RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
05000259/LER-1980-047-03, /03L-0:on 800604,during Power Operation,While Testing Drywell Air Sampling Sys,Vacuum Pump Associated W/ RM-1-90-256 Failed.Caused by Normal Wear.Pump Was Replaced
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
B12676, Forwards Response to 870709 Generic Ltr 87-12 Re Loss of RHR While RCS Partially Filled.Description of Circumstances & Conditions Under Which Facilities Would Enter Draindown Process W/Rcs Partially Filled Encl
B17085, Forwards Millstone,Unit 1 Annual Rept for Period Jan-Dec 1997.No Commitments Contained within Ltr
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
BVY-96-144, Forwards 10CFR50.59 Evaluation Re Core Spray & RHR Containment Isolation Valves at Plant
BVY-96-123, Forwards Summary of Evaluation of Intention to Redesignate Several Core Spray & Residual Heat Removal Sys Containment Isolation Valves at Vermont Yankee
BECO-83-214, Submits Addl Info Re Insp of BWR Stainless Steel Piping,Per 830808 Meeting.Issue Will Be Resolved as Expeditiously as Is Consistent W/Public Safety.Related Info Encl
B13169, Proposed Tech Specs,Revising Sections 3.6, Core Cooling Sys, 3.7, Min Water Vol & Boron Concentration in Refueling Water Storage Tank & 4.3, Core Cooling Sys-Periodic Testing, to Combine Into New Section 3.6, Eccs
05000271/LER-1998-007, :on 980318,group III Pci Signal Was Potentially Blocked from Initiating Isolation of Containment Air Monitoring Isolation Valves.Caused by Potential Single Error.Isolated Valves & Entered 7 Day LCO
05000219/LER-1985-007, :on 850320,discovered Outside Floor Drain Sample Tank Used But Not Sampled Since 850313.Caused by Personnel Error & Lack of Procedural Controls.Radwaste & Chemistry Operating Procedures Revised
05000259/LER-1985-001-01, :on 850121,drywell Leakage Rate in Excess of Tech Specs Noted.Caused by Leak in Temporary Hose Used to Test Check Valve & Small Weld Crack Inside Drywell.Crack Repaired.Procedures Revised
05000259/LER-1984-026, :on 840620,unidentified Drywell Leakage Exceeded Tech Spec Coolant Leakage Rate of 5 Gpm.Orderly Shutdown Initiated & Unit Manually Scrammed at 59% Power. Seal Replaced
05000331/LER-1984-013, :on 840413,increase of Unidentified Leakage Into Drywell Observed.Shutdown of Reactor Commenced.Caused by Packing Leak in Recirculation Pump a Discharge Bypass Valve.Valves Repacked & Adjusted
05000331/LER-1983-048-03, /03L-0:on 831230,containment Atmosphere Monitor B (RE-8103B) Declared Inoperable Due to Inadequate Process Line Flow.Caused by Moisture Problems W/Magnehelic Flow Switch.Heat Tracing Rerouted
05000293/LER-1991-007, :on 910429,TS Required Shutdown Completed Due to Drywell Floor Sump Leakage Rate & Subsequent Scram Signal While Shutdown.Seal Cartridges Replaced & Responsible Operator Counseled
05000296/LER-1983-043-03, /03L-0:on 830727,CAM3-90-256 Removed from Svc to Replace Sample Pump.Caused by Sample Pump Nearing End of Normal Svc Life.Sample Pump Replaced
05000296/LER-1982-056-03, /03L-0:on 821128,particulate Channel on 3-90-256 Drywell CAM Went Downscale Due to Moisture in Sample Chamber.Caused by Accumulation of Condensation in Sample Chamber of NMC Model AM-331F CAM.O-rings Replaced
05000278/LER-1990-015-03, :on 901125,operators Failed to Record Drywell Sump Flow Readings Every 4 H Per Tech Spec 3.6.C.Caused by Personnel Error.Timer Will Be Obtained to Alarm Every 4 H to Prompt Operator to Record Drywell Readings
05000281/LER-1982-056-03, /03L-0:on 820907,pressure in Nitrogen Bottle Supplying Emergency Air to PCV-MS-202A & B Discovered Below Limit.Caused by Leaking Nitrogen Bottle Connection. Replacement Bottle Correctly Installed
05000296/LER-1982-061-03, /03L-0:on 821203,drywell Atmosphere CAM RM 3-90-256 Inoperable Due to Moisture Damaged Particulate Detector.Caused by Accumulation of Condensation in Sample Chamber of CAM Due to Leakage Past O-rings
05000260/LER-1982-025-03, /03L-0:on 820719,during Startup,Relay Coil Failed, Resulting in Partial Primary Containment Isolation.Caused by Burned Out Coil Relay,Causing Relay to Fail in Safe Direction for Primary Containment Isolation
05000293/LER-1993-018, :on 930721,planned Shutdown Initiated Due to Unidentified Leakage of 3 Gpm.On 930722,planned Shutdown Became TS Required Shutdown When Insp Revealed Leakage to Be Rc Pressure Boundary Leakage.Leakage Repaired
05000282/LER-1993-008, :on 930624,observed That Valve CV-31740, Instrument Air to Unit 1 Containment Closed Due to Failure of Coil in Solenoid Operated Pilot Valve.Valve Reopened Locally to Restore Instrument Air
NG-93-2104, Application for Amend to License DPR-49,consisting of Request for TS Change (RTS-197A),correcting Errors & Improving Consistency of Rewrite of TS Section 3.6, Primary Sys Boundary
05000306/LER-1993-002-02, :on 930403,containment Isolation Valve Which Controls Reactor Makeup Water to Containment Exceeded Max Time for Closure.On 930413,lockwire & Safety Tag Removed. Caused by Communication Errors.Safety Tag Process Reviewed
05000277/LER-1993-007, :on 930403,discovered That Drywell Atmospheric Radiation Monitor Isolated from Drywell Atmosphere for an Indeterminate Period,Due to Mispositioninig of Purge Valve. Valves Will Be Removed Temporarily
05000333/LER-1981-074-03, /03X-2:on 811010,during Normal Operation,Reactor Water Conductivity Exceeded Tech Specs.Caused by Hot Water in Waste Collector Tank Resulting in Injection of Decomposed Ion Exchange Resin to Reactor Vessel
BECO-90-101, Application for Amend to License DPR-35,changing Tech Specs by Removing cycle-specific Parameter Limits & Relocating to Core Operating Limits Rept
05000309/LER-1983-016-03, /03L-0:on 830504,while Performing ECCS Hot Monthly Surveillance Testing,Safeguards Recirculation Stop Valve SIA-M-54 Failed to Operate.Caused by Mechanical Binding of Valve Stem.Maint Program to Be Upgraded
05000309/LER-1983-017-03, /03L-0:on 830509,830517 & 18,cooling Water Outlet Stop Valve PCC-M-43 to RHR HX Failed to Open from Main Control Board.Caused by Misadjusted Valve Motor Operator Torque Settings
05000333/LER-1981-019-03, /03L-0:on 810210,during Normal Operation,Reactor Water Conductivity Exceeded Tech Spec 3.6.C.4 Limits.Caused by Addition of Caustic to Condensate Storage Tanks Due to Personnel Error.Two Condensate Storage Tanks Cleaned
BECO-89-090, Responds to NRC Verbal Request for Addl Info Re NUREG-0737, Item II.E.4.2(7) Requirement for Automatic Isolation of Containment Purge & Vent Valves.Submittal Provides Summary of Changes Made to Alarm Response Procedures
B13354, Application for Amend to License DPR-21,revising Tech Specs 3.6.c.1.a, Coolant Chemistry & 6.9.1.5, Annual Repts, to Reflect Generic Ltr 85-19
05000265/LER-1980-012-03, /03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor
05000293/LER-1979-043-03, /03L-0:on 791108,drywell Unidentified Leakage Rate Exceeded Tech Specs.Caused by Leakage Passing Inboard Isolation Valve MO-2301-4 on HPCI Sys.Valve Backseated & Leakage Reduced to Less than That Requiring Shutdown
05000254/LER-1979-027-03, /03L-0:on 790921,Tech Specs Exceeded for Water Reactor Conductivity & Chloride Concentration.Caused by Personnel Error.All Personnel Informed of Importance of Knowing Surveillance Limits
05000331/LER-1981-003-03, /03L-0:on 810108,drywell Particulate Radiation Element Re 8101B Found Inoperable.Caused by Sensor Failure Due to Condensation on Particulate Detector.New Radiation Element,Mylar Window & Beta Phosphor Installed
05000331/LER-1981-004-03, /03L-0:on 810111,drywell Particulate Radiation Monitor B Failed Downscale.Caused by Condensate on NMC Model RAK-221F Radiation Element Re 8101B.Design Review Initiated & Particulate & Iodine Filters Examined Daily
BECO-89-042, Responds to 890117 Request for Addl Info Re NUREG-0737,Item II.E.4.2(7), Automatic Isolation of Containment Purge & Vent Valves. Given Multiple & Diverse Alarms of Reactor Coolant Leakage,Adequate Detection of Leak Assured
05000293/LER-2007-001, Regarding Primary Containment Isolations Following a Manual Reactor Scram
05000280/LER-2006-001, Re Voluntary Report - Motor Driven AFW Pump High Flow Condition with Low Steam Generator Pressure
05000271/LER-2003-001, E-mail from M. Sherer of Vermont Yankee to Various, Regarding Station 271 LER 2003-001-00
05000293/LER-2003-006, Re Reactor Coolant Pressure Boundary Leakage Due to Reactor Vessel Nozzle Weld Crack Propagation
05000333/LER-1993-019, :on 930923,potential Design Inadequacies in Control Room Ventilation Sys Occurred.Caused by Inadequate Design Control & Documentation by Engineering Organizations. CRV Placed in Isolate Mode of Operation
05000298/LER-1979-001-03, /03L-0 on 790103:during Operation,Drywell Atmospheric Radiation Monitor Gas Channel (RMV-RM-4C) Failed Downscale.Caused by Detector Failure Caused by Moisture in Detector Chamber.Detector Replaced;Chamber & Lines Dried
05000331/LER-1997-010, :on 970814,alarms Received Indicating Isolation of Drywell Sumps & Shutdown Cooling.Caused by open-circuited Coil.Maint Personnel Replaced Failed Coil,Drywell Floor & Equipment Drain Sys Thereby Reestablished & LCO Exited
05000260/LER-2078-005, For Browns Ferry Nuclear Plant, Unit 2, Unidentified Coolant Leakage in Drywall Was Found to Be 9.5 Gpm & Exceeded 5 Gpm Limit of Technical Specification 3.6.C.1. During Normal Operation
05000259/LER-1985-001-02, :on 850121,unidentified Drywell Leakage Rate in Excess of Tech Spec,Noted.Shutdown Initiated.Caused by Leak in Temporary Hose & Weld Crack Inside Drywell.Repairs Made & Pertinent Procedures Revised