RETAQS, Inc.

 

             

General

bullet 10-CFR Code of Federal Regulations -- Energy
bullet Index of All NRC Generic Communications

Bulletins

bullet BL73005  Manufacturing Defects in Boiling Water Reactor Control Rods
bullet BL73006  Inadvertent Criticality in a Boiling Water Reactor
bullet BL78014  Deterioration of Buna-N Components in ASCO Solenoids
bullet BL79026  Boron Loss from BWR Control Blades
bullet BL79026R1  Boron Loss from BWR Control Blades
bullet BL80007  BWR Jet Pump Assembly Failure
bullet BL80017  Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR
bullet BL8007S1  BWR Jet Pump Assembly Failure
bullet BL8017S1  Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR
bullet BL8017S2  Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR
bullet BL8017S3  Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR
bullet BL8017S4  Failure of Control Rods to Insert During a Scram at a BWR
bullet BL8017S5  Failure of Control Rods to Insert During a Scram at a BWR
bullet BL88007  Power Oscillations in Boiling Water Reactors (BWRs)
bullet BL8807S1  Power Oscillations in Boiling Water Reactors (BWRs)
bullet BL96001  Control Rod Insertion Problems
bullet BL96002  MOVEMENT OF HEAVY LOADS OVER SPENT FUEL, OVER FUEL IN THE REACTOR CORE, OR OVER SAFETY-RELATED EQUIPMENT

Circulars

bullet CR77007  Short Period During Reactor Startup
bullet CR77012  Dropped Fuel Assemblies at BWR Facilities
bullet CR79007  Unexpected Speed Increase of Reactor Recirculation MG Set Resulted in Reactor Power Increase
bullet CR80002  Nuclear Power Plant Staff Work Hours

Generic Letters

bullet GL79058  ECCS Calculations On Fuel Cladding
bullet GL80003  BWR Control Rod Failures
bullet GL80063  IEB 80-17 Failure Of Control Rods To Insert During A Scram At A BWR
bullet GL80066  IEB 80-17 Supplement 1 Failure Of Control Rods To Insert During A Scram At A BWR
bullet GL80067  Scram Discharge Volume
bullet GL80068  IEB 80-17 Supplement 2 Failures Revealed By Testing Subsequent To Failure Of Control Rods To Insert During A Scram At A BWR
bullet GL80079  IEB 80-17 Supplement 3 Failures Revealed By Testing Subsequent To Failure Of Control Rods To Insert During A Scram At A BWR
bullet GL80084  BWR Scram System
bullet GL80107  BWR Scram Discharge System
bullet GL81009  BWR Scram Discharge System
bullet GL81018  BWR Scram Discharge System-Clarification of Diverse Instrumentation Requirements
bullet GL81020  Safety Concerns Associated With Pipe Breaks in The BWR Scram System
bullet GL81024  Multi-Plant Issue B-56 Control Rods Fail To Fully Insert
bullet GL81030  Safety Concerns Associated With Pipe Breaks in the BWR Scram System
bullet GL81034  Safety Concerns Associated With Pipe Breaks in the BWR Scram System
bullet GL81035  Safety Concerns Associated With Pipe Breaks in the BWR Scram System
bullet GL82003  High Burnup MAPLHGR Limits
bullet GL82012  Nuclear Power Plant Staff Working Hours
bullet GL86002  Technical Resolution of Generic Issue B-19 -Thermal Hydraulic Stability
bullet GL86003  Applications For License Amendments
bullet GL86004  Policy Statement On Engineering Expertise On Shift
bullet GL88011  NRC Position on Radiation Embrittlement Of Reactor Vessel Materials And Its Impact On Plant Operations
bullet GL94002  Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs
bullet GL94003  Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors
bullet GL96004  BORAFLEX DEGRADATION IN SPENT FUEL POOL STORAGE RACKS
bullet GL97001  Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations
bullet GL99001 NRC Generic Letter 99-01: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities

Information Notices

bullet IN80001 Fuel Handling Events
bullet IN80002 8X8R Water Rod Lower End Plug Wear
bullet IN80004 BWR Fuel Exposure in Excess of Limits
bullet IN80030 Potential for Unacceptable Interaction between Control Rod Drive Scram...and Non-Essential Control Air at GE BWRs
bullet IN80045 Potential Failure of BWR Backup Manual Scram Capability
bullet IN81011 Alternate Rod Insertion for BWR Scram Represents a Potential Path for Loss of Primary Coolant
bullet IN81012 Guidance on Order Issued January 9, 1981 Regarding Automatic Control Rod Insertion on Low Control Air Pressure
bullet IN81016 Control Rod Drive System Malfunctions
bullet IN81023 Fuel Assembly Damaged Due to Improper Positioning of Handling Equipment
bullet IN82027 Fuel Rod Degradation Resulting from Baffle Water-Jet Impingement
bullet IN83029 Fuel Binding Caused by Fuel Rack Deformation
bullet IN83075 Improper Control Rod Manipulation
bullet IN84021 Inadequate Shutdown Margin
bullet IN84079 Failure to Properly Install Steam Separator at Vermont Yankee
bullet IN85012 Recent Fuel Handling Events
bullet IN85014 Failure of Heavy Control Rod (B4C) Drive Assembly to Insert a Trip Signal
bullet IN86058 Dropped Fuel Assembly
bullet IN86068 Stuck Control Rod
bullet IN86075 Incorrect Maintenance Procedure on Traversing Incore Probe Lines
bullet IN86089 Uncontrolled Rod Withdrawal Because of a Single Failure
bullet IN86109 Diaphragm Failure in Scram Outlet Valve Causing Rod Insertion
bullet IN86110 Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants
bullet IN87056 Improper Hydraulic Control Unit Installation at BWR Plants
bullet IN88021 Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear Power Plants
bullet IN88034 Nuclear Material Control and Accountability of Non-Fuel Special Nuclear Material at Power Reactors
bullet IN88039 LaSalle Unit 2 Loss of Recirculation Pumps with Power Oscillation Event
bullet IN89009 Credit for Control Rods Without Scram Capability in the Calculation of the Shutdown Margin
bullet IN89024 Nuclear Criticality Safety
bullet IN89031 Swelling and Cracking of Hafnium Control Rods
bullet IN90063 Management Attention to the Establishment and Maintenance of a Nuclear Criticality Safety Program
bullet IN90077 Inadvertent Removal of Fuel Assemblies From the Reactor Core
bullet IN90078 Previously Unidentified Release Path From Boiling Water Reactor Control Rod Hydraulic Units
bullet IN9077S1  Inadvertent Removal of Fuel Assemblies From the Reactor Core
bullet IN91036 Nuclear Plant Staff Working Hours
bullet IN92021 Spent Fuel Pool Reactivity Calculations
bullet IN92039 Unplanned Return to Criticality During Reactor Shutdown
bullet IN92074 Power Oscillations at Washington Nuclear Power Unit 2
bullet IN9221S1 Spent Fuel Pool Reactivity Calculations
bullet IN93070 Degradation of Boraflex Neutron Absorber Coupons
bullet IN93077 Human Errors That Result in Inadvertent Transfers of Special Nuclear Material at Fuel Cycle Facilities
bullet IN93079 Core Shroud Cracking at Beltline Region Welds in Boiling-Water Reactors
bullet IN93082 Recent Fuel and Core Performance Problems in Operating Reactors
bullet IN93101 Jet Pump Hold-Down Beam Failure
bullet IN94013 Unanticipated & Unintended Movement - Fuel Assemblies & Other Components Due - Improper Operation of Refueling Equipment
bullet IN94042 Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors
bullet IN94064 Reactivity Insertion Transient and Accident Limits for High Burnup Fuel
bullet IN9413S1 Unanticipated & Unintended Movement - Fuel Assemblies & Other Components Due - Improper Operation of Refueling Equipment
bullet IN9442S1 Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors
bullet IN9464S1 Reactivity Insertion Transient and Accident Limits For High Burnup Fuel
bullet IN95008 Inaccurate Data Obtained With Clamp-on Ultrasonic Flow Measurement Instruments
bullet IN95016 Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor
bullet IN95017 Reactor Vessel Top Guide and Core Plate Cracking
bullet IN95038 Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks
bullet IN95051 Recent Incidents Involving Potential Loss of Control of Licensed Material
bullet IN95056 Shielding Deficiency in Spent Fuel Transfer Canal at a Boiling-Water Reactor
bullet IN95057 Risk Impact Study Regarding Maintenance During Low-Power Operation and Shutdown
bullet IN96007 SLOW FIVE PERCENT SCRAM INSERTION TIMES CAUSED BY VITON DIAPHRAGMS IN SCRAM SOLENOID PILOT VALVES
bullet IN96012 Control Rod Insertion Problems
bullet IN96016 BWR Operation With Indicated Flow Less Than Natural Circulation
bullet IN96017 Reactor Operation Inconsistent With the Updated Final Safety Analysis Report
bullet IN96025 Traversing In-Core Probe Over withdrawn at LaSalle County Station, Unit 1
bullet IN96039 ESTIMATES OF DECAY HEAT USING ANS 5.1 DECAY HEAT STANDARD MAY VARY SIGNIFICANTLY
bullet IN96041 EFFECTS OF A DECREASE IN FEEDWATER TEMPERATURE ON NUCLEAR INSTRUMENTATION
bullet IN96069 OPERATOR ACTIONS AFFECTING REACTIVITY
bullet IN97002 CRACKS FOUND IN JET PUMP RISER ASSEMBLY ELBOWS AT BOILING WATER REACTORS
bullet IN97013 Assessment of Spent Fuel Pool Cooling
bullet IN97015 Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors And Compliance With 10 CFR 50.46a(3)
bullet IN97017 Cracking of Vertical Welds in The Core Shroud and Degraded Repair
bullet IN97030 Control of Licensed Material During Reorganizations, Employee-Management Disagreements, And Financial Crises
bullet IN97039  Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations
bullet IN97042  Management Weaknesses Resulting in Failure to Comply With Shipping Requirements for Special Nuclear Material
bullet IN97051 Problems Experienced Loading and Unloading Spent Nuclear Fuel Storage and Transportation Casks
bullet IN97062 Unrecognized Reactivity Addition During Plant Shutdown
bullet IN97077 Exemptions From the Requirements of Section 70.24 of Title 10 of The Code of Federal Regulations
bullet IN97085 Effects of Crud Buildup and Boron Deposition on Power Distribution and Shutdown Margin
bullet IN98029 NRC Information Notice 98-29: Predicted Increase in Fuel Rod Cladding Oxidation
bullet IN99031 Operational Controls to Guard Against Inadvertent Nuclear Criticality
bullet IN00001 Operational Issues Identified in Boiling Water Reactor Trip and Transient
 

 

 

   
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Last modified on March 21, 2007