ML18275A234: Difference between revisions
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Revision as of 13:32, 5 February 2019
| ML18275A234 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/27/2018 |
| From: | Wilson G A Division of Materials and License Renewal |
| To: | Entergy Operations |
| Clark P, NRR-DMLR 415-6447 | |
| References | |
| Download: ML18275A234 (13) | |
Similar Documents at Waterford | |
|---|---|
Category:Report
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[Table view]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 Category:Miscellaneous MONTHYEARW3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024
[Table view]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 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 ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1392021-03-22022 March 2021 Strategy 1 ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy 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 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 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) 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 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 W3F1-2012-0079, Special Report SR-12-002-00, Containment High Range Radiation Monitor ARMIRE5400 a Inoperable for Greater than 7 Days2012-09-20020 September 2012 Special Report SR-12-002-00, Containment High Range Radiation Monitor ARMIRE5400 a Inoperable for Greater than 7 Days ML12157A4262012-05-23023 May 2012 Attachment 38 to GNRO-2012/00039 - Ensr. 2007, Impingement Mortality and Entrainment Characterization Study (Imecs), Entergy -Waterford 3. December 2007 W3F1-2012-0034, Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 25, 20122012-04-30030 April 2012 Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 25, 2012 W3F1-2011-0074, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2011-11-17017 November 2011 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) ML1017302002010-06-17017 June 2010 Chemical Effects Summary Related to RAI Response to GL-2004-02 ML1012704392010-05-0505 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 Line2010-02-22022 February 2010 License Amendment Request for Approval of Leak-Before-Break of the Pressurizer Surge Line W3F1-2009-0033, Blind Sample Investigation Report2009-07-15015 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 Outage2008-07-24024 July 2008 Day Report for Reactor Pressure Vessel Head and Pressurizer Inspection/Repair for the Spring 2008 Refueling Outage W3F1-2007-0030, Day Steam Generator Tube Inspection Report for the 14th Refueling Outage2007-06-21021 June 2007 Day Steam Generator Tube Inspection Report for the 14th Refueling Outage ML0705902052007-02-21021 February 2007 Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds W3F1-2006-0059, Core Operating Limits Report - Cycle 14 Revision 0 Change 12006-11-0707 November 2006 Core Operating Limits Report - Cycle 14 Revision 0 Change 1 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 Yankee2006-07-13013 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 W3F1-2006-0012, Report of Facility Changes, Tests and Experiments and Commitment Changes2006-05-0101 May 2006 Report of Facility Changes, Tests and Experiments and Commitment Changes CNRO-2006-00023, Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests2006-04-24024 April 2006 Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests W3F1-2006-0008, Supplement to Amendment Request NPF-38-260 Tubesheet Inspection Depth for Steam Generator Tube Inspections for Waterford, Unit 32006-03-22022 March 2006 Supplement to Amendment Request NPF-38-260 Tubesheet Inspection Depth for Steam Generator Tube Inspections for Waterford, Unit 3 W3F1-2005-0067, Supplemental Startup and Power Report for Cycle 14 Waterford, Unit 32005-12-0808 December 2005 Supplemental Startup and Power Report for Cycle 14 Waterford, Unit 3 ML0612801172005-12-0101 December 2005 ER-W3-2000-0334-000, Heating Ventilation and Air Conditioning Equipment Room and Component Cooling Heat Exchanger Room Calculations Correction ML0612801142005-10-19019 October 2005 ER-W3-2005-0334-001, Temporary Alteration for Reactor Vessel Gasket Leak-off Pressure High Annunciator ML0612801122005-09-14014 September 2005 ER-W3-2005-0378-000, Outside Containment Leak Reduction Program Test Medium Change ML0612801132005-09-14014 September 2005 ER-W3-2005-0396-000, Confirmatory Criticality Calculation Correction for Spent Fuel Racks ML0520901582005-08-0202 August 2005 2004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment 2024-06-17 |
Text
Code of Federal RegulationsFederal Register Federal Register Protection of EnvironmentCode of Federal Regulations
Federal Register
- i. No-Action Alternative ii. Alternative Energy Sources New Nuclear Alternative Supercritical Pulverized-Coal Alternative Natural Gas Combined-Cycle Alternative Combination Alternative (Natural Gas Combined Cycle, Biomass, and Demand-Side Management)
Summary
Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel Endangered Species Act (ESA) Section 7 ConsultationAcipenser oxyrinchusdesotoiScaphirhynchus albusTrichechusmanatus
/RA Joseph E. Donoghue for/
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