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ML23111A21321 April 2023Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities
ML22300A20830 November 2022Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors25 April 2022Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors
ML22007A31718 January 20221, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
ML21354A74820 December 2021Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 3 of 18
ML21354A75020 December 2021Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 5 of 18
ML21354A75320 December 2021Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 8 of 18
ML21160A05716 August 2021Summary of Regulatory Audit in Support of Digital Upgrade License Amendment Request (EPID L-2020-LLA-0164)Non-Proprietary
ML21175A28714 July 2021Updated NRC Staff Draft White Paper Analysis of Applicability of NRC Regulations for Non-LWRs
ML21158A3007 June 2021Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI
IR 05000382/202109018 May 2021Notice of Violation; NRC Inspection Report 05000382/2021090 and NRC Investigation Report 4-2017-033
IA-21-006, NOV IA-21-006 Waterford Hernandez18 May 2021NOV_IA-21-006_Waterford_Hernandez
ML21071A2861 April 2021Summary of Cat. 1 Public Meeting with Entergy Operations,Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital Instrumentation and Control Interim Staff Guidance No.06,Rev.2,Licensing Processes NON-PROPRIETARY
IR 05000382/20210135 March 2021NRC Inspection Report 05000382/2021013 and NRC Investigation Report 4-2017-033
ML21039A26822 February 2021Summary of Category 1 Meetings with Entergy Operations, Inc. LAR to Install Digital Upgrade in Accordance with Digital I&C ISG No. 06, Rev. 2 for Waterford Steam Electric Station, Unit 3
ML21032A01319 February 202101/06 and 01/21/2021 Summary of - Category 1 Meetings with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C ISG No. 06, Rev. 2 for Waterford Steam Electric Station
ML20325A32117 December 2020Summary of November 4, 2020, Nonproprietary - Category 1 Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Rev. 2, Licensing Processes (Redacted)
ML20325A24117 December 2020Summary of November 18, 2020, REDACTED- Category 1 Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Rev. 2, Licensing Processes
ML20315A26717 December 2020Summary of October 21,2020, Redacted Category 1 Public Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06,Rev.2, Licensing Processes(NON-PROPRIETARY)
ML20344A05710 December 2020Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors
ML20226A27218 August 2020Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI
CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)12 August 2020Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
ML20258A08811 September 201911 to Final Safety Analysis Report, Chapter 06 - Engineered Safety Features (EPID L-2020-LLA-0164) - Redacted
ML20258A08711 September 201911 to Final Safety Analysis Report, Chapter 05 - Reactor Coolant System and Connected Systems (EPID L-2020-LLA-0164) - Redacted
ML20258A07111 September 201911 to Final Safety Analysis Report, Chapter 01 - Introduction and General Description of Plant - Redacted
CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 431 January 2019Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4
ML18275A23427 December 2018NRC Record of Decision for the License Renewal Application for Waterford, Unit 3
ML18323A10330 November 2018NUREG-1437, Suppl. 59, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Waterford Steam Electric Station, Unit 3 - Final Report
ML18282A03018 October 2018Proposed Alternative to ASME Code, Section XI, Regarding Charging Pipe Visual Inspection
ML20255A24225 July 201810 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features (EPID L-2020-LLA-0164) - Redacted
ML20255A23925 July 201810 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems (EPID L-2020-LLA-0164) - Redacted
ML20255A21825 July 201810 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (EPID L-2020-LLA-0164) - Redacted
ML18128A0678 June 2018Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
IR 05000382/201700828 December 2017NRC Design Bases Assurance Inspection Report 05000382/2017008
ML17341A12011 December 2017Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049)
W3F1-2017-0082, Submittal of the Inservice Inspection Plan and Containment Inservice Inspection Plan for the Fourth 10-Year Interval4 December 2017Submittal of the Inservice Inspection Plan and Containment Inservice Inspection Plan for the Fourth 10-Year Interval
ML17192A00727 July 2017Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3
ML17069A18722 March 2017Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024
CNRO-2016-00024, Entergy - Form 10-K for Fiscal Year Ended December 31, 201520 December 2016Entergy - Form 10-K for Fiscal Year Ended December 31, 2015
ML16278A01719 October 2016Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code
ML16256A15325 August 2016Revision 309 to Final Safety Analysis Report, Chapter 2, Site Characteristics, Section 2.5
ML16257A07925 August 2016Revision 309 to Final Safety Analysis Report, Chapter 11, Radioactive Waste Management, Section 11.2, Figures 11.2-1 Through 11.2-2
ML16257A08025 August 2016Revision 309 to Final Safety Analysis Report, Chapter 11, Radioactive Waste Management, Section 11.3, Figures 11.3-1 Through 11.3-2
ML16344A29325 August 2016Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Section 5.1, Figures 5.1-1 Through 5.1-4
ML16256A12825 August 2016Revision 309 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant, Section 1.6
ML16256A12225 August 2016Revision 309 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant, Table of Contents
ML16256A14425 August 2016Revision 309 to Final Safety Analysis Report, Chapter 2, Site Characteristics, Table of Contents
ML16257A07525 August 2016Revision 309 to Final Safety Analysis Report, Chapter 11, Radioactive Waste Management, Section 11.4, Figures 11.4-1 Through 11.4-8
ML16348A45325 August 2016Redacted Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 9, Auxiliary Systems, Section 9.5, Figures 9.5-1 Through 9.5-8
ML16256A21325 August 2016Revision 309 to Final Safety Analysis Report, Chapter 4, Reactor, Section 4.4, Figures 4.4-1 Through 4.4-11
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