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| Issue date | Title | Topic | |
|---|---|---|---|
| W3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 | 19 December 2023 | Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 | |
| ML23325A144 | 21 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 Days | 27 June 2022 | SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days | |
| 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 L | 6 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 | |
| ML21083A136 | 23 March 2021 | Completed Activities | |
| ML21083A144 | 22 March 2021 | Strategy 6 | |
| ML21083A138 | 22 March 2021 | Rulemaking | |
| ML21083A143 | 22 March 2021 | Strategy 5 | |
| ML21083A142 | 22 March 2021 | Strategy 4 | |
| ML21083A140 | 22 March 2021 | Strategy 2 | |
| ML21083A141 | 22 March 2021 | Strategy 3 | |
| ML21083A139 | 22 March 2021 | Strategy 1 | |
| ML21083A137 | 22 March 2021 | NEIMA Reporting | |
| ML21014A267 | 14 January 2021 | Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy | Probabilistic Risk Assessment Exemption Request |
| W3F1-2019-0043, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2018 | 1 July 2019 | Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2018 | |
| ML18275A234 | 27 December 2018 | NRC Record of Decision for the License Renewal Application for Waterford, Unit 3 | Incorporated by reference License Renewal Environmental Justice |
| W3F1-2018-0029, Submittal of Annual Report on Westinghouse Electric Co., LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2017 | 7 June 2018 | Submittal of Annual Report on Westinghouse Electric Co., LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2017 | |
| W3F1-2017-0042, Focused Evaluation of External Flooding | 17 May 2017 | Focused Evaluation of External Flooding | Ultimate heat sink FLEX Fukushima Dai-Ichi Time Critical Operator Action Flood Hazard Mitigation Strategies Assessment Flooding Focused Evaluation |
| ML17023A282 | 27 February 2017 | Flood Hazard Mitigating Strategies Assessment | Boric Acid FLEX Fukushima Dai-Ichi Flood Hazard Mitigation Strategies Assessment |
| ML16308A447 | 19 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) | Mission time Significance Determination Process |
| 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 End | 21 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 | Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Frazil ice |
| ML15204A324 | 21 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 | Earthquake |
| ML15204A323 | 21 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 | |
| ML14129A350 | 29 April 2014 | Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 25, 2014 | Safe Shutdown Shutdown Margin Ultimate heat sink Mission time Stroke time Anticipated operational occurrence Post Accident Monitoring Temporary Modification Emergency Lighting Functionality Assessment B.5.b Operability Determination Time Critical Operator Action Fuel cladding Scaffolding Unidentified leakage Unidentified leak Power Uprate |
| W3F1-2013-0054, CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B | 9 September 2013 | CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B | |
| W3F1-2013-0027, Closure Option for Generic Safety Issue - 191 | 16 May 2013 | Closure Option for Generic Safety Issue - 191 | Boric Acid Coatings Foreign Material Exclusion |
| W3F1-2012-0079, Special Report SR-12-002-00, Containment High Range Radiation Monitor ARMIRE5400 a Inoperable for Greater than 7 Days | 20 September 2012 | Special Report SR-12-002-00, Containment High Range Radiation Monitor ARMIRE5400 a Inoperable for Greater than 7 Days | |
| ML12157A426 | 23 May 2012 | Attachment 38 to GNRO-2012/00039 - Ensr. 2007, Impingement Mortality and Entrainment Characterization Study (Imecs), Entergy -Waterford 3. December 2007 | Zebra Mussel |
| W3F1-2012-0034, Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 25, 2012 | 30 April 2012 | Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 25, 2012 | Boric Acid Stroke time Tornado Missile Time to boil Temporary Modification Cyber Security Emergency Lighting Functionality Assessment Aging Management Tornado Generated Missile Operability Determination Fuel cladding Unidentified leakage Unidentified leak |
| W3F1-2011-0074, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) | 17 November 2011 | License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) | |
| ML101730200 | 17 June 2010 | Chemical Effects Summary Related to RAI Response to GL-2004-02 | Boric Acid |
| ML101270439 | 5 May 2010 | Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants | |
| W3F1-2010-0003, License Amendment Request for Approval of Leak-Before-Break of the Pressurizer Surge Line | 22 February 2010 | License Amendment Request for Approval of Leak-Before-Break of the Pressurizer Surge Line | Safe Shutdown Earthquake Weld Overlay Pressure Boundary Leakage Dissimilar Metal Weld |
| W3F1-2009-0033, Blind Sample Investigation Report | 15 July 2009 | Blind Sample Investigation Report | |
| W3F1-2008-0049, Day Report for Reactor Pressure Vessel Head and Pressurizer Inspection/Repair for the Spring 2008 Refueling Outage | 24 July 2008 | Day Report for Reactor Pressure Vessel Head and Pressurizer Inspection/Repair for the Spring 2008 Refueling Outage | Boric Acid Non-Destructive Examination Weld Overlay |
| W3F1-2007-0030, Day Steam Generator Tube Inspection Report for the 14th Refueling Outage | 21 June 2007 | Day Steam Generator Tube Inspection Report for the 14th Refueling Outage | Nondestructive Examination |
| ML070590205 | 21 February 2007 | Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds | Weld Overlay Finite Element Analysis |
| W3F1-2006-0059, Core Operating Limits Report - Cycle 14 Revision 0 Change 1 | 7 November 2006 | Core Operating Limits Report - Cycle 14 Revision 0 Change 1 | Shutdown Margin Coatings |
| CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee | 13 July 2006 | Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee | Mururoa |
| W3F1-2006-0012, Report of Facility Changes, Tests and Experiments and Commitment Changes | 1 May 2006 | Report of Facility Changes, Tests and Experiments and Commitment Changes | Ultimate heat sink |
| CNRO-2006-00023, Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests | 24 April 2006 | Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests | VT-2 |
| W3F1-2006-0008, Supplement to Amendment Request NPF-38-260 Tubesheet Inspection Depth for Steam Generator Tube Inspections for Waterford, Unit 3 | 22 March 2006 | Supplement to Amendment Request NPF-38-260 Tubesheet Inspection Depth for Steam Generator Tube Inspections for Waterford, Unit 3 | Nondestructive Examination |
| W3F1-2005-0067, Supplemental Startup and Power Report for Cycle 14 Waterford, Unit 3 | 8 December 2005 | Supplemental Startup and Power Report for Cycle 14 Waterford, Unit 3 | Power change Downpower |
| ML061280117 | 1 December 2005 | ER-W3-2000-0334-000, Heating Ventilation and Air Conditioning Equipment Room and Component Cooling Heat Exchanger Room Calculations Correction | |
| ML061280114 | 19 October 2005 | ER-W3-2005-0334-001, Temporary Alteration for Reactor Vessel Gasket Leak-off Pressure High Annunciator | Safe Shutdown Fuel cladding Fire Watch |
| ML061280112 | 14 September 2005 | ER-W3-2005-0378-000, Outside Containment Leak Reduction Program Test Medium Change | Offsite Dose Calculation Manual Fire Protection Program Fire Watch |
| ML061280113 | 14 September 2005 | ER-W3-2005-0396-000, Confirmatory Criticality Calculation Correction for Spent Fuel Racks | Offsite Dose Calculation Manual Fuel cladding Fire Protection Program Fire Watch |
| ML052090158 | 2 August 2005 | 2004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment | Fitness for Duty Enforcement Discretion Probabilistic Risk Assessment Condition Adverse to Quality Significance Determination Process Large early release frequency Systematic Assessment of Licensee Performance Earthquake Maintenance Rule Program Pressure Boundary Leakage Backfit Power change Siren |
| ML061280108 | 6 June 2005 | ER-W3-2004-0276-002, Steam Generator Tube Rupture Impacts Due to Alternate Source Term Methodology with Revised Assumptions | Offsite Dose Calculation Manual Probabilistic Risk Assessment Fire Protection Program Fire Watch |
| ML061280111 | 6 June 2005 | ER-W3-2004-0122-000, Pressurizer Heater Sleeve and Instrument Nozzle Repair |