by NRC JLD-ISG-2012-03. The specific location of the electronic processing module and the Display has not been determined yet.
V. Reliability Reliability of the primary and backup instrument channels will be assured by conformance with the guidelines of NRC JLD-ISG-2012-03 or NE112-02, as discussed in Section 3.4, Qualification and 3.8 Testing. Reliable level indication will be functional during all times when used fuel is in the SFP cons istent with NEI 12-02 Section 4.3, Testing and Calibration .
VI. Instrument Channel Design Criteria Instrument channel design will meet the guidelines of NRC JLD-ISG-2012-03 and [\\EI12-02 and applicable sections of the plant FSAR with the exceptions and clarifications as detailed below.
A. Arrangement SFP level probes will be installed separate from each other in the SFP . Primary and backup level indication will be installed in the Main Control Room, at the alternate shutdown panel, or another appropriate and accessible location (reference NEI12-06) that complies with the NE112-02 following characteristics. SNC has not determined the exact location at this time and has several options that provide various benefits. For example, the Main Control Room is the NRC preferred location while an appropriate accessible location in the plant would provide information to personnel in the plant at a location closer to the pool and mitigation equipment. Both existing and new barriers will be used to provide a level of protection for the cable located on the refueling floor from falling debris missiles generated by the event.
Probes will consist of a small diameter stainless steel cable mounted within a protective sleeve (stilling well). The cable will end just above the fuel racks . Based on the light weight of the probe, it is assumed that the probe will survive the event with little or no damage . Likewise, the pool wall or spent fuel will not be damaged by any interaction with the protective sleeve during the event.
Specific channel level sensing components physical properties and installation details will be provided later after the engineering and design phase is completed.
The probe support (including stilling well) will be designed to shield the probe from event generated missiles (falling debris). The design of the probe and probe support will allow the fuel handling machine to pass over it without interference.
VEGP-1 & 2 RSFPI Integrated Plan Page 6 of 15 2/27/2013 12:21 PM
Cabling for power supplies and indications for each channel will be separated for missile protection (falling debris) and routed in separate conduits from cabling for the other channel.
B. Mounting Per NEI 12-02 Section 3.3, Mounting, the new equipment will be mounted to maintain the current Seismic Class of the Spent Fuel Pool which is Seismic Class I (Reference 13).
Thus, the new equipment will be seismically qualified to Class I. In addition, the mounting of the primary and backup channel components throughout the plant will meet the criteria of the structure it will be routed through or attached to. (refer to Qualification details below relating to cable and raceway installation criteria)
- c. Qualification The components/cables/connections for both primary and backup channels will be reliable at the temperature, humidity, and radiation levels consistent with the spent fuel pool water at saturation conditions for seven (7) days. Saturation temperature at the bottom of the SFP assuming normal water level will be approximately 250°F. Post event temperature at sensors located above the SFP is assumed to be 212°F. Post event humidity in the fuel pool floor near and above the SFP is assumed to be 100% with condensing steam. The components/cables/connections will be qualified for expected conditions at the installed location assuming the SFP has been at saturation for an extended period. The components/cables/connections located in the vicinity of the SFP will be qualified to withstand peak and total integrated dose radiation levels for their installed location assuming that post event SFP water level is equal to the top of irradiated fuel for a time no greater than six (6) hours. It is anticipated that the station personnel can align one of the three (3) SFP Cooling Strategies as detailed in NEI 12-06 if conditions are degrading as indicted by decreasing SFP level.
Conduit design in the SFP area will be installed to Seismic Category 1 criteria. Both existing and new barriers will be used to provide a level of protection for the cable located on the refueling floor from missiles. The existing and new raceway used to route the cable to the Display will be installed to Seismic Class 1 criteria. Augmented quality requirements, similar to those applied to fire protection, will be applied to the components installed in response to this Order.
The specific values to use for the shock and vibration qualification will be determined in the design phase of the implementation using FSAR and Design Basis information.
Components of the instrument channels installed in the SFP area will be qualified for shock and vibration using one or more of the following methods (note different methods may be used for the various sub components of the primary and back-Up instrument channels):
- Instrument channel components use known operating principles are supplied by manufacturers with commercial quality programs (such as IS09001) with shock and vibration requirements included in the purchase specification and/or instrument design, and commercial design and testing for operation in environments where VEGP-1 & 2 RSFPI Integrated Plan Page 7 of 15 2/27/2013 12:21 PM
significant shock vibration loadings are common, as for hand-held devices or transportation applications;
\II Substantial history of operational reliability in environments with significant shock and vibration loading, such as transportation applications; or
\II components inherently resistant to shock vibration loadings or are seismically reliable such as For seismic impact on instrument channel components after a potential event for installed components, the following measures will to verify design and installation is adequate. Applicable components the instrument channels are rated by the manufacturer (or otherwise tested) for seismic impact at commensurate with those of postulated basis event in area of channel component use using one or more the following methods (note different methods may used for the various sub components of the primary and p instrument chan
\II Adequacy of seismic design and installation is demonstrated on the guidance in Sections 7, 8, 9, and 10 of IEEE IEEE Recommended Practice for Seismic Qualification of 1E Equipment for Nuclear Power Stations, (Reference 9) or a substantially similar industrial standard
\II Instrument channel components use known operating principles, are supplied by manufacturers with commercial quality programs (such as 1509001) with seismic requirements included in the specification and/or instrument design, and commercial design and in where seismic oU,>r1"c are common
\II history of operational reliability in environments with vibration, such as for portable hand-held devices or transportation applications
\II Demonstration of seismic reliability methods the performance by:
Analysis of the equipment under simulated seismic conditions
- Using a combination of test
\II Demonstration that proposed devices are substantially similar in design to models have been tested seismic effects in excess of plant design at the location the instrument is to ranges)
\II qualification seismic motion consistent with of existi ng loading at the installation location.
VEGP-l & 2 RSFPI Page 8 of 15 2/27/2013 12:21 PM
D. Independence The primary and backup instrument channels are of the same technology, are permanently installed, separated by distance or barriers, and utilize independent power supplies from different buses/switchgear.
E. Power Supplies Each channel will normally be powered from independent (different buses/switchgear) 120V AC power sources and will have a dedicated battery backup. The battery backup will be dedicated to each channel, should have the capability of automatically switching and operating on backup batteries and will have manual switching as a minimum. A minimum battery life of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be provided to allow for power restoration from portable equipment (refer to attachment 2 for a typical sketch). Refer to Safety Function Support section of the SNC Integrated Plan February 28,2013, submittal for NRC Order EA-12-049 for details on the power strategy from portable FLEX Diesel Generators (DGs) .
F. Accuracy Instrument channels will be designed such that they will maintain their design accuracy without recalibration following a power interruption or change in power source.
SNC plans for the instrument design accuracy to be within +/- 1 inch, or as close as reasonably achievable, over the entire range for the expected environmental and process conditions. Accuracy will consider SFP post event conditions, e.g., saturated water, steam environment, or concentrated borated water. Additionally, the instrument accuracy of the GWR technology will be sufficient to allow trained personnel to determine when the actual level exceeds the specified level of each indicating range (levels 1, 2 and 3) without conflicting or ambiguous indication. The accuracy will be within the resolution requirements of Figure 1 of NEI 12-02 .
G. Testing Instrument channel design will provide for routine testing and calibration consistent with Order EA-12-051 and the guidance in NEI 12-02.
- SNC plans for the design to facilitate in-situ testing and lor calibration of the Static or non-active installed (fixed) sensors
- SNC plans for the design to facilitate the microprocessor based channel features to be capable of testing while mounted in the pool.
- Existing work control processes will be used to control maintenance and testing.
(e.g., Preventive Maintenance (PM) Program, Surveillance Program, Vendor Contracts, or work orders)
- Other testing and calibration requirements are located in Program Controls testing sub section below.
VEGP-1 & 2 RSFPI Integrated Plan Page 9 of 15 2/27/2013 12:21 PM
H. Display Primary and backup indication will be provided in the Main Control Room, at the alternate shutdown panel, or another appropriate and accessible location (reference NEI12-06) that complies with the NE112-02 characteristics. If multiple display locations are powered from the instrument loop, then the guidance in NE112-02 regarding multiple displays will be followed (refer to attachment 2 for a typical sketch).
VII. Instrument Channel Program Criteria Instrument channel program criteria will be consistent with the guidelines of NRC JLD-ISG-2012 03 and NEI 12-02.
A. Training A systematic approach will be used to identify the population to be trained and to determine both the initial and continuing elements of the required training. Personnel will complete training prior to being assigned responsibilities associated with this instrument.
B. Procedures Procedures will be developed using guidelines and vendor instructions to address the maintenance, operation, and abnormal response issues associated with the new SFP instrumentation consistent with NEI12-02.
Procedures will address a strategy to ensure SFP water level addition is initiated at an appropriate time consistent with implementation of NEI12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide (References 5 and 7).
C. Testing and Calibration Processes will be established and maintained for scheduling and implementing necessary testing and calibration of the primary and backup spent fuel pool level instrument channels to maintain the instrument channels at the design accuracy.
Testing and calibration of the instrumentation will be consistent with vendor recommendations and any other documented basis. Calibration will be specific to the mounted instrument and the monitor. Out of service time as identified in NEI 12-02 will be incorporated consistent with the programmatic process used for compliance with NRC Order EA-12-049 (Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events).
VIII. Need for Relief and Basis Southern Nuclear is not requesting relief from the requirements of Order EA-12-051 or the guidance in NE112-02 at this time, except as discussed herein.
Consistent with the requirements of Order EA-12-051 and the guidance in NE112-02 as endorsed by NRC JLD-ISG-2012-03, the six-month reports will delineate progress made, any VEGP-l & 2 RSFPI Integrated Plan Page 10 of 15 2/27/2013 12:21 PM
in our compliance methods, updates to the schedu and, if and their IX. References
- 1) Issuance of Order to Mod with to Spent Fuel Pool Instrumentation, March 2012
- 2) EA-12-049, Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation for External March 2012
- 3) NRC JLD-ISG-2012-03, Compliance with Order EA-12-051, Reliable Spent Pool Instrumentation, Revision 0, August 2012
- 4) NEI Industry for Compliance with NRC EA-12-051, Modify Licenses with Regard to Reliable Spent Pool Instrumentation," Revision 1, August 2012
- 5) NEI Diverse and Flexible Coping (FLEX) Implementation Guide, Revision 0, August 2012
- 6) Letter, NL-12-2152, Initial Status Report in Response to Commission Order Modifying Licenses with Regard to Requirements Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), October 2013
- 7) Letter NL-12-2147, Initial Status Report in Response to Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis Events Number d 2013
- 8) IS09001, Quality management systems - Requirements IEEE Standard IEEE Recommended Practice for Seismic Qualification Class lE Equipment for Nuclear Power Stations
- 10) Vogtle Nuclear Plant Unit 1 and 2 Safety Reports, Revision 18, 12-05-12
- 11) lX5DT0037, Ver. 0, "Level Setting Diagram Spent Fuel Pool Pit" 2X5DT0037, Ver. 0, "Level Diagram Spent Fuel Pool Pit" AX6D004, Ver. 0.0, Handling Bldg Floor Plan EI 220 ft 0 in EI 263 ft 8 in Levell and 3 Seismic Category"
- 14) lK7-1213-001-01, Ver. "Spent Fuel Pit Cooling Sys Fab Iso Fuel Bldg Area 3A Lvi A" lK7-1213-002-01, Ver. 10.0, "Spent Fuel Pit Cooling Sys Fab Iso Fuel Handling Bldg Area 3A Lvi A" 2K7-1213-001-01, Ver. "Fab Iso"
- 17) Ver. 7.0, "Spent Fuel Pit Sys Fuel Bldg Area 3A, A" VEGP-l & 2 Integrated Plan 11 15 2/27/2013 12:21 PM
Attachment 1: Probe Location Sketch I
North NOTE:
- 1. Snapshot taken from Reference 13.
- - Potential Probe 1 Location and 0 - Potential Probe 2 Location FNP-1 & 2 RSFPI Integrated Plan Page 12 of 15 2/27/2013 12:21 PM
Attachment 2: Electrical Sketches (Page lof3) aUlA
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