Category:Letter
MONTHYEARIR 05000382/20230042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24213A1632024-08-0101 August 2024 2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 ML24137A3352024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A3742024-03-15015 March 2024 Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24032A0032024-03-0606 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23312A1832023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23158A1042023-06-0808 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment 2024-09-06
[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
[Table view] |