| NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 | 14 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 Application | 2 December 2021 | National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application | Ultimate heat sink
License Renewal
Biofouling
Power Uprate |
| NL-20-1295, 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B | 14 December 2020 | 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B | |
| ML20303A178 | 29 September 2020 | Submittal of Revision 38 to Updated Final Safety Analysis Report | Qualified Offsite Circuit
License Renewal
Fuel cladding
Offsite Circuit |
| 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 1 | 30 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 | Nondestructive Examination
Dissimilar Metal Weld |
| NL-18-0282, Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch | 4 April 2018 | Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch | |
| NL-17-1916, Pressure and Temperature Limits Report | 27 November 2017 | Pressure and Temperature Limits Report | Hydrostatic
Pressure and Temperature Limits Report |
| ML18012A058 | 31 October 2017 | NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. | Earthquake |
| NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. | 31 October 2017 | NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. | Earthquake |
| NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. | 31 October 2017 | NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. | Earthquake |
| NL-18-0026, NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. | 30 September 2017 | NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. | Fuel cladding |
| NL-17-1255, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation | 22 August 2017 | Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation | Mission time
Internal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Seismically rugged
Large early release frequency
Earthquake |
| NL-16-2466, Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion | 15 December 2016 | Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion | High Radiation Area
Ultimate heat sink
Probabilistic Risk Assessment
Emergency Lighting
Locked High Radiation Area
FLEX
Fukushima Dai-Ichi
Seismically rugged
Design basis earthquake
Earthquake
Power-Operated Valves
Power Operated Valves |
| NL-16-1136, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation | 10 August 2016 | Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation | Probabilistic Risk Assessment
Fukushima Dai-Ichi
Design basis earthquake
Earthquake |
| NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B | 2 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 Package | 24 November 2014 | Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package | Dissimilar Metal Weld |
| ML14223A794 | 31 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 | Anticipated operational occurrence
Minimum Critical Power Ratio |
| ML14176A961 | 24 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 | Fire Barrier
Coatings
Foreign Material Exclusion |
| NL-14-0343, Seismic Hazard and Screening Report for CEUS Sites | 31 March 2014 | Seismic Hazard and Screening Report for CEUS Sites | Probabilistic Risk Assessment
Fukushima Dai-Ichi
Design basis earthquake
Earthquake |
| ML13364A202 | 27 February 2014 | Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown
High winds
Ultimate heat sink
Tornado Missile
Time to boil
Safe Shutdown Earthquake
Internal Flooding
Operating Basis Earthquake
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Tornado Missile Protection
Design basis earthquake
Containment Hardened Vent
Frazil ice
B.5.b Mitigating Strategies
Earthquake |
| ML14045A147 | 12 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 | Safe Shutdown
High winds
Ultimate heat sink
Tornado Missile
Time to boil
Safe Shutdown Earthquake
Internal Flooding
Operating Basis Earthquake
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Tornado Missile Protection
Design basis earthquake
Containment Hardened Vent
Frazil ice
B.5.b Mitigating Strategies
Earthquake
Hardened vent
GOTHIC |
| NL-13-0402, GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 | 31 January 2013 | GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 | |
| ML13115A473 | 31 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) | 7 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) | Weld Overlay
Finite Element Analysis
Liquid penetrant
Dissimilar Metal Weld |
| NL-11-1131, Unit 2, GNF-Ziron Lead Test Assemblies | 16 June 2011 | Unit 2, GNF-Ziron Lead Test Assemblies | Exemption Request
Fuel cladding |
| NL-10-0824, Hatch, Unit 2, GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties. | 31 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. | 31 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. | 31 March 2010 | GNF-0000-0113-8604NP, GNF-Ziron Performance Benefits and Licensing Requirements Assessment. | Anticipated operational occurrence
B.5.b Mitigating Strategies
Fuel cladding |
| ML101340740 | 31 March 2010 | GNF-0000-0114-0175NP, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction. | |
| ML101340738 | 31 March 2010 | GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties. | |
| NL-09-0503, Response to Preliminary White Finding on 1B EDG Coupling Failure | 15 April 2009 | Response to Preliminary White Finding on 1B EDG Coupling Failure | Mission time
Probabilistic Risk Assessment
Finite Element Analysis
Significance Determination Process
Preliminary White Finding |
| ML091600672 | 31 March 2009 | GE-NE-0000-0080-0259-NP-R4, Shroud Repair Replacement of Upper Support Stress Analysis Report, Public | Finite Element Analysis
Flow Induced Vibration |
| NL-08-1781, Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap | 19 December 2008 | Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap | Weld Overlay |
| 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 Cladding | 22 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 | Exemption Request
Fuel cladding |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer
Power change |
| ML082250037 | 31 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 2008 | 31 July 2008 | GNF-0000-0088-6043NP, Enclosure 6, Properties of GNF-Ziron, July 2008 | Finite Element Analysis
Fuel cladding |
| NL-08-1250, GNF-0000-0088-6047NP, Enclosure 4, Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits, July 2008 | 31 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. | 30 June 2008 | GE-NE-0000-0080-0259-R2, Hatch 2 Nuclear Plant, Shroud Repair Replacement of Upper Support Stress Analysis Report. | Finite Element Analysis
Flow Induced Vibration |
| NL-08-0634, Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses | 5 May 2008 | Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses | Power Uprate |
| NL-08-0590, Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding | 2 May 2008 | Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding | Exemption Request
Fuel cladding |
| NL-08-0380, Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding | 21 March 2008 | Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding | Fuel cladding |
| ML062490242 | 29 August 2006 | Enclosure 1, E. I. Hatch Request to Implement an Alternative Source Term - AST Safety Assessment | Safe Shutdown
High winds
Mission time
Safe Shutdown Earthquake
Seismically rugged
Design basis earthquake
Earthquake
Deep Dose Equivalent
Power Uprate |
| ML062490492 | 28 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 | Hydrostatic
Seismically rugged
Design basis earthquake
Earthquake |
| ML062490498 | 28 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 | Safe Shutdown
Safe Shutdown Earthquake
Design basis earthquake
Earthquake |
| ML043430475 | 20 October 2004 | SIR-04-120, Rev. 0, Elastic-Plastic Fracture Mechanics Evaluation of the Plant Hatch Unit 1, Core Shroud V5 and V6 Welds. | Finite Element Analysis |
| ML080290231 | 12 February 2004 | Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 | Power change |
| ML062490259 | 30 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. | FLEX
Seismically rugged
Earthquake
Weak link |
| ML031180057 | 25 April 2003 | Results of the Edwin I. Hatch Generating Station Units 1 and 2 SDP Phase 2 Notebook Benchmarking Visit | Internal Flooding
Significance Determination Process |
| ML031050264 | 19 December 2002 | Request for License Amendment Measurement Uncertainty Recapture Power Uprate, Enclosures 1 - 6 | Reactor Vessel Water Level
Ultimate heat sink
Anticipated operational occurrence
Feedwater Controller Failure
Fuel cladding
Fire Protection Program
Flow Induced Vibration
Coast down |