Category:Letter type:W
MONTHYEARW3F1-2024-0038, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0039, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0041, Reply to a Notice of Violation, EA-24-0522024-09-19019 September 2024 Reply to a Notice of Violation, EA-24-052 W3F1-2024-0040, Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days2024-09-0303 September 2024 Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0019, (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 252024-07-22022 July 2024 (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0032, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-07-17017 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation W3F1-2024-0025, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test W3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024 Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0013, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program2024-05-0808 May 2024 Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program W3F1-2024-0018, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 252024-05-0101 May 2024 Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0014, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20242024-04-29029 April 2024 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2024 W3F1-2024-0015, Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure2024-04-24024 April 2024 Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure W3F1-2024-0016, Annual Radiological Environmental Operating Report (AREOR) - 20232024-04-24024 April 2024 Annual Radiological Environmental Operating Report (AREOR) - 2023 W3F1-2024-0017, Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.22062024-04-23023 April 2024 Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.2206 W3F1-2024-0020, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20232024-04-11011 April 2024 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 W3F1-2024-0008, Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0009, Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0012, Response to NRC Integrated Inspection Report 05000382/20230042024-03-11011 March 2024 Response to NRC Integrated Inspection Report 05000382/2023004 W3F1-2024-0006, Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days2024-02-28028 February 2024 Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0056, Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 2024-09-03
[Table view] Category:Report
MONTHYEARW3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024 Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0018, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 252024-05-0101 May 2024 Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2023-0056, Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1422021-03-22022 March 2021 Strategy 4 W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-29029 January 2021 Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2019-0043, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20182019-07-0101 July 2019 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2018 W3F1-2019-0022, Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results2019-03-14014 March 2019 Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results ML18275A2342018-12-27027 December 2018 NRC Record of Decision for the License Renewal Application for Waterford, Unit 3 W3F1-2018-0029, Submittal of Annual Report on Westinghouse Electric Co., LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20172018-06-0707 June 2018 Submittal of Annual Report on Westinghouse Electric Co., LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2017 ML17163A1852017-06-30030 June 2017 Biological Evaluation of Impacts to Federally Listed Species for Waterford License Renewal W3F1-2017-0042, Focused Evaluation of External Flooding2017-05-17017 May 2017 Focused Evaluation of External Flooding ML17023A2822017-02-27027 February 2017 Flood Hazard Mitigating Strategies Assessment ML16308A4472016-10-19019 October 2016 Final ASP Program Analysis Precursor for Waterford Steam Electric Station, Unit 3 Re. Both Emergency Diesel Generators Declared Inoperable (LER 382-2015-007) ML15268A0202015-09-23023 September 2015 Attachment 3, Fuel Thermal Conductivity Degradation Evaluation (Non-Proprietary) W3F1-2015-0042, Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 3-147 Through the End2015-07-21021 July 2015 Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 3-147 Through the End ML15204A3242015-07-21021 July 2015 Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 3-62 Through 3-146 ML15204A3232015-07-21021 July 2015 Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 1 Through 3-61 ML14129A3502014-04-29029 April 2014 Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 25, 2014 ML13220A4022013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A9692013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Waterford Steam Electric Generating Station, Unit 3, TAC No.: MF0977 W3F1-2013-0054, CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B2013-09-0909 September 2013 CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B W3F1-2013-0027, Closure Option for Generic Safety Issue - 1912013-05-16016 May 2013 Closure Option for Generic Safety Issue - 191 W3F1-2013-0024, Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 10142013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 1014 ML13120A4642013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment C, Rev. 0, Safety Injection Sump Outlet Header B Isolation, Enclosure to W3F1-2013-0024, Pages 312 - 591 of 1014 ML13120A4622013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment G, Rev. 0, Peer Review Checklist for SWEL, Enclosure to W3F1-2013-0024, Pages 820 - 1014 of 1014 ML13120A4612013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Revision 1, Wateford, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Enclosure to W3F1-2013-0024, Pages 1 - 311 of 1014 CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments W3F1-2012-0100, WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 22012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 2 ML12333A2772012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 1 2024-06-17
[Table view] Category:Technical
MONTHYEARW3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-29029 January 2021 Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2019-0022, Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results2019-03-14014 March 2019 Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results ML17163A1852017-06-30030 June 2017 Biological Evaluation of Impacts to Federally Listed Species for Waterford License Renewal ML15268A0202015-09-23023 September 2015 Attachment 3, Fuel Thermal Conductivity Degradation Evaluation (Non-Proprietary) ML13220A4022013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A9692013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Waterford Steam Electric Generating Station, Unit 3, TAC No.: MF0977 W3F1-2013-0024, Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 10142013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 1014 ML13120A4642013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment C, Rev. 0, Safety Injection Sump Outlet Header B Isolation, Enclosure to W3F1-2013-0024, Pages 312 - 591 of 1014 ML13120A4622013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment G, Rev. 0, Peer Review Checklist for SWEL, Enclosure to W3F1-2013-0024, Pages 820 - 1014 of 1014 ML13120A4612013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Revision 1, Wateford, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Enclosure to W3F1-2013-0024, Pages 1 - 311 of 1014 ML12333A2722012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 3 W3F1-2012-0100, WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 22012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 2 ML12333A2772012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 1 ML12333A2752012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 5 ML12333A2742012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 4 ML12181A4152012-06-28028 June 2012 Attachment 1 to W3F1-2012-0049, Analysis of Proposed Operating License Change, Section 4.0 Through 6.0 W3F1-2012-0040, Technical Specification Bases Update to the NRC for the Period November 1, 2011 Through April 30, 20122012-05-30030 May 2012 Technical Specification Bases Update to the NRC for the Period November 1, 2011 Through April 30, 2012 ML1005506072010-02-28028 February 2010 WCAP-17187-NP, Technical Justification for Eliminating Pressurizer Surge Line Rupture as the Structural Design Basis for Waterford Steam Electric Station, Unit 3 Using Leak-Before-Break Methodology, Enclosure 2 to W3F1-2010-0003 ML0918312592009-06-24024 June 2009 Attachment 6 to W3F1-2009-0022, HI-2094376, Rev. 0, Licensing Report for Waterford, Unit 3 Spent Fuel Pool Criticality Analysis ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 W3F1-2008-0039, Steam Generator Conditions Observed at Waterford 32008-05-20020 May 2008 Steam Generator Conditions Observed at Waterford 3 W3F1-2008-0018, Attachment 2, Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, (Non-Proprietary Version)2008-02-29029 February 2008 Attachment 2, Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, (Non-Proprietary Version) W3F1-2007-0045, Supplement to the ECCS Performance Analysis Submittal in Support of Next Generation Fuel - 1999 EM Optional Steam Cooling Model Justification2007-10-0404 October 2007 Supplement to the ECCS Performance Analysis Submittal in Support of Next Generation Fuel - 1999 EM Optional Steam Cooling Model Justification CNRO-2006-00039, Results of the Waterford 3 Pressurizer Flaw Evaluation2006-08-31031 August 2006 Results of the Waterford 3 Pressurizer Flaw Evaluation ML0523803522005-08-25025 August 2005 Steam Generator Tube Inspection Results for the 2003 Outage W3F1-2005-0045, 60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage2005-07-19019 July 2005 60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage ML0513702182005-05-17017 May 2005 Pgs. 1-61 Waterford 3 EAL Basis Document (W3-EP-001-001 Rev. Xx) ML0513702362005-05-16016 May 2005 Pgs. 62-123 Waterford 3 EAL Basis Document (W3-EP-001-001 Rev. Xx) W3F1-2005-0025, Holtec Licensing Report Errors2005-04-15015 April 2005 Holtec Licensing Report Errors W3F1-2004-0101, to Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 32004-10-19019 October 2004 to Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 3 W3F1-2004-0075, Reissue of Report BAW-2177, Analysis of Capsule W-97 Entergy Operations, Inc. Waterford Generating Station Unit 3 - Reactor Vessel Material Surveillance Program2004-09-13013 September 2004 Reissue of Report BAW-2177, Analysis of Capsule W-97 Entergy Operations, Inc. Waterford Generating Station Unit 3 - Reactor Vessel Material Surveillance Program W3F1-2004-0044, Small Break Loss-of-Coolant Accident Emergency Core Cooling System Performance Analysis2004-05-26026 May 2004 Small Break Loss-of-Coolant Accident Emergency Core Cooling System Performance Analysis ML0414101032004-04-0202 April 2004 Faxed on 04/02/94 to T.Alexion - Entergy - Waterford, Initial Engineering Evaluation for SBLOCA with DC Bus Single Failure CNRO-2003-00049, Letter Transmitting Mark-Up of Engineering Report M-EP-2003-004, Rev. 0 Fracture Mechanics Analysis for the Assessment Potential for Primary Water Stress Corrosion Crack (PWSCC) Growth, Un-Inspected Regions..., Pages 43 Through 572003-09-26026 September 2003 Letter Transmitting Mark-Up of Engineering Report M-EP-2003-004, Rev. 0 Fracture Mechanics Analysis for the Assessment Potential for Primary Water Stress Corrosion Crack (PWSCC) Growth, Un-Inspected Regions..., Pages 43 Through 57 CNRO-2003-00038, Rev. 0 to M-EP-2003-004, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element Drive Mechanism At..., Appendix D, Attachment 5 Thro2003-09-15015 September 2003 Rev. 0 to M-EP-2003-004, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element Drive Mechanism At..., Appendix D, Attachment 5 Through Enc CNRO-2003-00030, Arkansas, Unit 2 and Waterford, Unit 3, Letter CNRO-2003-00027 to NRC, Relaxation Requests to NRC Order EA-03-009, Dated July 1, 20032003-07-24024 July 2003 Arkansas, Unit 2 and Waterford, Unit 3, Letter CNRO-2003-00027 to NRC, Relaxation Requests to NRC Order EA-03-009, Dated July 1, 2003 CNRO-2003-00020, Arkansas, Unit 2 and Waterford, Unit 3, Relaxation Requests to NRC Order EA-03-0092003-06-11011 June 2003 Arkansas, Unit 2 and Waterford, Unit 3, Relaxation Requests to NRC Order EA-03-009 W3F1-2002-0099, Ses, Report of Facility Changes, Tests & Experiments for Period from June 1, 2001 Through May 31. 20022002-11-27027 November 2002 Ses, Report of Facility Changes, Tests & Experiments for Period from June 1, 2001 Through May 31. 2002 ML19066A0671986-11-30030 November 1986 Overview Description of the Core Operating Limit Supervisory System (COLSS)(CEN-312-NP, Revision 01-NP 8701270057) ML19066A0851986-04-30030 April 1986 CPC and Methodology Changes for the CPC Improvement Program (CEN-310-NP-A 8605270198) ML15350A2151985-09-0505 September 1985 Overview Description of Core Operating Limit Supervisory System (Colss)(Rev 00-NP to CEN-312-NP) 2021-09-30
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