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 Issue dateTitle
ML26044A15725 February 2026SLR Audit Breakout Questions
ML26044A15625 February 2026Aging Management Audit Report - Edwin I. Hatch, Units 1 and 2 - Subsequent License Renewal Application
NL-25-0421, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information, Set 122 December 2025Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information, Set 1
ML25328A24224 November 2025SLR - Request for Additional Information (Final Rev. 1)
ML25100A08127 March 202520250327-Hatch-Pre-Application - Updated
ML25083A21527 March 2025March 27, 2025 Hatch Pre-Submittal Public Meeting - Southern Slides
ML24352A16713 November 2024Southern Company Presentation Slides
ML24313A10513 November 2024November 13, 2024, Hatch Pre-Submittal Public Meeting Slides (Southern Co.)
NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 202319 July 202410 CFR 50.46 ECCS Evaluation Model Annual Report for 2023
NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material22 July 202030-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material
ML17271A30730 November 2017Issuance of Amendments to Revise Actions of TS 5.5.12, Primary Containment Leakage Rate Testing Program
ML17010A37410 January 2017Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 - FSAR Part 9 -Redacted
ML17010A36110 January 2017Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 - FSAR Part 4 - Redacted
ML17010A33610 January 2017Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 - FSAR Part 1 Redacted
ML16330A1285 December 2016Request for Additional Information
ML16244A40825 August 2016Edwin I. Hatch, Unit 1 & 2, Updated Final Safety Analysis Report. Part 2 of 22
NL-16-1245, Edwin I. Hatch, Units 1 and 2, Updated Final Safety Analysis Report, Reference Drawings. Part 10 of 2225 August 2016Edwin I. Hatch, Units 1 and 2, Updated Final Safety Analysis Report, Reference Drawings. Part 10 of 22
ML15337A41421 December 2015Safety Evaluation for High Density Polyethylene Piping Alternative HNP-ISI-ALT-HDPE-01
NL-15-1628, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Final Stress Analysis for the Design of the Hdpe System3 September 2015Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Final Stress Analysis for the Design of the Hdpe System
ML14176A96124 June 2014Submittal 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
IR 05000321/201300724 January 2014IR 05000321-13-007 & 05000366-13-007; 11/04/2013 - 12/13/2013; Edwin I. Hatch Nuclear Plant, Units 1, and 2; Post Approval Site Inspection for License Renewal
ML12355A63126 November 2012SNCH082-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
NL-12-2268, Edwin I. Hatch, Unit 1, SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 1126 November 2012Edwin I. Hatch, Unit 1, SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 11
NL-12-2269, 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 1126 November 2012SNCH082-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
NL-12-2269, 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 1 of 1126 November 2012SNCH082-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 1 of 11
ML12355A63726 November 2012SNCH082-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 1 of 11
NL-11-1812, Edwin I. Hatch, Unit 2 - 2011 Updated Final Safety Analysis Report, Revision 29, Chapter 6, Engineered Safety Features Through Chapter 7, Instrumentation and Control24 October 2011Edwin I. Hatch, Unit 2 - 2011 Updated Final Safety Analysis Report, Revision 29, Chapter 6, Engineered Safety Features Through Chapter 7, Instrumentation and Control
ML08120088214 April 2008Notification of Potential Part 21 on Safety Related Noncompliance Deviation
ML07127028430 April 2007Southern Nuclear Operating Company - Quality Assurance Topical Report, ANSI N18.7-1976 Conformance Matrix, Enclosure 5
ML0706400416 March 2007Commitment Lists for Renewed Operating License (ROL) Plants with No Commitment Appendix Attached to Its ROL Sers/Nuregs for Use with IP-71003
NL-06-2611, Request for Use of Radium Hurricane Hood Category-2 and Category-311 December 2006Request for Use of Radium Hurricane Hood Category-2 and Category-3
ML07043009220 November 2006E. I. Hatch, Unit 2, Volume 1, Revision 2, Introduction Fourth Ten-Year Examination Plan
ML0626503121 September 2006Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure)
NL-06-1042, NRC Generic Letter 2006-03 Response9 June 2006NRC Generic Letter 2006-03 Response
ML0616003769 June 2006NRC Generic Letter 2006-03 Response
ML0704300816 February 2006E. I. Hatch, Unit 1, Volume 1, Revision 1, Introduction Fourth Ten-Year Inservice Inspection Plan
ML0533500026 January 2006Exemption MC6540, VT-3 Examination Containment Vent System
NL-05-1493, Third and Fourth 10-Year Interval Inservice Inspection Programs Submittal of Revised Exemption Request24 August 2005Third and Fourth 10-Year Interval Inservice Inspection Programs Submittal of Revised Exemption Request
NL-05-1372, Third and Fourth 10-Year Interval Inservice Inspection Programs, Submittal of Revised Exemption Request2 August 2005Third and Fourth 10-Year Interval Inservice Inspection Programs, Submittal of Revised Exemption Request
NL-05-0532, Third and Fourth 10-Year Interval Inservice Inspection Programs30 March 2005Third and Fourth 10-Year Interval Inservice Inspection Programs
NL-04-0563, Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension26 April 2004Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension
NL-03-0656, And Vogtle Electric Generating Plant - Request for Technical Alternative to ASME Section XI, IWA-4120(a) and IWA-43107 May 2003And Vogtle Electric Generating Plant - Request for Technical Alternative to ASME Section XI, IWA-4120(a) and IWA-4310
HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.1118 August 1999Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11
HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-52830 July 1999Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528
ML20206P6987 January 1999Ehnp Intake Structure Licensing Rept
ML20155C66022 October 1998Safety Evaluation Supporting Amends 214 & 155 to Licenses DPR-57 & NPF-5,respectively
HL-5687, Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment19 October 1998Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment
ML20237D60621 August 1998Forwards Draft SE Accepting Request to Increase Max Thermal Power from 2,558 Mwt to 2,763 Mwt,About 8 Percent Increase
NRC Generic Letter 1998-0414 July 1998NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i
ML20249A63815 June 1998Summary of 980604 Meeting W/Listed Attendees in Rockville,Md to Discuss Containment Analysis for Extended Power Uprate for Plant,Units 1 & 2.Licensee Slides Encl
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