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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML17326A288 +
- ML20012F599 +
- ML18094A756 +
- ML19347F144 +
- ML20050W947 +
- ML20050B745 +
- ML20054F427 +
- L-04-079, May 2004 Monthly Operating Report for Beaver Valley Power Station +
- ML20078G038 +
- ML20073P126 +
- ML20093J565 +
- ML20091A936 +
- ML20129D790 +
- ML20151U300 +
- ML20066D147 +
- ML20212Q277 +
- ML20245A231 +
- ML20247H599 +
- IR 05000271/1985099 +
- B12009, Forwards Addl Info Re 851206 Proposed Tech Spec Change Allowing Sleeving of Steam Generator Tubes as Repair Option, in Response to 860221 Request.Special Local Ventilation in Steam Generator Repair Area Provided +
- BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with +
- A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event +
- 05000254/LER-1989-004-07, :on 890417,reactor Manually Scrammed Due to Electromagnetic Relief Valve 1-203-3D Being Stuck Open. Caused by Steam Leakage Past Pilot Valve & Obstruction of Drain Orifice.Relief & Pilot Valves Replaced +
- 05000254/LER-1986-031-02, :on 861108,diesel Generator auto-started After Incorrect Electrical Test Switch Opened During Maint.Caused by Poorly Labeled Electrical Drawings.Change Requests Submitted to Properly Identify Equipment +
- 05000324/LER-1987-004-02, :on 870311,reactor Scram on Low Level Due to Loss of Uninteruptible Power Supply & Subsequent Loss of Feedwater.Caused by Noncompliance W/Procedure to Transfer Power.Motor Replaced & Sys Returned to Normal +
- 05000261/LER-1986-009-01, :on 860322,during Escalation in Power,Level in Steam Generator B Began to Swell,Resulting in Turbine Trip on hi-hi Level & Subsequent Reactor Trip.Caused by Transmitter Sensing Line Problems +
- 05000331/LER-1986-017, :on 860613,at Approx 5% Power,Manual Scram Initiated When Reactor Water Level Approached Low Level Scram Setpoint.Caused by Faulty Position Controllers. Positioners Replaced & Cleaned +
- 05000498/LER-1988-009, :on 880123,unanticipated Safety Injection Signal Occurred from Solid State Protection Sys Actuation Train A.Caused by Inadequate Surveillance Procedure.Train a & B Master Relay Test Procedures Revised +
- 05000382/LER-1997-006, :on 970221,discovered Void at Penetration 39 During Ultrasonic Testing of Lpsi.Caused by TS 4.5.2j Not Being Completed post-maint.Invoked TS Requirement Surveillance 4.0.3 to Complete TS 4.5.2j +
- 05000267/LER-1986-003, :on 860113,circulator C Tripped on high-buffer, mid-buffer Differential Pressure.Caused by Water Entering Circulator C Buffer Sense Lines.Sense Lines Blown Down W/ Clean Helium +
- 05000289/LER-1986-002, :on 860104,anticipatory Reactor Trip from Turbine Trip Occurred During Power Escalation.Caused by High Moisture Separator Level.Failed Controller Replaced & Power Escalation Recommenced +
- 05000293/LER-1992-005, :on 920403,actuation of CSCS Logic Circuitry Occurred While Shut Down.Caused by Procedure Deficiency. Procedure Tp 92-020,Rev 0 Retired & Replaced by Procedure Tp 92-022,Rev 0 +
- 05000373/LER-1994-014, :on 941123,HP Core Spray Pump Unexpectedly Made Inoperable.Caused by Mgt Deficiency in That Clear Intruction Were Not Provided & Scope of OOS Not Properly Identified. Addl Training Will Be Provided to Operators +
- 05000395/LER-1983-087-03, /03L-0:on 830803,diesel Generator a Failed Diesel Generator Operability Surveillance Test.Caused by Dirty Contacts on Maint Local/Remote Selector Switch. Contacts Cleaned +
- 05000461/LER-1991-002, :on 910218,loss of Svc & Instrument Air Occurred Resulting in Manual Scram Insertion.Caused by Personnel Error.Surge Suppression Switch on Compressor Recalibrated +
- 05000278/LER-1993-004-03, :on 930730,simulated Low Steam Flow Signal to Recombiner Initiated Isolation Signal to Off Gas Recombiner, Causing Main Condenser Vacuum to Begin Decreasing.Special Procedure SP-1438 Revised +
- 05000311/LER-1990-021, :on 900515,radiation Monitoring Sys Channel 2R12A Failed Resulting in ESF Signal Actuation for Containment Purge/Pressure Vacuum Relief Sys Isolation. Caused by Equipment/Design Concerns +
- 05000311/LER-1981-119-03, /03L-0:on 811111-28,quadrant Power Tilt Ratio Calculations (QPTR) Determined at 1.03 & Channel N-43 Declared Inoperable.Caused by Malfunctions in Power Range Channel N-43 Nuclear Instrumentation +
- 05000311/LER-1981-119, Forwards LER 81-119/03L-0.Detailed Event Analysis Encl +
- 05000498/LER-1991-004, :on 910215,loss of Offsite Power Actuation Occurred During Routine Maint.Caused by Lack of Attention to Work Performance Methods.Training Conducted for Maintenance Personnel +
- 05000254/LER-1980-020-03, /03L-0:on 800831,during Electromatic Relief Valve Operability Surveillance Qos 201-1,electromatic Relief Valve 1-203-3B Failed to Close.Caused by Steam Cutting of Pilot Valve Allowing Steam to Leak Out Exhaust Port +
- 05000400/LER-1990-005-01, :on 900307,engineered Safety Sys Feature Actuation Occurred Due to Radiation Monitor Spike.Caused by Loose Pin Connection in Coaxial Cable Connector.Maint Surveillance Test Revised +
- 05000316/LER-1993-004, :on 930408,rod Position Indication for Rods H-12 & M-8 Found Indicating Greater than 12 Steps from Demand Position Indication.Caused by Transformer Sensitivity to Temp Changes.Position Verified +
- 05000397/LER-1992-037, :on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures +
- CNL-16-177, Mitigating Strategies Assessment for Flooding - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 +
- 05000315/LER-2003-003, From Cook, Unit 1 Regarding Dual Unit Manual Trip Due to Failure of Intake Traveling Screens & Failure to Comply with TS 3.8.1.1 +
- ML20136E548 +
- 05000397/LER-1990-025, :on 901023,HPCS Sys Declared Inoperable.Caused by Equipment Failure.Plant Policy Reviewed,Design Differential Pressure Calculation Process Revised & Thrust Calculation HPCS-V-23 Revised +