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Category:Letter type:NL
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal 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-23-0542, 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-23-0566, 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-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal 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-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 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-23-0372, 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-23-0310, 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-23-0019, 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-23-0263, 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-23-0208, 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-23-0014, 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-23-0228, 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-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 NL-23-0003, Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 12023-01-20020 January 2023 Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1 NL-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error NL-22-0316, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-11-30030 November 2022 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0850, Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-11-18018 November 2022 Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0832, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF .2022-10-27027 October 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF . NL-22-0800, Supplement to Authorized Relief Request HNP-ISI-RR-05-022022-10-27027 October 2022 Supplement to Authorized Relief Request HNP-ISI-RR-05-02 NL-22-0801, Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of .2022-10-14014 October 2022 Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of . NL-22-0757, Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-09-30030 September 2022 Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NL-22-0687, Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 22022-08-31031 August 2022 Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 2 NL-22-0406, Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes2022-08-19019 August 2022 Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes NL-22-0650, Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-08-19019 August 2022 Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0590, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten2022-08-18018 August 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten NL-22-0672, Registration of Spent Fuel Cask Use2022-08-17017 August 2022 Registration of Spent Fuel Cask Use NL-22-0564, and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use2022-07-21021 July 2022 and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use 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 NL-22-0499, Registration of Spent Fuel Cask Use2022-06-27027 June 2022 Registration of Spent Fuel Cask Use NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0365, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R302022-05-31031 May 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R30 NL-22-0335, Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And.2022-05-17017 May 2022 Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And. NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0315, Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days2022-05-0404 May 2022 Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days NL-22-0325, Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-05-0303 May 2022 Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0283, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-04-29029 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. NL-22-0271, Changes to the Physical Security Plan2022-04-19019 April 2022 Changes to the Physical Security Plan NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations NL-21-0918, License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 52022-03-31031 March 2022 License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 5 NL-22-0220, Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 20222022-03-28028 March 2022 Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 2022 NL-22-0221, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2022-03-28028 March 2022 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) 2024-01-30
[Table view] Category:Report
MONTHYEARML24005A1142024-01-0505 January 2024 Recommendation for 2023-301 Cr/Sim 3 (Emergency Depress the Reactor Using Main Steam Line Drains) 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 A000412, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2021-12-0202 December 2021 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-20-1295, 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B2020-12-14014 December 2020 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B ML20303A1782020-09-29029 September 2020 Submittal of Revision 38 to Updated Final Safety Analysis Report 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 NL-18-0863, CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations2018-06-21021 June 2018 CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations NL-18-0506, Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test2018-04-16016 April 2018 Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test 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-18-0282, Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch2018-04-0404 April 2018 Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch NL-17-1916, Pressure and Temperature Limits Report2017-11-27027 November 2017 Pressure and Temperature Limits Report ML18012A0582017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-09-30030 September 2017 NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-17-1255, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation2017-08-22022 August 2017 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation NL-17-0955, Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-062017-06-0505 June 2017 Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-06 ML17069A2402017-04-13013 April 2017 Mitigating Strategies Assessment (CAC Nos. MF7932 and MF7933) - Redacted ML16356A0172016-12-16016 December 2016 Information Report for Lead Use Assemblies NL-16-2466, Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion2016-12-15015 December 2016 Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion NL-16-1136, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation2016-08-10010 August 2016 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation NL-16-0463, Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report2016-04-0101 April 2016 Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B2015-11-0202 November 2015 E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B NL-15-1461, Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2015-08-21021 August 2015 Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B ML15097A4242015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 of the NTTF Review ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ML14335A1372015-03-25025 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) NL-14-1989, Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.12014-12-30030 December 2014 Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1 NL-14-1876, Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package2014-11-24024 November 2014 Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package NL-14-1245, 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-08-22022 August 2014 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample ML14223A7942014-07-31031 July 2014 Enclosure 2 - Non-Proprietary Gnf Report GNF-001N6296-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hatch 2 Cycle 24 ML14155A4052014-06-30030 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 (TAC MF0234-35) ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14155A3612014-06-0606 June 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-14-0343, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites NL-14-0326, Units 1 and 2, Recommendation 2.1 Flood Hazard Reevaluation Report, Requested by NRC Letter Dated March 12, 20122014-03-0606 March 2014 Units 1 and 2, Recommendation 2.1 Flood Hazard Reevaluation Report, Requested by NRC Letter Dated March 12, 2012 ML13364A2022014-02-27027 February 2014 Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14045A1472014-02-12012 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2, TAC Nos.: MF0712 and MF0713 NL-13-1898, 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2013-08-30030 August 2013 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B ML13193A3662013-08-0707 August 2013 Request for Concurrence on the Effects of the Edwin I. Hatch Nuclear Plant, Units 1 and 2 on the Federally-Listed Endangered Species Altamaha Spinymussel NL-13-0172, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051)2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051) NL-13-0214, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events..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 Mitigation Strategies for Beyond-Design-Basis External Events.. ML13115A4732013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 NL-13-0402, GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 20082013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 ML12355A6332012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 3 of 11 ML12355A6312012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 11 ML12355A0592012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 11 of 11 ML12355A0562012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 8 of 11 ML12355A0552012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 7 of 11 ML12355A0542012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 6 of 11 2024-01-05
[Table view] Category:Technical
MONTHYEARNL-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 A000412, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2021-12-0202 December 2021 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-20-1295, 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B2020-12-14014 December 2020 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B ML20303A1782020-09-29029 September 2020 Submittal of Revision 38 to Updated Final Safety Analysis Report 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 NL-18-0282, Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch2018-04-0404 April 2018 Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch NL-17-1916, Pressure and Temperature Limits Report2017-11-27027 November 2017 Pressure and Temperature Limits Report ML18012A0582017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-09-30030 September 2017 NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-17-1255, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation2017-08-22022 August 2017 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation NL-16-2466, Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion2016-12-15015 December 2016 Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion NL-16-1136, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation2016-08-10010 August 2016 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B2015-11-0202 November 2015 E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B NL-14-1876, Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package2014-11-24024 November 2014 Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package ML14223A7942014-07-31031 July 2014 Enclosure 2 - Non-Proprietary Gnf Report GNF-001N6296-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hatch 2 Cycle 24 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 NL-14-0343, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites ML13364A2022014-02-27027 February 2014 Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14045A1472014-02-12012 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2, TAC Nos.: MF0712 and MF0713 NL-13-0402, GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 20082013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 ML13115A4732013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 NL-11-1081, Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Crack Growth Calculations and Stress Analysis - Spring 2011 Outage (2R21)2011-07-0707 July 2011 Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Crack Growth Calculations and Stress Analysis - Spring 2011 Outage (2R21) NL-11-1131, Unit 2, GNF-Ziron Lead Test Assemblies2011-06-16016 June 2011 Unit 2, GNF-Ziron Lead Test Assemblies NL-10-0824, Hatch, Unit 2, GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties.2010-03-31031 March 2010 Hatch, Unit 2, GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties. NL-10-0824, Hatch, Unit 2, GNF-0000-0114-0175NP, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction.2010-03-31031 March 2010 Hatch, Unit 2, GNF-0000-0114-0175NP, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction. NL-10-0824, GNF-0000-0113-8604NP, GNF-Ziron Performance Benefits and Licensing Requirements Assessment.2010-03-31031 March 2010 GNF-0000-0113-8604NP, GNF-Ziron Performance Benefits and Licensing Requirements Assessment. ML1013407402010-03-31031 March 2010 GNF-0000-0114-0175NP, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction. ML1013407382010-03-31031 March 2010 GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties. NL-09-0503, Response to Preliminary White Finding on 1B EDG Coupling Failure2009-04-15015 April 2009 Response to Preliminary White Finding on 1B EDG Coupling Failure ML0916006722009-03-31031 March 2009 GE-NE-0000-0080-0259-NP-R4, Shroud Repair Replacement of Upper Support Stress Analysis Report, Public NL-08-1781, Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap2008-12-19019 December 2008 Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap NL-08-1448, Submittal of Additional Information to Support Proposed Exemption to 10 CFR 50.448 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding2008-09-22022 September 2008 Submittal of Additional Information to Support Proposed Exemption to 10 CFR 50.448 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0822500372008-07-31031 July 2008 GNF-0000-0088-6047NP, Enclosure 4, Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits, July 2008 NL-08-1250, GNF-0000-0088-6043NP, Enclosure 6, Properties of GNF-Ziron, July 20082008-07-31031 July 2008 GNF-0000-0088-6043NP, Enclosure 6, Properties of GNF-Ziron, July 2008 NL-08-1250, GNF-0000-0088-6047NP, Enclosure 4, Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits, July 20082008-07-31031 July 2008 GNF-0000-0088-6047NP, Enclosure 4, Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits, July 2008 NL-08-1301, GE-NE-0000-0080-0259-R2, Hatch 2 Nuclear Plant, Shroud Repair Replacement of Upper Support Stress Analysis Report.2008-06-30030 June 2008 GE-NE-0000-0080-0259-R2, Hatch 2 Nuclear Plant, Shroud Repair Replacement of Upper Support Stress Analysis Report. NL-08-0634, Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses2008-05-0505 May 2008 Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses NL-08-0590, Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding2008-05-0202 May 2008 Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding NL-08-0380, Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding2008-03-21021 March 2008 Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding ML0624902422006-08-29029 August 2006 Enclosure 1, E. I. Hatch Request to Implement an Alternative Source Term - AST Safety Assessment ML0624904922006-07-28028 July 2006 Enclosure 8, E. I. Hatch, Request to Implement an Alternative Source Term - Unit 1 Main Steam Isolation Valve Alternate Leakage Path Seismic Evaluation ML0624904982006-07-28028 July 2006 Enclosure 9, E. I. Hatch, Request to Implement Alternative Source Term - Unit 1 Seismic Verification of Potential Secondary Containment Bypass Leakage Paths Terminating at Main Condenser ML0434304752004-10-20020 October 2004 SIR-04-120, Rev. 0, Elastic-Plastic Fracture Mechanics Evaluation of the Plant Hatch Unit 1, Core Shroud V5 and V6 Welds. ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 ML0624902592003-04-30030 April 2003 Enclosure 13, E. I. Hatch Request to Implement an Alternative Source Term - EPRI Technical Report 1007896, Seismic Evaluation Guidelines for HVAC Duct and Damper Systems. ML0311800572003-04-25025 April 2003 Results of the Edwin I. Hatch Generating Station Units 1 and 2 SDP Phase 2 Notebook Benchmarking Visit ML0310502642002-12-19019 December 2002 Request for License Amendment Measurement Uncertainty Recapture Power Uprate, Enclosures 1 - 6 2022-07-14
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Text
Justin T. Wheat Southern Nuclear Nuclear Licensing Manager Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.5998 SOUTHERN -.\
Fax 205.992.7601 NUCLEAR A SOUTHERN COMPANY AUG 1 0 2016 Docket Nos.: 50-321 NL-16-1136 50-366 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant- Units 1 and 2 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation
References:
- 1. NRC Letter, "Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012.
- 2. Letter to NRC, "Edwin I. Hatch Nuclear Plant- Units 1 and 2, Seismic Hazard and Screening Report for CEUS Sites," dated March 31, 2014.
- 3. NRC Letter, "Edwin I. Hatch Nuclear Plant- Units 1 and 2, Staff Assessment of Information Pursuant to 10 CFR 50.54(f) Seismic Hazard Reevaluations Relating to Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident," dated April27, 2015.
- 4. NRC Letter, "Final Determination of Licensee Seismic Probabilistic Risk Assessments under the Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated October 27, 2015.
Ladies and Gentlemen:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report. The requested information was submitted to the NRC for the Edwin I. Hatch Nuclear Plant Units 1 and 2 (HNP) by Southern Nuclear Operating Company (SNC) on March 31,2014 (Reference 2). On April27, 2015, SNC received the NRC's staff assessment of the HNP seismic hazard and the resulting Ground Motion Response Spectra (GMRS) (Reference 3).
The NRC issued the final determination of licensee seismic probabilistic risk assessment on October 27, 2015 (Reference 4). This NRC letter requested that HNP perform a limited-scope low frequency evaluation consistent with the seismic evaluation guidance provided in the Screening, Prioritization and Implementation Details (SPID). SNC has performed the subject evaluation as an assessment of risk significance of HNP using the principles from the SPID. The enclosure provides an overview of HNP's assessment for why the exceedance at the seismic
U.S. Nuclear Regulatory Commission NL-16-1136 Page 2 low frequency content is not risk-significant to HNP. This letter is the formal and final response to Fukushima Near-Term Task Force Recommendation 2.1 Seismic limited-scope low frequency evaluation as requested in the NRC's final determination letter (Reference 4). This information was communicated to the NRC by conference call on May 31, 2016.
This letter contains no new NRC commitments. If you have any questions, please contact John Giddens at 205.992.7924.
Mr. J. T. Wheat states he is the Nuclear Licensing Manager for 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.
Respectfully submitted, l
.; l J. T. Wheat Nuclear Licensing Manager JTW/JMG/MRE Sworn to and subscri;tjd before me this~day of Jlv~ ,2016.
d~rif~b-Notary Public My commission expires: I D - ! / Zo (1
Enclosure:
Edwin I. Hatch Nuclear Plant - Units 1 and 2 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice President- Hatch Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch RTYPE: CHA02.004
U. S. Nuqlear Regulatory Commission NL-16-1136 Page 3 U.S. Nuclear Regulatory Commission Mr. W. M. Dean, Director of the Office of Nuclear Reactor Regulations Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manager- Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch State of Georgia Mr. J. H. Turner, Director- Environmental Protection Division
Edwin I. Hatch Nuclear Plant- Units 1 and 2 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Enclosure Limited-Scope Low Frequency Evaluation
Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation Edwin I. Hatch Nuclear Plant - Units 1 and 2 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation On March 12, 2012, the Nuclear Regulatory Commission (NRC) requested each addressee in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report (Reference 1). The requested information was submitted to the NRC for the Edwin I. Hatch Nuclear Plant Units 1 and 2 (HNP) by Southern Nuclear Operating Company (SNC) on March 31,2014 (Reference 2). On April27, 2015, SNC received the NRC's staff assessment of the HNP seismic hazard and the resulting Ground Motion Response Spectra (GMRS) (Reference 3).
The NRC issued the final determination of licensee seismic probabilistic risk assessment on October 27, 2015 (Reference 4). That NRC letter requested that HNP perform a limited-scope low frequency evaluation consistent with the seismic evaluation guidance provided in the Screening, Prioritization and Implementation Details (SPID) (Reference 5).
On May 31, 2016, SNC presented to the NRC the status and results of the limited-scope low frequency (LF) evaluations. That presentation provided a comprehensive overview for why the exceedance at the seismic low frequency content is not risk-significant to HNP. This letter/enclosure serves as the formal and final submittal in response to Fukushima Near-Term Task Force Recommendation 2.1 Seismic limited-scope low frequency evaluation as requested in the NRC's final determination letter (Reference 4).
1 Approach for the Seismic Low Frequency Evaluation SNC used the guidance provided in the SPID (Reference 5) section 3.2.1.1 "GMRS Comparisons and Screening of Plants at Low Seismic Hazard Sites" to perform LF evaluations for HNP. Previous and ongoing seismic evaluations were used to screen for structures, systems, and components (SSCs) that are potentially susceptible to LF considerations. High confidence of a low probability of failure (HCLPF) capacities from these seismic evaluations were used to demonstrate that there are no safety significant SSCs with vulnerabilities due to the low frequency exceedance of the HNP Design Basis Earthquakes (DBE) by the HNP GMRS.
2 Previous and Ongoing Seismic Evaluations Several previous and ongoing seismic evaluations provided useful information in screening for LF vulnerabilities. In particular, the Seismic Margin Assessment (SMA), the USI A-46 evaluations, the Expedited Seismic Evaluation Process (ESEP) evaluations and potential work 10 CFR 50.69 work were reviewed. Figure 1 (provided within this Enclosure) shows the various spectra compared to the HNP GMRS. These previous and ongoing seismic evaluations were selected as they used seismic inputs that were comparable to the GMRS and projects that evaluated numerous SSCs.
SMA and IPEEE: HNP Unit 1 completed a full scope SMA including relay and soil failure assessments as a pilot for the EPRI Seismic Margin Assessment methodology (Reference 6).
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Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation HNP Unit 2 completed a focus scope SMA. Both of these SMAs were used for the IPEEE-seismic submittals (Reference 7). The seismic demand for the IPEEE is based on in-structure response spectra (ISRS) from seismic re-analysis of all safety related structures using a NUREG/CR-0098 type median input ground motion with a peak ground acceleration (PGA) of 0.3g which is called the Seismic Margin Earthquake (SME). Numerous SSCs were reviewed as a part of these projects, including items that could potentially be considered low frequency sensitive.
US/ A-46: In addition, both HNP units performed further seismic evaluations following the SQUG GIP to respond to USI A-46 (References 8 & 9). The ISRS used for resolution of USI A-46 were half (0.5) of the SME ISRS but conservatively defined as "median-centered realistic" ISRS. This required use of all the SQUG GIP factors that increase the seismic demand depending on type of capacity to demand comparison being performed. The USI A-46 project reviewed numerous SSCs, including items that could potentially be considered low frequency sensitive.
Figure 1 (provided within this Enclosure) shows the IPEEE SME ground spectrum and the 0.5 SME ground spectrum compared to the HNP GMRS. Note that the Hatch IPEEE SME ground spectrum is also called the Hatch HCLPF spectrum since the Hatch SMA demonstrated that all SSCs evaluated had a HCLPF capacity defined by this ground motion spectrum. The HNP SMAs and the USI A-46 evaluations were peer reviewed by consultants that participated in developing these seismic assessment methodologies. These peer reviews concluded that the HNP seismic evaluations were of high quality.
ESEP. The ESEP equipment list consisted of a selection of various types of equipment throughout the plant. Except for the Condensate Storage Tanks (CSTs),the HNP Expedited Seismic Evaluation Process (ESEP) (Reference 1O) used the full HNP SME ISRS for the seismic assessment of the Expedited Seismic Evaluation equipment. Since the CSTs are founded directly on soil at plant grade, they were evaluated using the HNP GMRS ..
10 CFR 50.69: SNC's Risk Informed Engineering group is currently performing risk assessments for HNP for possible risk-informed applications (1 0 CFR 50.69). The seismic demand is based on a seismic hazard consistent with the HNP 2.1 seismic hazard GMRS submittal. Information from this ongoing risk assessment was used to supplement, as needed, the screening for low frequency sensitive SSCs.
3 Comparison of the GMRS to Design Basis Ground Motions (DBEs) and Ground Motions used for IPEEE and USI A-46 Figure 1 provides a graphical representation and comparison of the various spectra used in previous seismic evaluations as well as the HNP GMRS and DBEs. The peak spectral acceleration (SAp) of the HNP GMRS is 0.32g, which is well below the SPID Low Hazard Threshold (LHT) defined as 0.4g. The LHT is shown in Figure 1 and pictorially demonstrates that the HNP is a low seismic hazard site. Figure 1 also shows the HNP Unit 1 and 2 DBEs.
Figure 1 shows that the 0.5 SME ground motion spectra used for the USI A-46 evaluations is equal to or greater than the DBEs for Unit 1 and Unit 2. The HNP Unit 2 DBE is basically identical to the 0.5 SME at approximately 6Hz and below. It should be noted that HNP Unit 1 and Unit 2 have shared structures, the DBE ISRS for both units are similar, and both units were E-2
Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation subsequently evaluated for ground motions of the SME for IPEEE and 0.5 SME for USI A-46.
Based on these facts, the low frequency exceedance range is considered to be 2 Hz (fL) and below (fL<2 Hz); i.e. the low frequency range where the GMRS exceeds the 0.5 SME and the Unit 2 DBE ground motion spectra.
4 Identification of SSCs that potentially have Low Frequency Failure Modes SPID section 3.2.1.1 lists examples of SSCs that could potentially be susceptible to damage from spectral accelerations at low frequencies. Screening for these and other potential low frequency vulnerabilities was performed using previous and ongoing seismic evaluations. In particular, the SMAIIPEEE and the ESEP were used as well as ongoing work within SNC for possible use in risk-informed (1 0 CFR 50.69) applications. In addition, insights from the HNP USI A-46 evaluations were used to search for SSCs that potentially could be susceptible to damage from spectral acceleration at low frequencies.
5 Seismic Capacity (HCLPF) to Demand (GMRS) Evaluation Previous and ongoing evaluations were used to compare the seismic capacity of various low frequency SSCs to the seismic demand. This information demonstrated a high confidence of a low probability of failure (HCLPF) for various SSCs that is greater than the GMRS. These HCLPF values are defined as PGA values for the specified input ground motion spectral shape.
SPID section 3.2.1.1 lists five examples of SSCs and failure modes that are potentially susceptible to damage from spectral accelerations at low frequencies. Information from past evaluations and the ongoing risk-informed application evaluations provided insights for other SSCs that should be added to the five listed in the SPID section 3.2.1.1.
The following sections provide results of the screening for SSCs that could potentially be susceptible to damage from spectral accelerations at low frequencies:
5.1 Liquid sloshing in atmospheric pressure storage tanks:
CSTs are normally the weakest link in a plant SMA evaluation. The Hatch CSTs were part of the ESEP and were evaluated using the GMRS as the input. Since the Unit 1 CST HCLPF is equal to 0.15g PGA (as shown in the HNP ESEP report (Reference 10)), the HCLPF is equal to or greater than the GMRS. Since the Unit 2 CST HCLPF is equal to 0.18g PGA (as shown in the HNP ESEP report (Reference 10)), the HCLPF is greater than the GMRS. The ongoing risk-informed evaluations have not identified any other low frequency sensitive atmospheric storage tanks.
Therefore, no low frequency vulnerabilities of atmospheric pressure storage tanks were identified.
5.2 Very flexible distribution systems with frequencies less than 2 Hz:
Using information from previous evaluations, three categories of flexible distribution systems were identified: Cable tray and conduit supports, HVAC supports, and Rod hung 831 piping.
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Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation Cable tray and conduit supports: The HNP IPEEE SMA report stated the cable tray and conduit supports have a HCLPF of at least 0.3g PGA. Cable tray and conduit support evaluations from the USI A-46 project were also reviewed. That review identified only one support that could possibly be considered potentially susceptible to low frequency accelerations. It was reevaluated using the GMRS and still demonstrated significant margin.
Therefore, the cable tray and conduit supports have a HCLPF greater than the GMRS.
HVAC supports: The HNP IPEEE SMA report stated the HVAC supports have a HCLPF of at least 0.3g PGA. Therefore, the HCLPF is greater than the GMRS.
Rod hung 831 piping: As part of the HNP IPEEE SMA all adjacent and overhead non-safety rod hung piping was evaluated and no failure or seismic interactions were identified for ground motions up to the full HNP SME. The IPEEE SME is greater than the GMRS; therefore the potential rod rung piping seismic interactions would have a HCLPF greater than the GMRS.
Therefore, no low frequency vulnerabilities of very flexible distribution systems have been identified.
5.3 Sliding and rocking of unanchored components:
HNP has procedures in place that require all safety related (Seismic Category 1) components to be anchored. While non-Category 1 components are typically anchored, they are required to be anchored if they are adjacent to Category 1 components. Any unanchored non Category 1 component must be located in an area where any sliding, rocking, or overturning of the component would not impact a Category 1 component.
Therefore, there is no low frequency vulnerability associated with sliding and rocking of unanchored components.
5.4 Fuel assemblies inside the reactor vessel:
The IPEEE evaluations for both HNP Unit 1 and HNP Unit 2 have detail assessments of the NSSS which included fuel assemblies. Information was obtained from General Electric to support those IPEEE evaluations. In both cases the seismic margin assessment demonstrated the NSSS HCLPF is greater than 0.3g PGA (SME).
After completion of the HNP IPEEE a shroud repair was installed due to potential horizontal cracking of the shroud. A seismic margin assessment performed of a typical Hatch shroud repair demonstrated the HCLPF was still greater than 0.3g PGA. Therefore the HNP NSSS HCLPF is much greater than the GMRS.
Therefore, no low frequency vulnerabilities have been identified associated with fuel assemblies.
5.5 Soilliquefaction
The IPEEE SMA evaluated settlement, differential settlement, and slope stability. The HNP Unit I project included a seismic margin assessment of soil liquefaction at the plant for a E-4
Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation ground motion equal to the IPEEE SME which is greater than the GMRS. Since the result of that seismic margin assessment demonstrated a HCLPF of 0.3g PGA the HNP site soil liquefaction HCLPF is much greater than the GMRS.
Therefore, no low frequency vulnerabilities have been identified associated with soil liquefaction.
5.6 Other SSCs:
Information from previous evaluations and the ongoing risk-informed application project provided insights for other SSCs to be added to the five listed in the SPID section 3.2.1.1 to be considered for HNP.
During the HNP IPEEE SMA, new soil-structure interaction analyses were performed (References 6 and 7). Updated soil profiles were developed and used in these SMA analyses. These updated soil profiles represent a better understanding of the HNP dynamic soil properties. In general the updated soil profiles had lower shear wave velocities than those used in the original DBE SSI analyses. In some cases these SMA SSI analyses produced ISRS that showed a shift in the frequency range of the peak spectral acceleration when compared to the original DBE ISRS. The HNP IPEEE SMA report (Reference 7) states the following:
"The Seismic Review Team (SRT) reviewed the original plant design criteria, loading conditions, and typical construction details to ensure that the Seismic Category I structures can be screened out. The soil structure interaction (SSI) performed for the SMA indicated that the maximum response of the reactor building and the control building is in the 1-to 3-Hz range, which was not predicted in the original design. To ensure the structures could be prescreened with this difference in response, a sample of the maximum SME responses was compared to the original DBE responses for these buildings. Based on this comparison and the original plant design and construction, the SRT concluded there is no concern with these structures surviving the SME. Therefore, based on the SMA screening guidelines and review by the SRT, Plant HNP Seismic Category I structures have a HCLPF level of at least 0.3g PGA."
Therefore, HNP Category I structures evaluated in the HNP IPEEE SMA have HCLPFs greater than the GMRS.
In addition, the SNC staff working on a possible risk informed application (1 0 CFR 50.69) was contacted to help identify any other SSCs that potentially have failure modes due to spectral accelerations below 2 Hz. The HNP Main stack, which is supported on piles, was identified as having a low fundamental natural frequency. The calculated natural frequency was determined to be approximately 0.6 Hz. However, the fragility analysis resulted in a HCLPF of 0.56g PGA based on ground motion reported in the HNP 2.1 seismic hazard submitted in March 2014 (Reference 2}. The GMRS PGA equals 0.1422g. As a result, it can be concluded the stack structure has a HCLPF greater than the GMRS.
Therefore, no other SSCs, based on previous or ongoing seismic evaluations, have been identified that have low frequency vulnerabilities.
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Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation 6 Conclusions In response to Near-Term Task Force Recommendation 2.1 Seismic, a limited-scope low frequency evaluation has been performed for HNP. Previous and ongoing HNP seismic evaluations were used to screen for potentially low frequency vulnerable SSCs. The previous HNP seismic evaluations included the HNP IPEEE SMA and ESEP. Insights from the HNP A-46 SQUG GIP evaluations were used to search for potentially low frequency vulnerable components (but not to define a HCLPF capacity). In addition insights and results from a potential risk-informed application {1 0 CFR 50.69) were used.
Potentially low frequency sensitive SSCs have been evaluated in previous and ongoing evaluations that used ground motions greater than the GMRS. No low frequency vulnerabilities were identified and all potentially low frequency vulnerable components were found to have a HCLPF greater than the GMRS.
The GMRS exceedance at the seismic low frequency content is not risk-significant to HNP.
Therefore, no low frequency vulnerabilities have been identified in response to the NRC request for a NTIF 2.1 Seismic limited-scope low frequency evaluation for HNP.
7 References The following references support the 2.1 Low Frequency Evaluation in this
Enclosure:
- 1. NRC Letter, "Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012.
- 2. Letter to NRC, "Edwin I. Hatch Nuclear Plant- Units 1 and 2, Seismic Hazard and Screening Report for CEUS Sites," dated March 31, 2014.
- 3. NRC Letter, "Edwin I. Hatch Nuclear Plant- Units 1 and 2, Staff Assessment of Information Pursuant to 10 CFR 50.54(f) Seismic Hazard Reevaluations Relating to Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident," dated April 27, 2015.
- 4. NRC Letter, "Final Determination of Licensee Seismic Probabilistic Risk Assessments under the Request for Information Pursuant to 10 CFR 50.54{f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated October 27, 2015.
- 5. Electric Power Research Institute (EPRI) Report 1025287, "Seismic Evaluation Guidance:
Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," dated February 2013
- 6. Electric Power Research Institute (EPRI) Report NP-7217-NL, Vol. 1-3, "Seismic Margin Assessment of the Edwin I. Hatch Nuclear Plant Unit 1," dated June 1991.
- 7. SNC letter, "Edwin I. Hatch Nuclear Plant Response to Generic Letter 88-20, Supplement 4," dated January 26, 1996 (HL-5102).
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Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation
- 8. "Unresolved Safety Issue A-46 Summary Report, Edwin I. Hatch Nuclear Plant Unit 1,"
Georgia Power Company, May 30, 1995.
- 9. "Unresolved Safety Issue A-46 Summary Report, Edwin I. Hatch Nuclear Plant Unit 2,"
Georgia Power Company, May 30, 1995.
- 10. SNC letter, "Edwin I. Hatch Nuclear Plant- Units 1&2 Expedited Seismic Evaluation Process Report- Fukushima Near-Term Task Force Recommendation 2.1 ,"dated December 30, 2014.
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Enclosure to NL-16-1136 NTTF 2.1 - Seismic Limited-Scope Low Frequency Evaluation Figure 1. Comparison of the various spectra used in previous seismic evaluations.
Hatch Units 1 and 2 0.8 - - Hatch HCLPF Spectrum (SMA)
Hatch IPEEE SME
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