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Information Notices - 1994

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Document Number Title Revision Publish Date Reviewed Date
IN-94-90 Transient Resulting in a Reactor Trip and Multiple Safety Injection System Actuations at Salem -- 12/30/1994 --
IN-94-89 Equipment Failures at Irradiator Facilities -- 12/28/1994 --
IN-94-88 Inservice Inspection Deficiencies Result in Severely Degraded Steam Generator Tubes -- 12/23/1994 A 12/23/1994 B --
IN-94-87 Unanticipated Crack in a Particular Heat of Alloy 600 Used for Westinghouse Mechanical Plugs for Steam Generator Tubes -- 12/22/1994 --
IN-94-86 Legal Actions Against Thermal Science, Inc., Manufacturer of Thermo-Lag S1 11/15/1995 --
-- 12/22/1994 --
IN-94-85 Problems with the Latching Mechanism in Potter and Brumfield R-10-E3286-2 Relays -- 12/21/1994 --
IN-94-84 Air Entrainment in Terry Turbine Lubricating Oil System -- 12/04/1994 --
IN-94-83 Reactor Trip Followed by Unexpected Events -- 12/06/1994 --
IN-94-82 Concerns Regarding Essential Chiller Reliability During Periods of Low Cooling Water Temperature -- 12/05/1994 --
IN-94-81 Accuracy of Bioassay and Environmental Sampling Results -- 11/25/1994 --
IN-94-80 Inadequate DC Ground Detection in Direct Current Distribution System -- 11/25/1994 --
IN-94-79 Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping -- 11/23/1994 --
IN-94-78 Electrical Component Failure Due to Degradation of Polyvinyl Chloride Wire Insulation -- 11/21/1994 --
IN-94-77 Malfunction in Main Generator Voltage Regulator Causing Overvoltage at Safety-related Electrical Equipment -- 11/17/1994 --
IN-94-76 Recent Failures of Charging/safety Injection Pumps -- 10/26/1994 --
IN-94-75 Minimum Temperature for Criticality -- 10/14/1994 --
IN-94-74 Facility Management Responsibilities for Purchased or Contracted Services for Radiation Therapy Programs -- 10/13/1994 --
IN-94-73 Clarification of Criticality Reporting Criteria -- 10/12/1994 --
IN-94-72 Increased Control Rod Drop Time From Crud Buildup -- 10/05/1994 --
IN-94-71 Degradation of Scram Solenoid Pilot Valve Pressure and Exhaust Diaphragms -- 10/04/1994 --
IN-94-70 Issues Associated with Use of Strontium-90 and Other Beta Emitting Radiopharmaceuticals -- 09/29/1994 --
IN-94-69 Potential Inadequacies in the Prediction of Torque Requirements for and Torque Output of Motor- Operated Butterfly Valves -- 09/28/1994 --
IN-94-68 Safety-Related Equipment Failures Caused by Faulted Indicating Lamps -- 09/27/1994 --
IN-94-67 Problems with Henry Pratt Motor-Operated Butter- Fly Valves -- 09/26/1994 --
IN-94-66 Overspeed of Turbine-Driven Pumps Caused by Governor Valve Stem Binding S1 06/16/1995 --
-- 09/19/1994 --
IN-94-65 Potential Error in Manual Brachytherapy Dose Calculations Generated Using a Computerized Treatment Planning System -- 09/12/1994 --
IN-94-64 Reactivity Insertion Transient and Accident Limits for High Burnup Fuel S1 04/06/1995 --
-- 08/31/1994 --
IN-94-63 Boric Acid Corrosion of Charging Pump Casing Caused by Cladding Cracks. -- 08/30/1994 --
IN-94-62 Operational Experience on Steam Generator Tube Leaks and Tube Ruptures -- 08/30/1994 --
IN-94-61 Corrosion of William Powell Gate Valve Disc Holders S1 05/25/1995 --
-- 08/25/1994 --
IN-94-60 Potential Overpressurization of Main Stream System -- 08/24/1994 --
IN-94-59 Accelerated Dealloying of Cast Aluminum-Bronze Valves Caused by Microbiologically Induced Corrosion -- 08/17/1994 --
IN-94-58 Reactor Coolant Pump Lube Oil Fire -- 08/16/1994 --
IN-94-57 Debris in Containment and the Residual Heat Removal System -- 08/12/1994 --
IN-94-56 Inaccuracy of Safety Valve Set Pressure Determination Using Assist Devices -- 08/11/1994 --
IN-94-55 Problems with Copes-Vulcan Power-Operated Relief Valves -- 08/04/1994 --
IN-94-54 Failures of General Electric Magne-Blast Circuit Breakers to Latch Closed -- 08/01/1994 --
IN-94-53 Hydrogen Gas Burn Inside Pressurizer During Welding -- 07/18/1994 --
IN-94-52 Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 -- 07/15/1994 --
IN-94-51 Inappropriate Greasing of Double Shielded Motor Bearings -- 07/15/1994 --
IN-94-50 Failure of General Electric Contactors to Pull in at the Required Voltage -- 07/14/1994 --
IN-94-49 Failure of Torque Switch Roll Pins -- 07/06/1994 --
IN-94-48 Snubber Lubricant Degradation in High-Temperature Environments -- 06/30/1994 --
IN-94-47 Accuracy of Information Provided to NRC During the Licensing Process -- 06/21/1994 --
IN-94-46 Nonconservative Reactor Coolant System Leakage Calculation -- 06/20/1994 --
IN-94-45 Potential Common-Mode Failure Mechanism for Large Vertical Pumps -- 06/17/1994 --
IN-94-44 Main Steam Isolation Valve Failure To Close On Demand Because Of Inadequate Maintenance and Testing -- 06/16/1994 --
IN-94-43 Determination of Primary-to-Secondary Steam Generator Leak Rate -- 06/10/1994 --
IN-94-42 Cracking in the Lower Region of the Core Shroud in Boiling-water Reactors -- 06/07/1994 --
IN-94-41 Problems with General Electric Type CR124 Overload Relay Ambient Compensation -- 06/07/1994 --
IN-94-40 Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood Unit 2 S1 12/15/1994 --
-- 05/26/1994 --
IN-94-39 Identified Problems in Gamma Stereotactic Radiosurgery -- 05/31/1994 --
IN-94-38 Results of a Special NRC Inspection at Dresden ... Unit 1 Following a Rupture of Service Water Inside Containment -- 05/27/1994 --
IN-94-37 Misadministration Caused By a Bent Interstitial Needle During Brachytherapy Procedure -- 05/27/1994 --
IN-94-36 Undetected Accumulation of Gas in Reactor Coolant System -- 05/24/1994 --
IN-94-35 NIOSH Respirator User Notices, "Inadvertent Separation of the MMR From the Facepiece of MSA Company MMR SCBA and Status" -- 05/16/1994 --
IN-94-34 Thermo-Lag 330-660 Flexi-Blanket Ampacity Derating Concerns -- 05/13/1994 --
IN-94-33 Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems -- 05/09/1994 --
IN-94-32 Revised Seismic Hazard Estimates -- 04/29/1994 --
IN-94-31 Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles -- 04/14/1994 --
IN-94-30 Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station S1 08/19/1994 --
-- 04/12/1994 --
IN-94-29 Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure -- 04/11/1994 --
IN-94-28 Potential Problems with Fire-Barrier Penetration Seals -- 04/05/1994 --
IN-94-27 Facility Operating Concerns Resulting From Local Area Flooding -- 03/31/1994 --
IN-94-26 Personnel Hazards and Other Problems From Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor -- 03/28/1994 --
IN-94-25 Failure of Containment Spray Header Valve to Open Due to Excessive Pressure From Inertial Effects of Water -- 03/25/1994 --
IN-94-24 Inadequate Maintenance of Uninterruptable Power Supplies and Inverters -- 03/24/1994 --
IN-94-23 Guidance to hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program -- 03/25/1994 --
IN-94-22 Fire Endurance and Ampacity Derating Test Results for 3-hour Fire-Rated Thermo-Lag 330-1 Fire Barriers -- 03/16/1994 --
IN-94-21 Regulatory Requirements When No Operations Are Being Performed -- 03/18/1994 --
IN-94-20 Common-Cause Failures Due to Inadequate Design Control and Dedication -- 03/17/1994 --
IN-94-19 Emergency Diesel Generator Vulnerability to Failure From Cold Fuel Oil -- 03/16/1994 --
IN-94-18 Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) -- 03/16/1994 --
IN-94-17 Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use -- 03/11/1994 --
IN-94-16 Recent Incidents Resulting in Offsite Contamination -- 03/03/1994 --
IN-94-15 Radiation Exposures During an Event Involving a Fixed Nuclear Gauge -- 03/02/1994 --
IN-94-14 Failure to Implement Requirements for Biennial Medical Examinations and Notification to NRC of Changes in Medical Condition of Licensed Operators S1 04/14/1997 --
-- 02/24/1994 --
IN-94-13 Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment S2 11/28/1994 --
S1 06/28/1994 --
-- 02/22/1994 --
IN-94-12 Insights Gained From Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment -- 02/09/1994 --
IN-94-11 Turbine Overspeed and Reactor Cooldown During Shutdown Evolution -- 02/08/1994 --
IN-94-10 Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key -- 02/04/1994 --
IN-94-09 Release of Patients with Residual Radioactivity From Medical Treatment and Control Areas ... Revised 10 CFR Part 20 -- 02/03/1994 --
IN-94-08 Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve -- 02/01/1994 --
IN-94-07 Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 -- 01/28/1994 --
IN-94-06 Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves -- 01/28/1994 --
IN-94-05 Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves -- 01/19/1994 --
IN-94-04 Digital Integrated Circuit Sockets with Intermittent Contact -- 01/14/1994 --
IN-94-03 Deficiencies Identified During Service Water System Operational Performance Inspections -- 01/11/1994 --
IN-94-02 Inoperability of General Electric Magne-blast -- 01/07/1994 --
IN-94-01 Turbine Blade Failure Caused by Torsional Excitation from Electrical System Disturbance -- 01/07/1994 --

Page Last Reviewed/Updated Thursday, November 2, 2023