BVY 15-037, Submittal of 2014 Radioactive Effluent Release Report
BVY 13-096, Technical Specifications Proposed Change No. 307 Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition Vermont Yankee Nuclear Power Station
BVY 12-035, 2011 Radioactive Effluent Release Report
BVY 18-020, Submittal of 2017 Radioactive Effluent Release Report
BVY 10-030, Radioactive Effluent Release Report
BVY 09-037, Vermont Yankee - 2008 Radioactive Effluent Release Report
BVY 07-037, Annual 2006 Radioactive Effluent Release Report
BVY 06-046, Annual 2005 Radioactive Effluent Release Report
05000263/LER-1979-015-03, /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell
05000263/LER-1979-013-03, /03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced
05000263/LER-1979-012-03, /03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced
05000263/LER-1980-013-01, /01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling
05000263/LER-1980-020-03, /03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake
IA-89-143, Responds to Request Re Recent Foreign Experience.Review of Several Data Bases Conducted.No Failures of Reactor Coolant Pump Impellers or Water Bearing Rings Due to Faulty Welds Found.Related Info Encl
FVY-81-172, Responds to NRC Re Violations Noted in IE Insp Rept 50-271/81-15.Corrective Actions:Misaligned Valves Positioned & Procedure OP 4117 Will Be Revised by 820101 to Insure Correct Valve Lineup for Standby Gas Treatment Train
BVY 14-038, Vermont Yankee Nuclear Power Station - 2013 Radioactive Effluent Release Report
05000282/LER-1979-009-01, /01T-0 on 790412:notified by Vendor That Small Break in Pressurizer Indicator Lp May Hang Up While Pp Decreases,Delaying Safety Injection.Westinghouse Recommends Manually Initiating Safety Injection Implements
05000306/LER-1983-017-03, /03L-0:on 830712,during Surveillance Test, Containment Air Sample Inlet Isolation Valve CV-31642 Failed to Fully Close on Demand.Caused by Inaccuracy in Maintaining Hard Valve Seats
05000306/LER-1983-024-03, /03L-0:on 831004 & 08,steam Flow Transmitter Failed Low.Cause Unknown.Transmitter Returned to Normal During Troubleshooting.Unit Replaced W/Rosemount Model 1153HD6 Transmitter
05000306/LER-1983-025-03, /03L-0:on 831011,containment Air Sample Inlet Isolation Valve CV-31642 Failed to Fully Close,Per Tech Spec 3.6.A.6.Caused by Loose Set Screw in Switch Actuator Arm & Poor Contact W/Valve Switch.Screw Tightened
05000263/LER-1983-011-03, /03L-0:on 830519,discovered Steam Leak on Reducer at Moisture Separator Drain D Valve CV-3134 to Heater 14B. Caused by Erosion of Carbon Steel Reducers by Steam at 380 F & 195 Psi.Stainless Steel Reducers Installed
05000282/LER-1983-028-03, /03L-0:on 831031,during Review of Surveillance Program,One Monthly Surveillance Test Found Not Performed According to Tech Spec 4.0.Caused by Personnel Failure to Update Schedule During Unit 2 Refueling
05000306/LER-1983-006-03, /03L-0:on 830408,during Surveillance Test,Relay for motor-driven Auxiliary Feedwater Pump 21 on lo-lo Level in Steam Generator 21 Failed.Caused by Relay Coil Failure. Coil Replaced
05000263/LER-1978-001-01, /01T-0:on 780105,nonconconforming Bolts Found in Radwaste Shipping Cask.Caused by Cask Supplier Error.Cask Handling Procedure Will Be Revised to Include Verification of Proper Bolt Size
05000263/LER-1978-011-01, /01T-0:on 780606,four of Six APRM Scram Trip Settings Three to Four Percent Low.Aprm Calibr at 50% Power. Gain Settings Corrected
05000263/LER-1978-004-03, /03L-0:on 780421,during Surveillance Test RWCU Outboard Isolation Valve MO-2398 Failed to Close First Time Switch Placed in Close Position.Cause Unknown
05000263/LER-1978-010-03, /03L-0:on 780605,CRD 06-19 Delayed for Indefinite Period of Time.Caused by Buna N Disc in Scram Pilot Solenoid Plunger Broken in Several Pieces.Plunger Including Disc Replaced
05000263/LER-1978-008-03, /03L-0:on 780525,inlet Air Heater Operating at Reduced Capacity Due to Fuse Failure.Fuse Block & Fuses Replaced in Kind
05000263/LER-1978-014-01, /01T-0:on 780728,CRD 30-47 Delayed Approx 1.4 Before Scramming.Disc in Scram Pilot Valve Solenoid Plunger Broken Into Several Pieces,Wedging & Preventing Valve from Venting Air on Scram Valves
05000263/LER-1978-009-03, /03L-0:on 780525,trip of Essential MCC B33A Supply Breaker 52-304 Resulted in Operation in Degraded Mode Permitted by Various Lco.Cause Unknown.Evaluation Continuing
05000306/LER-1983-014-01, /01T-0:on 830613,containment Inservice Purge Supply Isolation Failed Local Leakage Rate Test.Caused by Dirty Valve Seats.Valve Seats Cleaned.Blind Flanges to Be Installed During Next Outage
05000263/LER-1983-026-03, /03L-0:on 831205,outboard Steam Isolation Valve MO-2076 Failed to Close.Caused by Loose Screw Bumping Lead, Causing Torque Switch in Limitorque Valve to Fail Open. Switch Replaced
05000282/LER-1983-032-03, /03L-0:on 831121,discovered Monthly Station Battery Test SP1096-1 Not Completed as Scheduled.Caused by Temporary Change in Responsibilities Leading to Personnel Error.Schedule Changed
05000282/LER-1983-030-03, /03L-0:on 831104,control Room Annunciator on Diesel Cooling Water Pump 22 Actuated Due to False Signal in Cable Control.Cause Unknown.Investigation Ongoing.Ground Removed from Control Cable Shield
05000263/LER-1983-021-03, /03L-0:on 831019,calibr of Safeguards Bus Degraded Voltage Relays Performed 8 Days Beyond Allowable Schedule Deviation.Caused by Scheduling Error.Personnel Instructed & Schedule Form Revised
05000306/LER-1983-026-03, /03L-0:on 831021,sodium Hydroxide Concentration of 11.5% in Spray Additive Tank Exceeded Tech Spec Limit of 11%.Caused by Inadequate Mixing for Design Change.Tank Refilled.Solution Diluted & Recirculated
05000263/LER-1983-023-03, /03L-0:on 831026,flow Through Train B Standby Gas Treatment Less than Tech Spec Requirement.Caused by Stack Exhaust Flow Incorrectly Adjusted.Stack Flow Corrected
05000263/LER-1983-022-01, /01T-0:on 831024,reactor Recirculation Motor Generator Set Drive Breaker Trip Coil Failed.Cause Unknown. Component Replaced
05000282/LER-1983-021-03, /03L-0:on 830830,during Surveillance Test MV-32035,cooling Water Header Isolation Valve B Failed to Close.Caused by Failure of GE Auxiliary Switch,Part CR105X100P.Switch Replaced
05000282/LER-1983-018-03, /03L-0:on 830719,device Controlling Screen & Bypass Gate Operation in Intake Screenhouse Malfunctioned, Causing Restricted Intake Flow of Condenser Circulating & Cooling Water.Detailed Rept to Follow
05000263/LER-1983-018-03, /03L-0:on 830718,RHR Pump 11 Declared Inoperable Following Failure of Min Flow Valve CV1994 to Open as Required Due to Flow Switch Failure.Caused by Microswitch Contact Wear Due to flow-induced Vibration
05000306/LER-1983-022-03, /03L-0:on 830909,steam Flow Transmitter Found Out of Calibr Low by 1%.Cause Unknown.Transmitter Returned to Vendor for Analysis.Rosemount Model 1153HA6 Differential Pressure Transmitter Replaced
05000306/LER-1983-016-03, /03L-0:on 830627,during Power Operation, Containment Vacuum Breaker Isolation Valve CV-31628 Failed to Close on Demand.Caused by Diaphragm Failure in Quick Exhaust Valve.Valve Replaced
05000263/LER-1983-010-03, /03L-0:on 830226,during Surveillance Testing, Outboard MSIV,AO-2-86B Closed Faster than Value Stated in Tech Spec Table 3.7.1.Caused by Oil Leak from Needle Valve Assembly on Bottom Dashpot Cylinder Head
05000282/LER-1983-010-03, /03L-0:on 830417,reactor Coolant Sample Found Missing After Load Changing Operations for Turbine Testing. Sample Taken 2 H Late.Caused by Lack of Communication.Load Changing Procedure Will Be Revised
05000306/LER-1983-009-03, /03L-0:on 830416,spike Occurred in RCS Activity Up to 3.26 Uci/Gm Dose Equivalent I-131.Caused by Washout of Fission Products from Fuel Pin Defects Following Reactor Shutdown & RCS Cooldown & Depressurization
05000263/LER-1982-004-01, /01T-0:on 820410,ASCO Inboard & Outboard Drywell Vent 3-way Solenoid Valves,Model 830064C64U,failed to Close Upon Hand Switch Activation When Coil de-energized.Probably Caused by Horizontally Mounted Solenoids.Valves Replace
05000263/LER-1983-015-01, /01T-0:on 830613,investigation of 250-volt Dc Battery Fault Revealed Grounded HPCI Woodward Governor EDR Hydraulic Actuator Coil.Caused by out-of-spec Nonhomogeneous Lube Oil.Lube Oil Replaced
BVY 17-004, Technical Specifications Proposed Change No. 313: Revision to License and Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool
BVY 14-038, Radioactive Effluent Release Report for 2013 Including Annual Radiological Impact on Man
05000263/LER-1979-021-03, /03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts
05000263/LER-1980-021-03, /03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced
05000263/LER-1979-014-03, /03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired
05000263/LER-1979-010-01, /01T-0 on 790426:informed by General Motors of Potential Diesel Generator Turbocharger Problem.Caused by Inadequate Design of Lube Oil Sys.Mod Being Developed
05000263/LER-1980-011-01, /01T-0:on 800306,during Refueling Outage,Repairs to Outboard MSIV Stop Valve Revealed Flow Path Between Secondary Containment & Turbine Bldg When MSIV Poppet Was Pulled.Caused by Lack of Preventive Procedure Controls
05000263/LER-1979-011-03, /03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line
05000263/LER-1980-023-03, /03L-0:on 800601,air Ejector Offgas Radiation Monitors Dropped to About 20% Normal for About 40 Minutes. Caused by Mechanical Vacuum Pump Offgas Sample Valve Being Incorrectly Opened.Valve Now Wired Shut
05000263/LER-1980-007-01, /01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors
05000263/LER-1979-016-03, /03L-0 on 790731:turbine Tripped on Low Oil Pressure.Caused by Clogged Lube Oil Filter.Sys Drained, Inspected & Flushed
05000263/LER-1980-006-03, /03L-0:on 800226,during Refueling Outage,Seven of Main Steam Line Area Temp Switches Found to Trip Above Required Level.Caused by Setpoint Drift.Switches Recalibr
05000263/LER-1979-009-03, /03L-0 on 790404:steam Leak Found in 90 Degree Elbow in 1-inch Core Isolation Cooling Steam Supply Drain Pot Condenser Line.Caused by Erosion Due to High Velocity Steam from Leaking Valve.Hole Patched.Repairs Planned
05000263/LER-1980-017-01, /01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified
05000263/LER-1979-019-03, /03L-0:on 790923,ECCS Yarway Level Switches Indicated Falsely High Level & Would Not Have Tripped within Specified Settings.Caused by Effects of Leak Which Developed in Reactor Pressure Gauge During Normal Operation
05000263/LER-1979-022-03, /03L-0:on 791213,during Normal Operation,Leak Discovered in 90-degree Elbow on 1-inch Condensate Line from Steam Supply to Recombiner Train Drain Trap.Caused by Erosion from Hot Steam Drains.Elbow Modified
05000263/LER-1979-023, Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review
05000263/LER-1979-005-03, /03L-0 on 790315:results of Special Test of Safety Relief Valve Effects on Torus Indicated Possible Excessive Opening Delay Time.Caused by Improper Installation of Insulation on Valve 67F.Maint Procedure to Modified
05000263/LER-1979-017-03, /03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage
05000263/LER-1980-018-03, /03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure
05000263/LER-1979-007-03, /03L-0 on 790318:valve Operability & Motor Current Check Signed Despite Current Outside Formula Spec.Caused by Misaligned Torque Switch.New Components Ordered
05000263/LER-1979-006-01, /01T-0 on 790317:during Recirculator Motor Generator Shutdown,Associated Field Breaker Failed to Trip. Caused by Metal Bead Fused to Arc Chute.Bead Removed,Breaker Tested & Returned to Svc
05000263/LER-1979-020-03, /03L-0:on 791030,reactor Core Isolation Cooling Isolation Temp Switch Found to Trip Above Allowable Setpoint.Caused by Setpoint Drift.Switch Replaced
05000263/LER-1978-016-03, /03X-1 on 780908:during Normal Operation,Trip of Essential MCC B33A Supply Breaker 52-304 Resulted in Operation in Degraded Mode.Caused by Low Setpoint on Trip Device & by Loss of Dash Pot Oil in Trip Device
05000263/LER-1979-001-03, /03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569
05000263/LER-1979-004-01, /01T-0 on 790313:shipping Cask Model B-2 Found W/ Two Missing Lid Bolt Nuts,Missing Inner Lid Gasket & Damaged Outer Lid Gasket.Caused by Inadequate Insp & Maint by Supplier.Cask Returned Empty
05000263/LER-1979-003-01, /01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled
05000263/LER-1978-022-03, /03L-0 on 781117:steam Leak Was Discovered in a 1 Wye Strainer,YS-4002,on the Main Steam Equalizer Drain Line. Leak Caused by a Defective Casting & Dev After Two Days of Svc
05000263/LER-1979-002-03, /03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error
05000263/LER-1978-021-03, /03L-0 on 781114:during Refueling Outage While Testing RHR SW Sys,A Pinhole Leak Was Discovered in CV-1729, RHR SW Differential Pressure Control Valve.Caused by Corrosion & Erosion of Upper Valve Body
05000263/LER-1978-028-03, /03L-0 on 781124:during Normal Oper,Small Steam Leak Was Discovered in Weld of 45 Degree Elbow on HPCI Steam Supply Line 1 Inch Drain Line to Main Condenser Due to Corrrosion.Weld Repair Made at Leak.Awaiting Parts
05000263/LER-1979-008-01, /01T-0 on 790323:one Trip Output Relay Failed to Initiate Trip in No 12 Recirculation Motor Generator Set Field Breaker Trip Logic.Caused by Contact Which Was Disengaged from Socket.Contact re-engaged in Socket
05000263/LER-1980-015-01, /01T-0:on 800317,during Refueling Outage & Insp Required by IE Bulletin 79-01B,unqualified Splices Found in Power Cables for Inboard MSIV Solenoid Valves.Cause Not Stated.Splices Replaced W/Qualified Matls
BVY 08-029, 2007 Radioactive Effluent Release Report
BVY 16-020, Transmittal of 2015 Radioactive Effluent Release Report
05000263/LER-1980-016-01, /01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements
05000263/LER-1983-012, /O3L-0:on 830519,mode Switch Scram Bypass Annunciator Came on Following Energization of Reactor Protection Logic.Caused by Relay Race.Relays Manually Actuated to Return to Normal Condition
05000263/LER-1983-014-01, /01T-0:on 830601,HPCI Isolated on High Steam Flow. Caused by Leakage of Inboard Injection Gate Valve,Causing Void in HPCI Injection Line.Procedure Changed to Operate W/Outboard Injection Valve Closed
05000263/LER-1983-019-01, /01T-0: on 830801,air Operated Reactor Bldg to Torus Vacuum Breaker AO-2380 Found Leaking in Excess of Tech Specs.Cause Unknown.Valve Placed on Accelerated Surveillance Program
05000263/LER-1983-013-03, /03L-0:on 830519,inboard MSIV AO-2-80D Closed Faster than Value Stated in Tech Spec Table 3.7.1.Caused by Leakage of Oil from Control Valve Housing to Body Threaded Connection.Housing Tightened
05000306/LER-1983-020-03, /03L-0:on 830829,maint Air Lock Door Exhibited Leakage of 21,000 Sccm Exceeding Tech Spec Limit.Caused by Deterioration of Grafoil Packing at Inboard Shaft Seals. Packing Will Be Replaced Prior to Startup
05000263/LER-1979-024-03, /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld