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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
[Table view] |
Text
David H. Jones Southern Nuclear Vice President Operating Company, Inc.
Engineering 40 Inverness Center Parkway Birmingham. Alabama 35242 Tel 205.992.5984 Fax 205.992.0341 50UIHERNA COMPANY May 2,2008 Energy to Serve lOurWorM'"
Docket No.: 50-366 NL-08-0590 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Unit 2 Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding Ladies and Gentlemen:
Southern Nuclear Operating Company (SNC) submitted an exemption request for the referenced subject in letter NL-08-0380 dated March 21, 2008. GNF has provided SNC with updated proprietary and nonproprietary reports. These reports, along with an updated proprietary affidavit, are being submitted as a replacement for the information provided in SNC's March 21, 2008 submittal.
This submittal supersedes NL-08-0380 in its entirety.
SNC requests an exemption from the fuel cladding material requirement in 10 CFR 50.46, and 10 CFR 50 Appendix K in order to load a small number of lead test assemblies (LTAs) into the Hatch-2 reactor during the 2009 Refueling Outage (2RF020). This exemption is requested because these LTAs will include fuel rods manufactured with a cladding material, called GNF-Ziron, which is similar in composition to Zircaloy-2, but contains a slightly higher iron content than specified in ASTM 8350. Irradiation of LTAs with GNF-Ziron fuel rods will enable SNC to acquire in-reactor operating experience with this material.
A modified zirconium alloy material for fuel components, GNF-Ziron, has been under development by GNF for over two decades. The properties of this material have been tested in various forms, including irradiation of cladding, spacers and water rods in a small quantity of LTAs in a foreign reactor of up to 68 gigawatt days per metric ton uranium (GWd/MTU). Results of these tests indicate that the corrosion properties of GNF-Ziron are similar to Zircaloy-2. However, there is a significant reduction in hydrogen pickup at higher exposures.
In order to further evaluate GNF-Ziron as an alternative to the industry standard Zircaloy-2 for fuel rods, SNC intends to load two standard GE 14 fuel assemblies with GNF-Ziron rods into the Hatch-2 reactor starting in operating Cycle 21.
U. S. Nuclear Regulatory Commission NL-08-0590 Page 2 Since the current regulations (10 CFR 50.46 and 10 CFR 50 Appendix K) restrict cladding material to either zircaloy or ZIRLO, SNC is requesting an exemption to this requirement for this lead test program. Enclosure 2 describes the technical basis for concluding that this exemption will not result in an increased risk to the health and safety of the public. In the 2 nd Quarter of 2008, GNF plans to submit a materials application licensing topical report (LTR) to the NRC documenting the GNF-Ziron properties and providing evaluations of the application of GNF-Ziron in GEH and GNF methods.
NRC authorization to proceed with this proposed LTA program is requested by August 15, 2008, to support the manufacturing of GNF-Ziron fuel rods for the Hatch-2 Reload 20 fuel.
Enclosure 1 contains the Global Nuclear Fuel Affidavit and the authorization to apply for its withholding. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b) (4) of 10 CFR 2.390 of the Commission's regUlations. Accordingly, it is respectfully requested that the information, which is proprietary to Global Nuclear Fuel, be withheld from public disclosure in accordance with 10 CFR 2.390 of the Commission's regulations. Enclosure 2 contains information proprietary to Global Nuclear Fuel, which is supported by the affidavit signed by Global Nuclear Fuel, the owner of the information. Enclosure 3 contains the nonproprietary version of Enclosure 2. The designation of proprietary in information in Enclosures 2 and 3 has been revised by GNF.
Mr. D. H. Jones 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.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, ZTHE UCLEAR OPERATING COMPANY D. H. Jones Vice President - Engineering *'l <.
SEtIt ~d before me this,t~ day of 1114l1j ,2008.
Notary 'public My commission expires: J:~ ~ .,tt)/()
DHJIWRM/daj
\
U. S. Nuclear Regulatory Commission NL-08-0590 Page 3
Enclosures:
- 1. Global Nuclear Fuels - Americas Affidavit
- 2. GNF-0000-0079-7396P, Strategy and Technical Basis Supporting GNF-Ziron Introduction into the Hatch Nuclear Plant, March 2008 (Proprietary)
- 3. GNF-0000-0079-7396NP, Strategy and Technical Basis Supporting GNF-Ziron Introduction into the Hatch Nuclear Plant, March 2008 (Nonproprietary) cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President - Hatch RTYPE: CHA02.004 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Acting Regional Administrator Mr. R. E. Martin, NRR Project Manager - Hatch Mr. J. A. Hickey, Senior Resident Inspector - Hatch State of Georgia Mr. N. Holcomb, Commissioner - Department of Natural Resources
Edwin I. Hatch Nuclear Plant - Unit 2 Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding Enclosure 1 Global Nuclear Fuels - Americas Affidavit
Global NDclear Fuel- Americas AFFIDAVIT I, Andrew A. Lingenfelter, state as follows:
(1) I am Vice President, Fuel Engineering, Global Nuclear Fuel - Americas, LLC
("GNF-A"), and have been delegated the function of reviewing the information described in par~graph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in GNF Report, GNF-0000 0079-7396P, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction into the Hatch Nuclear Plant, April 2008. The proprietary information in GNF Report, GNF-0000-0079-7396P, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction into the Hatch Nuclear Plant, A8ril 2008, is identified by a single ((<J.9.n~gJm4~F.Umt~jg~ ..49.yp.l~.§gm\r~.J?@~.l&~1~ .. _~)). Figures and other large objects are identified with double square brackets before and after the object. In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower defInition of trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatorv Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group
- v. FDA, 704F2d1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; GNF-OOOO-0079-7396P Affidavit Page 1 of 3
- c. Information which reveals aspects of past, present, or future GNF-A customer funded development plans and programs, resulting in potential products to GNF-A;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. Access to such documents within GNF-A is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology.
The development of the methods used in these analyses, along with the testing, development and approval of the supporting methodology was achieved at a significant cost, on the order of several million dollars, to GNF-A or its licensor.
GNF-OOOO-0079-7396P Affidavit Page 2 of 3
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 3rd day of April 2008.
Andrew A. Lingenfelter Vice President, Fuel Engineering Global Nuclear Fuel-Americas, LLC GNF-OOOO-0079-7396P Affidavit Page 3 of 3
Edwin I. Hatch Nuclear Plant - Unit 2 Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding Enclosure 3 GNF-0000-0079-7396NP, Strategy and Technical Basis Supporting GNF-Ziron Introduction into the Hatch Nuclear Plant - March 2008 (Nonproprietary)
GNF-0000-0079-7396NP Class I DRF 0000-0079-7396 April 2008 Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction into the Hatch Nuclear Plant Copyright 2008 Global Nuclear Fuels-Americas, LLC All Rights Reserved
Non-Proprietary Information GNF-0000-0079-7396NP Class I INFORMATION NOTICE This document is a non-proprietary version of GNF-0000-0079-7396P, which has the proprietary information removed. Portions of the document that have been removed are indicated by double open and closed brackets as shown here (( )).
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The information contained in this document is furnished solely for the purpose(s) stated in the transmittal letter. The only undertakings of GNF with respect to information in this document are contained in contracts between GNF and participating utilities, and nothing contained in this document shall be construed as changing those contracts. The use of this information by anyone other than those participating entities and for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.
Page 2 of 11
Non-Proprietary Information GNF-0000-0079-7396NP Class I Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction into the Hatch Nuclear Plant I.
Purpose:
Southern Nuclear - Southern Company (SNC) and Global Nuclear Fuel (GNF) intend to establish an option for use of GNF-Ziron fuel cladding in the Edwin I Hatch Nuclear Plant (Units 1 and 2). This document describes the licensing basis for using GNF-Ziron in Plant Hatch to obtain operating experience with GNF-Ziron cladding material. It is proposed that this operating experience be obtained through irradiation of two GE14 Lead Test Assemblies with selected rods (( )) clad with GNF-Ziron in Plant Hatch Unit 2 during Cycles 21, 22 and 23. The purpose of this document is to provide the technical bases to support SNCs request for exemption to cladding-specific requirements of 10 CFR 50.46, and 10 CFR Part 50 Appendix K. In addition, this document also discusses licensing approach to meeting the requirement in Reference 1 that lead test assemblies be analyzed with approved methods.
II. GNF-Ziron Characteristics and Properties GNF-Ziron is a zirconium-based alloy that is a slight modification to Zircaloy-2, which is widely used in the BWR industry as the material for fuel rod cladding and other fuel assembly components. The primary compositional difference is in the iron content of GNF-Ziron, which is selected to be above the range for Zircaloy-2 as specified in the ASTM B350 industry standard.
GNF-Ziron has an ((
)) For Zircaloy-2, the ASTM standard B350 describes the compositional requirements on Sn, Fe, Cr and Ni as the major alloying elements, but the oxygen content is not defined. ((
)) A comparison of the minimum and maximum compositions for ASTM and GNFs CC Zircaloy-2, and GNF-Ziron is given in Table 1.
Table 1 Comparison of the minimum, maximum and typical compositions for ASTM Zircaloy-2, GNFs CC Zircaloy-2, and GNF-Ziron Zircaloy-2 GNF-Ziron wt% ASTM Controlled Chemistry Min Max Min Max Typical Min Max Typical Sn 1.20 1.70 (( ((
Fe 0.07 0.20 Cr 0.05 0.15 Ni 0.03 0.08 O per PO FeCrNi 0.18 0.38 Zr 97.9 98.6 )) ))
As Table 1 shows, GNF-Ziron is similar to both ASTM and CC Zircaloy-2, in that all three types of alloy are based on ((
)) iron content is increased. It should be noted that the indicated composition range for GNF-Ziron is ((
Page 3 of 10
Non-Proprietary Information GNF-0000-0079-7396NP Class I
))
Table 1 also shows the typical or expected target compositions for GNFs CC Zircaloy-2 and GNF-Ziron. It is noted that the difference in the target/typical ((
)) As a comparison, this compositional difference is small compared to the changes associated with recent introduction of other new cladding materials in the PWR sector to replace Zircaloy-4, a zirconium based alloy similar to Zircaloy-2 but without nickel and with 0.18 - 0.24wt% iron and 0.07 - 0.13wt% chromium.
The material properties that are inputs to approved methods for evaluating the performance of fuel rods during various operating conditions (e.g. normal operation, LOCA) were evaluated and will be documented in a Licensing Topical Report (LTR) to be submitted to the NRC. The contents of the LTR are discussed further in the next section. A number of properties or characteristics for GNF-Ziron were obtained through testing; these are listed in Table 2. A number of other properties are governed by ((
)) these properties are provided in Table 3.
Based on the evaluation of properties in Tables 2 and 3, GNF concludes that the properties of GNF-Ziron are ((
)) One notable feature of GNF-Ziron is a lower propensity to absorb corrosion-released hydrogen, despite a similar corrosion performance compared with Zircaloy-2. This reduced tendency to absorb hydrogen is the primary reason to consider GNF-Ziron as a fuel rod cladding material.
Table 2 Material Characteristics and Properties Assessed Based on Test Data
((
))
Page 4 of 10
Non-Proprietary Information GNF-0000-0079-7396NP Class I Table 3
((
))
III. Reload Licensing Strategy A. Current GNF-Ziron Status in the GE14 Licensing Basis GE14 fuel is licensed according to criteria and requirements specified in GESTAR II (General Electric Standard Application For Reactor Fuel, NEDE-24011-P-A), as reported in the GE14 compliance report (GE14 Compliance With Amendment 22 of NEDE-24011-P-A, NEDC-32868P, Rev. 2). The GE14 compliance report states that the GE14 fuel cladding and water rods are made of Zircaloy-2. Because the composition of GNF-Ziron deviates slightly from the ASTM-specification ranges for Zircaloy-2 (ASTM Standard B350 for UNS60802), as described in the previous section [see also Table 1], the application of the GE14 licensing basis to GE14 fuel with GNF-Ziron material must be addressed.
B. Two-Phase Approach GNF proposes to approach the licensing basis for introduction of GNF-Ziron fuel cladding in two phases, which were discussed in a LTR pre-submittal meeting with the NRC during July, 2007
[FLN-2007-026,
Subject:
Ziron and Additive Fuel Pre-Submittal Meeting, Final Presentations July 24, 2007]. Phase 1 consists of GNF preparing and submitting a LTR. The LTR will address the application of GNF-Ziron to GNF Fuel Designs for reload applications. This submittal is necessary because GNF-Ziron is not addressed in the GE14 compliance report, which stated Zircaloy-2 as the cladding material, and because GNF-Ziron cannot be considered as Zircaloy-2, as discussed above. This LTR will compare the properties of GNF-Ziron with those of Zircaloy-2 ((
)) Once approved by the NRC, this LTR together with the GE14 compliance report will permit the application of GNF-Ziron on a reload basis for the GE14 fuel design, and accordingly, the GE14 compliance report will be revised to include the use of GNF-Ziron. Phase 1 will not invoke advantages of Page 5 of 10
Non-Proprietary Information GNF-0000-0079-7396NP Class I GNF-Ziron, ((
)) Phase 2, the schedule for which remains to be determined, will require the submittal to the NRC of a separate LTR on GNF-Ziron ((
))
IV. Lead Test Assemblies (LTA) Program at Plant Hatch GNF and SNC are proposing a Lead Test Assembly (LTA) irradiation program at Plant Hatch to provide in-reactor experience with the GNF-Ziron cladding in GE14 fuel. (The LTAs may also include GNF-Ziron ((
)) This operating experience, along with the revised GE14 compliance report to be issued following the approval of the GNF-Ziron LTR, will form the basis for future reload applications of GE14 fuel clad with GNF-Ziron at Plant Hatch.
SNC has agreed to irradiate two GE14 LTAs with selected rods ((
)) clad with GNF-Ziron in the Plant Hatch Unit 2 reactor during Cycles 21, 22 and 23.
Specific locations of the GNF-Ziron fuel rods in the LTAs have not been determined yet; however, it should be noted that the nuclear configuration of the LTAs would be the same as one of the reload 20 fuel batches. SNC has informed GNF that use of GNF-Ziron cladding is not prevented by the Plant Hatch Technical Specifications; therefore, subsequent to NRC-approval of this submittal, loading the LTAs into the Hatch-2 reactor will be evaluated as a change to the Plant as required by 10 CFR 50.59. GNF will provide SNC with technical information to support this evaluation. Consistent with the approach used for the GNF-Ziron LTR, the evaluations of the LTAs will be performed using GESTR-Mechanical (GESTR-M)
(Acceptance of Referencing of Licensing Topical Report NEDE-24011-P-A Amendment 7 to Revision 6, GE Standard Application for Reactor Fuel Letter, C.O. Thomas (NRC) to J.S.
Charnley (GE), MFN-036-85, March 1, 1985) and other approved methods.
V. Review of Methods As described in Reference 1 As long as the analysis of the LTAs using approved methods meets the approved criteria, it would be concluded that no unreviewed safety question exists.
GEH/GNF currently performs fuel rod thermal-mechanical design and licensing analyses with the GESTR-M code and its associated application methodology. A key part of the statistical methodology is the inclusion of model uncertainty based upon the GESTR-M qualification results. This prediction uncertainty, couched in terms of a corresponding uncertainty in ((
)) In addition to this model uncertainty, ((
))
Fuel rods are designed such that, if they are operated within their specific thermal-mechanical operating limits of power versus exposure (LHGR limits), all licensing and design criteria are explicitly satisfied. The LHGR limits are specified to ensure compliance with the primary fuel rod thermal-mechanical licensing and design constraints.
The primary thermal-mechanical licensing parameters that may be impacted by the introduction of a new cladding material such as GNF-Ziron are:
Page 6 of 10
Non-Proprietary Information GNF-0000-0079-7396NP Class I
((
))
An assessment of the impact of the Ziron cladding for each of these parameters has been performed. The conclusion from the assessment was that, ((
)) implementation of GNF-Ziron will have no detrimental impact on thermal-mechanical licensing limits or margins.
In addition to the thermal-mechanical design limits associated with GESTR-M, GNF uses a number of other NRC approved methods to demonstrate compliance with other design limits.
GNF has evaluated the potential impact of incorporating GNF-Ziron properties into these methods (nuclear, thermal hydraulic, safety limit MCPR, transient analyses, stability, ATWS, rod drop accident, channel bow, and LOCA) and concluded there is no significant impact on the use of these methods as a result of this change. This conclusion is consistent with ((
)) The assessment will be provided in the LTR, which will be submitted to the NRC.
VI. Technical Basis for Exemptions to 10 CFR 50.46 and Part 50 Appendix K Title 10 of the Code of Federal Regulations (10 CFR) Part 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, requires that the calculated emergency core cooling system (ECCS) performance for reactors with Zircaloy or ZIRLO fuel cladding meet certain criteria. 10 CFR Part 50 Appendix K, ECCS Evaluation Models, further requires that the Baker-Just equation be used in the ECCS evaluation model to determine the rate of energy release, cladding oxidation, and hydrogen generation after a postulated loss-of-coolant accident (LOCA). The Baker-Just equation presumes the use of Zircaloy or ZIRLO fuel cladding. There is no provision for cladding material other than Zircaloy or ZIRLO in 10 CFR 50.46 and Part 50 Appendix K. Exemptions to 10 CFR 50.46 and Part 50 Appendix K are therefore required for the use of GNF-Ziron as the cladding material.
In 10 CFR 50.46 and within the Baker-Just equation, no differentiation is made between types of Zircaloy, specifically between the commercially available Zircaloy-2 and Zircaloy-4. The underlying reason is that differences in composition between the two types of Zircaloy are not sufficient to result in significant differences in the high temperature oxidation characteristics. As noted in Section II, the composition of GNF-Ziron deviates only slightly from that of Zircaloy-2.
((
))
10 CFR 50.46 has requirements related to the maximum cladding oxidation, peak cladding temperature, maximum hydrogen generation, coolable geometry and long-term cooling. High temperature oxidation tests have been conducted ((
)) to demonstrate the applicability of the Baker-Just equation to GNF-Ziron and the results are shown in Figure 1. Figure 1 shows that the use of the Baker-Just equation remains conservative in the postulated LOCA circumstances relative to the measured GNF-Ziron data.
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Non-Proprietary Information GNF-0000-0079-7396NP Class I The maximum cladding oxidation and peak cladding temperature limits are collectively known as the embrittlement criteria. In order to address the potential embrittlement due to absorbed hydrogen associated with a postulated LOCA, ((
)) The predicted ECR values were calculated using the Baker-Just equation. The test results showed that ((
)) The test results thus indicate margin to embrittlement relative to the 17% ECR clad oxidation limit stated in 10 CFR 50.46.
As noted in Section II, the Fe content of GNF-Ziron deviates only slightly from that of Zircaloy-2,
(( )) Consequently, a significant change in the hydrogen generated from cladding-water reaction is not expected. Moreover, in the context of the proposed LTAs for Hatch Unit 2, any core-wide change in hydrogen generation due to a change from Zircaloy-2 to GNF-Ziron would be further diminished by the fact that only two assembles will be involved ((
)) Additionally, the composition change is ((
)) The potential effect on hydrogen generation due to replacing one Zr atom with a Fe atom can be estimated as follows. Each Zr atom will react with two H2O molecules to form stoichiometric ZrO2, thereby releasing 4 hydrogen atoms. Since Fe has a lower valence than Zr, each Fe atom can result in the release of 2, 3, or 2.67 atoms of hydrogen depending on whether stoichiometric Fe0, Fe2O3 or Fe304, respectively, is formed from the reaction with water. The expected result of replacing one Zr atom with one Fe atom is therefore a reduction in the number of released hydrogen atoms. Thus, ((
)) evaluation of hydrogen release based on GNF-Ziron cladding is conservatively bounded by the calculation based on Zircaloy-2 cladding. Furthermore, any difference in calculated hydrogen generation would be slightly less for the GNF-Ziron case.
The coolable geometry criterion is generally addressed through high temperature perforation tests. A comparison of test data obtained from GNF-Ziron with available data for Zircaloy-2 is shown in Figure 2, which shows that the ((
))
(( )) the high temperature test results described above thus demonstrate with a high degree of confidence that the underlying requirements of 10 CFR 50.46 and Part 50 Appendix K are met when GNF-Ziron is used as the cladding material. Therefore, there is no anticipated decrease in coolability or increase in dose consequences as a result of a postulated LOCA for GNF-Ziron relative to evaluations performed assuming Zircaloy cladding.
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Non-Proprietary Information GNF-0000-0079-7396NP Class I
((
))
Figure 1 Weight gain data for GNF-Ziron(( )) compared with Baker-Just
((
))
Figure 2 Perforation hoop stress of GNF-Ziron cladding compared with Zircaloy-2 data Page 9 of 10
Non-Proprietary Information GNF-0000-0079-7396NP Class I VII. Summary 10 CFR 50.46 and Part 50 Appendix K explicitly state or implicitly assume the cladding material to be zircaloy or Zirlo. In order to allow the development and in-reactor testing of a fuel cladding material which is neither zircaloy nor Zirlo, it is necessary to request the NRC grant exemptions to 10 CFR 50.46 and Part 50 Appendix K for the Plant Hatch LTAs containing GNF-Ziron cladding. Based on the (( )) and the high temperature test results, the underlying requirements of 10 CFR 50.46 and Part 50 Appendix K are shown to be met with a high degree of confidence when GNF-Ziron is used as the cladding material.
(( )) GNF has concluded that evaluations based on the currently approved methods (including GESTR-M) for fuel rod performance during various operating conditions, including accidents, are fully applicable to GE14 fuel bundles with GNF-Ziron fuel rod cladding. The GE14 LTAs with selected rods clad with GNF-Ziron to be inserted in Plant Hatch Unit 2 reactor during Cycles 21, 22 and 23 will be evaluated using existing approved methods utilizing the equivalency in properties.
VIII. References
- 1. NRC Letter, Lead Test Assembly Licensing, T. A. Ippolito (NRC) to R. E. Engel, September 23, 1981.
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