W3F1-2014-0067, Technical Specification Index and Bases Update to the NRC for the Period June 30, 2013 Through November 3, 2014
W3F1-2010-0087, Additional Responses to NRC Requests for Additional Information Regarding License Amendment Request for Leak-Before-Break of the Pressurizer Surge Line
W3F1-2010-0083, Supplemental Response to NRC Requests for Additional Information Regarding License Amendment Request for Leak-Before-Break of the Pressurizer Surge Line
W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition
W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program
W3F1-2008-0039, Steam Generator Conditions Observed at Waterford 3
W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007
W3F1-2007-0011, Response to Request for Additional Information on NRC Bulletin 2004-01 Regarding Alloy 600 Pressurizer Penetration Inspections
W3F1-2006-0070, Entergy Actions to Address RF14 Batwing Failures
W3F1-2006-0052, License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation, Waterford Steam Electric Station, Unit 3
W3F1-2006-0029, Revision to Amendment Request NPF-38-262 Steam Generator Tube Inservice Inspection Program
W3F1-2006-0016, To Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
W3F1-2006-0008, Supplement to Amendment Request NPF-38-260 Tubesheet Inspection Depth for Steam Generator Tube Inspections for Waterford, Unit 3
W3F1-2006-0005, License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation
W3F1-2006-0007, Supplement to Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
W3F1-2018-0065, Request for Relief from ASME Section XI Volumetric Examination Requirements - Third 10-Year Interval, W3-ISI-032
W3F1-2019-0054, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1
W3F1-2019-0052, CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2)
W3F1-2005-0040, License Amendment Request NPF-38-262 Proposed Technical Specification Change to Steam Generator Tube Inservice Inspection Program Using Consolidated Line Item Improvement Process
W3F1-2004-0090, Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/04
W3F1-2004-0060, Supplement to License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
W3F1-2004-0028, License Amendment Request NPF-38-254, Reactor Coolant System Leakage Detection
05000361/LER-1982-137, Forwards LER 82-137/03L-0.Detailed Event Analysis Submitted
PNO-V-86-009, on 860227,unusual Event Declared When Small Leak from Pressurizer Instrument Top Weld Discovered. Borating Began to Achieve Necessary Shutdown Margin.Cooldown & Leak Repair Planned
CNRO-2007-00002, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds
W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program
W3F1-2019-0056, Revision to Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1
05000382/LER-2023-002, Plant Shutdown Required by Technical Specifications for Unidentified Reactor Coolant System Leakage in Containment
05000029/LER-1989-012, :on 890825,leak Found in Weld Attaching Vent Line to Loop Bypass Line.Caused by Fatigue.Lab Evaluation Will Be Conducted to Confirm Results of Initial Evaluation
05000529/LER-1986-041-01, :on 860701,unidentified Leakage Greater than 1 Gpm Detected in Rcs.Caused by Seal Leakage Due to Strainer Flushing Techniques Previously Employed.Flushing Procedure Modified
05000382/LER-1999-002-03, :on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired
05000362/LER-1986-003-01, :on 860227,observed Small RCS Pressure Boundary Leak in 3/4-inch Instrument Nozzle on Head of Pressurizer. Cause Undetermined.Nozzle & Weld Completely Cut Out & Replaced
05000382/LER-1988-015, :on 880613,plant Shutdown Required Due to Leakage Past Reactor Coolant Loop Drain Valves.Caused by Inadequate Hand Closing One of Drain Valves.Valves Will Be Evaluated & Corrective Action Recommended
05000382/LER-1985-013, :on 850404,feedwater Pump B Tripped on Low Suction Pressure.Caused by Broken Yoke.Flow Orifice Added to Recirculation Line in Order to Limit Condensate Bypass Flow to Condenser
05000382/LER-1992-002-01, :on 920325,unusual Event Declared Due to RCS Unidentified Leakage in Excess of TS Limit of 1 Gallon Per Minute.Caused by Failed Packing Gland Studs Due to Boric Acid Corrosion.Valve RC-104 Will Be Repaired
05000382/LER-1992-006-01, :on 920711,unidentified RCS Leakage Greater than TS 3.4.5.2 Limit of 1 Gpm Discovered.Caused by Failure of Temporary Leak Repair to Hot Leg Sample Valve.Valve Closed & Repaired by Sealant Injection
05000382/LER-1991-008, :on 910517,unusual Event Declared Due to RCS Leakage from Pressurizer Spray Check Valve Being in Excess of TS Requirements.Caused by Underdeveloped Training on Pressure Seal Valve Installation
05000362/LER-1983-081-03, /03L-0:on 831012,RCS Water Inventory Balance Not Completed within Required Surveillance Interval.Caused by Operation Supervisor Not Properly Rescheduling Inventory. Inventory Balance Completed
05000362/LER-1983-071-03, /03L-0:on 830929,unusual Event Declared After Unidentified Leakage of 1.19 Gpm Detected in Rcs.Caused by Minor Leakage Past Either Chemical & Vol Control Sys Letdown Valve PSV-9206 or PSV-9207
05000382/LER-1991-008-01, :on 910517,reactor Coolant Sys Leakage Occurred in Excess of Tech Spec Requirements.Caused by Undeveloped Training on Pressure Seal Valve Installation.Submit Training Request to Train All Mechanical Personnel
05000029/LER-1990-007, :on 900927,incore Instrumentation Spire Failure Resulted in Pressure Boundary Leakage
05000382/LER-1994-006, :on 940415,determined That on 921103, Unidentified RCS Leak Rate of Greater than 1 Gpm Occurred. Caused by Error in RCS Mass Balance Equation.Approved Temporary Change to Procedure OP-903-024
05000528/LER-1998-007, :on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced
05000529/LER-1993-001-03, :on 930314,reactor Manually Tripped Following Steam Generator Tube Rupture.Investigation Team Formed & Investigation Initiated Per Incident Investigation Program. Results Will Be Provided in Supplemental LER
05000529/LER-1988-014-01, :on 881116,reactor Trip Occurred as Result of Low Steam Generator Water Level.Caused by Inadequate Feedwater Flow Due to Leakage of Packing.Procedural Changes Implemented & Evaluation Being Performed
05000528/LER-1992-001, :on 920102,pressure Boundary Leak Led to Cold Shutdown Per TS 3.4.5.2.Caused by Crack in Prz Steam Space Instrument Nozzle.Pad Weld Made to Stop Leak & 7 Inconel 600 Nozzles to Be Replaced at Next Outage
W3F1-2011-0040, License Amendment Request, Technical Specification Change Regarding Steam Generator Tube Integrity
W3F1-2006-0035, To Amendment Request NPF-38-260 Tubesheet Inspection Depth for Steam Generator Tube Inspections
W3F1-2006-0030, To Amendment Request NPF-38-260 Tubesheet Inspection Depth for Steam Generator Tube Inspections
05000529/LER-1993-001, :on 930314,SG Tube Ruptured in SG 2.Caused by Iga/Isgcc Occurring as Result of Tube to Tube Crevice Formation.Implemented Changes to EOP
05000528/LER-1985-042, :on 850711,identified RCS Leak Rate of 1.28 Gpm,Exceeding 1.0 Gpm Limit.Plant Shut Down Per Tech Spec 3.4.5.2.b.Caused by Miscalculation of Leak Rate Due to Procedural Deficiency.Procedure Improved