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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
Edwin I. Hatch Nuclear Plant - Unit 1 Information Reports for Lead Test Assemblies Enclosure 4 Non-Proprietary Report NEDC-33883, Revision O GNF ARMOR Lead Test Assembly
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT GNr- Global Nuclear Fuel Global Nuclear Fuel NED0-33883 Revision 0 September 2017 Non-Proprietary Information - Class I (Public)
GNF ARMOR LEAD TEST ASSEMBLY FOR EDWIN I. HATCH NUCLEAR PLANT, UNIT 1 Copyright 2017 Global Nuclear Fuel -Americas, LLC All Rights Reserved
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public)
INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33883P Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )) .
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The design, engineering, and other information contained in this document is furnished for the purpose contained in the contract between Southern Nuclear Operating Company, Inc. (SNC) and GNF, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone for any purpose other than that 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.
11
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information - Class I (Public)
REVISION HISTORY
.Date*
Revisi.on Descr~ption of ~hange 0 09/2017 Initial Release lll
~ : ~ E D Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27~2:P~-E~T NED0-33883 Revision 0 Non-Proprietary Information - Class I (Public)
TABLE OF CONTENTS 1.0 Introduction ............................................................................................................................... 1 2.0 ARMOR Coating and LTA Description ................................................................................... 2 2.1 ARMOR Coating ........................................................................................................... 2 2.2 Lead Test Assembly Description ................................................................................... 2 3.0 Licensing Analyses ................................................................................................................... ?
4.0 LTA Program Objectives and Planned Inspections .................................................................. 8 5.0 References ................................................................................................................................. 9 LIST OF TABLES Table 2-1 Nominal ARMOR Coating Composition .................................................................. 3 LIST OF FIGURES Figure 2-1 Rod Segment Schematic .......................................................................................... .4 Figure 2-2 Segmented Rod Axial Arrangement ......................................................................... 5 Figure 2-3 Planned Lead Test Rod Locations ............................................................................ 6 lV
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public)
ACRONYMS
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Term* ',,
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ARMOR Abrasion Resistant, More Oxidation Resistant COLR Core Operating Limits Report CRDA Control Rod Drop Accident GNP Global Nuclear Fuel - Americas, LLC HNP-1 Edwin I. Hatch Nuclear Plant, Unit 1 LOCA Loss-of-Coolant Accident LTA Lead Test Assembly LTR Lead Test Rod NRC Nuclear Regulatory Commission OLMCPR Operating Limit Minimum Critical Power Ratio
(( )) (( ))
SAFDL Specified Acceptable Fuel Design Limit SNC Southern Nuclear Operating Company, Inc.
SRLR Supplemental Reload Licensing Report TMOL Thermal Mechanical Operating Limit V
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT
- NED0-33883 Revision 0 Non-Proprietary Information - Class I (Public)
ABSTRACT Southern Nuclear Operating Company, Inc. (SNC) plans to load (( )) Lead Test Assemblies (LTAs) as part of the Edwin I. Hatch Nuclear Plant, Unit 1 (HNP-1) Reload 28 Cycle 29 during the 2018 refueling outage. These bundles, also referred to as Abrasion Resistant, More Oxidation Resistant (ARMOR) LTAs, are standard GNF2 assemblies in which a ((
))
This report contains information that is to be provided to the Nuclear Regulatory Commission (NRC). Included in this report are a description of the ARMOR coating and the ARMOR L TAs, a discussion of the licensing analyses, a description of the ARMOR LTA program objectives, and measurements planned for the ARMOR LTAs.
Vl
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information - Class I (Public) 1.0 Introduction SNC plans to load (( )) LTAs as part of the HNP-1 Reload 28 Cycle 29 during the 2018 refueling outage. These bundles, also referred to as ARMOR LTAs, are planned to be in operation as part of a joint program with Global Nuclear Fuel -Americas, LLC (GNP).
This report contains information that is to be provided to the NRC to comply with Reference I.
Reference 1 provides guidelines to be followed to install and operate LTAs. Included in this report are a description of the ARMOR LTAs, a discussion of the licensing analyses, a description of the LTA program objectives, and any applicable measurements planned for the L TAs.
The LTA design is described in Section 2.0 along with the ARMOR coating that is the feature to be tested. The subject LTAs are GNF2 bundles ((
)) No other aspects of the bundle are modified. The fuel material is standard U02.
Section 3.0 describes the licensing analyses that will be performed. Section 4.0 states the objectives of the ARMOR LTA program and describes the measurements planned.
1
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information - Class I (Public) 2.0 ARMOR Coating and LTA Description As part of GNF's effort to improve fuel performance against debris fretting, GNP has developed a fuel cladding coating that provides greater resistance to cladding failure due to debris wear. The coating has been named ARMOR, based on its abrasion resistant and more oxidation resistant characteristics.
2.1 ARMOR Coating ARMOR is a (( )) coating that is applied by ((
)) as an add-on process following production of fuel cladding using standard manufacturing processes. The coating is (( )) with a nominal chemical composition as indicated in Table 2-1. ((
))
when compared with Zircaloy-2 cladding without ARMOR coating. The ARMOR coating has demonstrated (( ))
As the ARMOR coating is ((
)) by that of the base Zircaloy-2 cladding.
2.2 Lead Test Assembly Description The LTA is essentially a standard production GNF2 fuel assembly as described in Reference 2
((
)) as depicted in Figures 2-1 and 2-2. The ends of the fuel rod (( )) processes and qualification. The fuel pellet material is standard U02. As the ARMOR coating is ((
)) GNF2 fuel rod. As such, the
(( )) characteristics associated with the rods and the assembly are
(( )) As illustrated in Figure 2-3, the LTRs are located in (( )) positions in the bundle that operate at (( )) . This provides inherent margin relative to the limiting rods within the bundle which accommodates ((
))
2
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public)
Table 2-1 Nominal ARMOR Coating Composition Coating. ((
ARMOR ))
I 3
Type: NED Report Spec Name: NE00-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Daie Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public)
((
))
Figure 2-1 Rod Segment Schematic 4
, - Type, NeD Repoa Spec Nam, NE00-33883 Re,c OSoc'°08P CIMS , D~emeel SW'"s Vedfied Osle '"°"d' Se, 8, 20,,, 27'23 PM EDo NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public)
((
))
Figure 2-2 Segmented Rod Axial Arrangement 5
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public)
((
))
Figure 2-3 Planned Lead Test Rod Locations 6
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public) 3.0 Licensing Analyses For specified engineering evaluations (e.g., fuel rod thermal-mechanical), the ARMOR L TAs have been analyzed using the NRC-approved methods described in Reference 3. These methods
((
)); however, irradiated material property data of the ((
)) for installing the LTAs. To adequately conform to standard Specified Acceptable Fuel Design Limits (SAFDLs), the following conservatisms are introduced:
- Fuel rod engineering evaluations to establish the LTR Thermal Mechanical Operating Limits (TMOLs) will apply ((
)) in material properties.
- The LTRs shall be limited in number to ((
))
e The LTAs shall be installed into core locations that are not limiting with respect to thermal limits as stipulated by Reference 3.
Because the ARMOR coating is ((
)) to the analysis and monitoring of the LTAs. While the axial heat flux distribution is ((
)) margin to boiling transition for the LTRs. As such, the ((
)) is applicable to the LTAs. Additionally, the LTAs shall be installed into non-limiting core locations resulting in increased margin. Standard reload licensing analyses will be performed for the L TAs for each cycle of operation. Preliminary evaluations confirm that the presence of ((
)) to the characteristics of the core.
Plant dependent, cycle independent events (e.g., Control Rod Drop Accident (CRDA), fuel handling accident, Loss-of-Coolant Accident (LOCA), and fuel storage) are considered to ensure conformance to established regulatory requirements. Because the ARMOR coating is thin, the zircaloy characteristics dominate, and the existing evaluations are adequate to support the safe installation and operation of the LTAs.
SNC intends to insert the LTAs into HNP-1 starting in Cycle 29 and to operate them under Technical Specification 4.2.1. An evaluation of the effects due to the introduction of the LTAs will be performed under 10 CFR 50.59. However, cycle-specific analyses to establish fuel operating limits are not yet complete. When cycle-specific analyses are complete, GNF and SNC will document the results in each respective Supplemental Reload Licensing Report (SRLR). SNC will update the HNP-1 Core Operating Limits Report (COLR) accordingly.
7
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Dccument Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information - Class I (Public) 4.0 LTA Program Objectives and Planned Inspections The purpose of the ARMOR LTA program is to demonstrate the coating integrity throughout the expected operational life of the LTRs. The program also offers the opportunity to ((
)), thereby supporting fuel rod design for reload application.
Poolside surveillance is planned throughout the irradiation period and ((
)) may be performed. The frequency and extent of these surveillances and examinations will be jointly developed by SNC and GNF consistent with the operational constraints at HNP-1 as determined by SNC.
8
Type: NED Report Spec Name: NED0-33883 Rev: 0 Security/IP: Class 1 Document Status: Verified Date Printed: Sep 8, 2017 4:27:23 PM EDT NED0-33883 Revision 0 Non-Proprietary Information- Class I (Public) 5.0 References
- 1. Letter, T. A. Ippolito (NRC) to R. E. Engel (GE), "Lead Test Assembly Licensing,"
MFN-182-81, September 23, 1981.
- 2. Global Nuclear Fuel, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," NEDC-33270P, Revision 8, April 2017.
- 3. Global Nuclear Fuel, "General Electric Standard Application for Reactor Fuel (GESTAR II),"
NEDE-24011-P-A-25, March 2017.
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