RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
NRC-2009-0354, FRN: General Notice. Notice of Consideration of Amendments to Facility Operating Licenses, Revising Technical Specification 6.4.Q, Steam Generator Program, to Exclude Portions of Tubes within Tubesheet from Periodic SG Inspections
05000280/LER-1987-001, :on 861223,pressurizer PORVs Declared Inoperable Due to Excessive Stroke Time.Caused by Insufficient Air Flow Due to Air Line Size.Air Lines Will Be Replaced W/Larger Tubing
05000282/LER-1987-002-01, :on 870220,normal Shutdown to Cold Shutdown Started Due to Steam Generator primary-to-secondary Leak. Caused by Design Error.Eddy Current Insp Performed,Crevice Flushing W/Boric & Online Boric Acids Added
05000245/LER-1997-017-01, :on 970222,failed to Meet TS 3.1.C, Reactor Protection Sys Power Monitoring. Caused by Personnel Error. Revised OP 344A to Delete Installation of Jumper
05000281/LER-1976-005-01, /01T:on 760915,pressurizer Level Fell 45% Below Level Set Point.Caused by Tube Leak in Steam Generator A. Steam Generator Isolated
05000281/LER-1982-007-03, /03L-0:on 820118,periodic Test 10 Revealed Unidentified Leak Rate Greater than 1 Gallon Per Minute. Caused by Inlet Flange Leak on Relief Valve.Flange Gasket Replaced
05000280/LER-2077-016, Submit Reportable Occurrence No. RO-S1-77-16 Re Unidentified Leakage During Normal Operational Surveillance
05000281/LER-1992-008-03, :on 921215,RCS Leak Identified Near Low Pressure Letdown Flow Transmitter.Caused by Failure of Swagelock Fitting on Flow Transmitter.Root Cause Evaluation in Progress & Fitting & Tube Replaced
05000280/LER-1990-008-01, :on 900727,determined That RCS Leakage Greater than 10 Gpm as Indicated by Level Drop on Vol Control Tank Level Recorder.Caused by Broken Gage Sensing Line in Letdown Sys.Sensing Line Repaired
05000281/LER-1991-005-02, :on 910602,reactor Coolant Sys Leakage Exceeded Tech Spec Limits.Caused by Mechanical Failure of Isolation Valve.Preparation of Design Change Has Been Underway That Will Install RTDs on Main RCS Lines
05000280/LER-1993-010-01, :on 930821,unit 1 Shutdown for Planned Maint to Repair Leakage on B SG Channel Head Caused by Cracking of Weld Associated W/B SG Channel Head Drain Line.Performed RCS Leak Rate
05000280/LER-1993-013-01, :on 931117,Unit 1 Vol Control Tank Level Decreased Unexpectedly During Ion Exchanger Resin Transfer. Caused by Leakage Past Seat of Manual Isolation Valve. Leakage Isolated Promptly
05000280/LER-1995-007, :on 950912,boron Crystals & Corrosion Products Discovered Outside Diameter of Vessel.Caused by through-wall Leakage.Work Request Initiated,Engineering & Shift Supervisor Notified
05000280/LER-1998-006, :on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
05000280/LER-1998-009, :on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
05000280/LER-1987-025, :on 871008,RCS Leakage Rate Test Results of 4.06 Gpm Found in Excess of Tech Specs 3.1.C.2 & 3.1.C.5. Caused by Inadequate Procedure & HX Bypass Valve Leakage. Valve Tightened & Procedure PT-10 Revised
05000280/LER-1987-013-01, :on 870623,unit Shutdown Commenced Due to High RCS Leak Rate.Caused by Failed Packing on Loop Stop Valve MOV-1593.Loop Stop Valves Repacked & Diaphragm on Drain Header Isolation Valve Replaced
PNO-II-89-072, on 891012,plant Shut Down Due to Leakage Past Pressurizer Safety Valve B.Operators Classified Leakage as Unidentified & Entered Tech Spec 3.1.C.2.Three Safety Valves Removed & Shipped to Westinghouse for Repair
NL-02-006, Response to Request for Additional Information Indian Point 2 License Amendment Request for Reactor Coolant System Heatup and Cooldown Limitation Curves
PNO-II-93-037, on 930820,unscheduled Shutdown in Excess of 72 H Occurred Due to Need to Repair Leak in Joint on SG B. RCS Temp Reduced Below 200 Degrees F.Licensee to Inspect Drain Valve Assemblies on Sg.State of VA Notified
05000281/LER-1983-038-03, /03L-0:on 830921,during RCS Integrity Test PT-11, Weld Leak Identified on Steam Generator a Channel Head Drain Piping at 2-RC-159.Cause Not Determined.Weld Completely Ground Out,Rewelded & Tested Satisfactorily