Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ML21272A3381 April 2021Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report
ML20258A07111 September 201911 to Final Safety Analysis Report, Chapter 01 - Introduction and General Description of Plant - Redacted
ML20255A21825 July 201810 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (EPID L-2020-LLA-0164) - Redacted
W3F1-2018-0031, Supplemental Information Supporting the License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components13 June 2018Supplemental Information Supporting the License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across the Steam Generator Secondary Side Internal Components
ML17045A1483 March 2017Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML16256A13225 August 2016Revision 309 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant, Appendix 1A
ML16256A18425 August 2016Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.7, Figures 3.7-1 Through 3.7-36
ML16256A17025 August 2016Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems, Table of Contents
ML16256A31925 August 2016Revision 309 to Final Safety Analysis Report, Chapter 7, Instrumentation and Controls, Section 7.4
ML16256A44525 August 2016Revision 309 to Final Safety Analysis Report, Chapter 9, Auxiliary Systems, Section 9.1
ML16256A12125 August 2016Revision 309 to Final Safety Analysis Report, Table of Contents
W3F1-2016-0024, Request for Alternative to 10 CFR 50.55a(c), Reactor Coolant Pressure Boundary ASME Section III Code Case 1361-1 Relief Request W3-ISI-02419 May 2016Request for Alternative to 10 CFR 50.55a(c), Reactor Coolant Pressure Boundary ASME Section III Code Case 1361-1 Relief Request W3-ISI-024
W3F1-2016-0001, Completion of Required Action by NRC Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation18 January 2016Completion of Required Action by NRC Order EA-12-051, Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation
W3F1-2014-0023, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Wa27 March 2014Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Waterfor
ML13120A46225 March 2013Engineering Report WF3-CS-12-00003, Attachment G, Rev. 0, Peer Review Checklist for SWEL, Enclosure to W3F1-2013-0024, Pages 820 - 1014 of 1014
IR 05000382/20110083 May 2012IR 05000382-11-008 and 07200075-11-001, on 07/25/2011 - 11/08/2011, Entergy Operations, Inc., Waterford Steam Electric Station, Unit 3, NRC Independent Spent Fuel Storage Installation (ISFSI)
ML08014031828 January 2008Staff Audit Report on Results of Corrective Actions to Address GSI-191 GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at PWRs
ML03076062012 March 2003Amendment, Design Basis Change Regarding Realignment of Refueling Water Storage Pool (Rwsp) Boundary Isolation Valves to Rwsp Purification System
ML20204H12322 March 1999Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping
ML20199D16918 September 1997Rev 19 to QA Program Manual
ML20199F14531 May 1997Rept of Facility Changes,Tests & Experiments Per 10CFR50.59 for Period 951201-970531
ML20137G20227 March 1997Application for Amend to License NPF-38,increasing SFP Storage Capacity & Increasing Maximum Fuel Enrichment from 4.9 W/O to 5.0 W/O U-235.Proprietary & Nonproprietary Repts HI-971628 Encl.Proprietary Rept Withheld
ML20134L61113 February 1997Submits Response to NRC Request for Addl Info Re ISI Relief Request ISI-017,Rev 1
ML20112D4293 June 1996Requests Approval to Delete Code Required Surface Exam on Reactor Pressure Vessel Support Integral Attachment Welds. Timely Review of Encl Relief Request Requested to Allow for Appropriate Planning of Refuel 8 ISI Activities
ML20108D39130 November 1995Rept of Facility Changes,Tests & Experiments Per 10CFR50.59 June 1994 - Nov 1995
ML20078C1137 October 1994QA Program Manual Updates from Period 921216-941007
IR 05000382/198901714 July 1989Insp Rept 50-382/89-17 on 890601-30.Violations Noted.Major Areas Inspected:Onsite Followup of Events,Monthly Maint Observation,Monthly Surveillance Observation & Operational Safety Verification
ML20114D14731 August 1987Package Consisting of Chapters 9 & 11 to Facility USARs
ML20099F37321 November 1984Submits Revised Responses,Supplementing Issues 6,7,19 & 20 & Assessment of Collective Significance.Rev to Issue 6 Provided Per Jm Cain to DG Eisenhut.Remaining Revs Reflect Info Developed Since First Submittal
W3P84-2971, Final Rept of Significant Const Deficiency 117 Re Limitorque Limit Switch & Motor Space Heaters Not Qualified to IEEE-323 & 344 Criteria.Space Heaters Disconnected from Class 1E Power Supply31 October 1984Final Rept of Significant Const Deficiency 117 Re Limitorque Limit Switch & Motor Space Heaters Not Qualified to IEEE-323 & 344 Criteria.Space Heaters Disconnected from Class 1E Power Supply
W3P84-2963, Final Rept,Rev 1,on Significant Const Deficiency 84 Re Tube Track Welding.Reevaluation Performed by Ebasco Engineering to Establish Max Stress Levels Expected to Exist at Tube Track Welded Connections26 October 1984Final Rept,Rev 1,on Significant Const Deficiency 84 Re Tube Track Welding.Reevaluation Performed by Ebasco Engineering to Establish Max Stress Levels Expected to Exist at Tube Track Welded Connections
ML20094N4662 August 1984First Interim Deficiency Rept 114 Re Possible Damage to safety-related Equipment Due to Water Hammers.Questionable or Damaged Seismic Restraints Reworked.Final Rept Will Be Submitted by 840831
ML20091J15828 May 1984Final Significant Const Deficiency Rept 102 Re Failure to Install Dowels & Shear Blocks on Emergency Feedwater Pumps, Motors,Turbine & Emergency Diesel Generators.Installation of Required Items Complete
ML20090H18012 October 1983Analysis of Cracks & Water Seepage in Foundation Mat
ML20040B81418 January 1982Final Rept of Significant Const Deficiency 30 Re Selection of Fastener Matl for Motor Control Ctr & Switchgear Bus Connections Resulting in Overtorquing of Fasteners.Repairs Completed on 811218 Per Ebasco Nonconformance Rept W 3-2750
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BTopic::Design-20basis-20earthquake-5D-5D-20-5B-5BSite::Waterford-5D-5D/-3FIssue-20date/-3FTitle/mainlabel%3D/order%3Ddescending/sort%3Dissue-20date/offset%3D0/format%3Dtable/searchlabel%3DWaterford"