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- Information Notice 2013-10, Programs for Monitoring Boiling-Water Reactor Steam Dryer Integrity +
- Information Notice 2012-10, Recent Issues Associated With Submittal Of NRC Form 396, Certification Of Medical Examination By Facility Licensee, For Applicants And Licensed Operators At Non-Power Reactors +
- Information Notice 2011-10, Thermal Issues Identified During Loading of Spent Fuel Storage Casks +
- Information Notice 2010-10, Implementation of a Digital Control System Under 10 CFR 50.59 +
- Information Notice 2008-10, Response to Indications of Potential Tampering, Vandalism, or Malicious Mischief +
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) +
- Information Notice 2007-10, Yttritium-90 TheraSpheres and SirSpheres Impurities +
- Information Notice 2006-10, Use of Concentration Control For Criticality Safety +
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 +
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. +
- Information Notice 2004-10, Loose Parts in Steam Generators +
- Information Notice 1999-10, Degradation of Prestressing Tendon Systems in Prestresssed Concrete Containments +
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments +
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988) +
- Information Notice 2007-10, Yttritium-90 Theraspheres and Sirspheres Impurities +
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments +
- Information Notice 1991-10, Summary of Semiannual Program Performance Reports on Fithess-For-Duty (FFD) in the Nuclear Industry +
- Information Notice 1985-10, Posttensioned Containment Tendon Anchor Head Failure +
- Information Notice 1989-10, Undetected Installation Errors in Main Steam Line Pipe Tunnel Differential Temperature-Sensing Elements at Boiling Water Reactors +
- Information Notice 1980-10, Partial Loss of Non-Nuclear Instrument System Power Supply During Operation +
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps +
- Information Notice 1993-10, Dose Calibrator Quality Control +
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key +
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation +
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances +
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments +
- Information Notice 1998-10, Probable Misadministrations Occurring During Intravascular Brachytherapy with Novoste Beta-cath System +
- Information Notice 2001-10, Failure of Central Sprinkler Companys Model Gb Series Fire Sprinkler Heads +
- Information Notice 2000-10, Recent Events Resulting in Extremity Exposures Exceeding Regulatory Limits +
- Information Notice 2012-10, Recent Issues Associated with Submittal of NRC Form 396, Certification of Medical Examination by Facility Licensee, for Applicants and Licensed Operators at Non-Power Reactors +
- Information Notice 2006-10, Use of Concentration Control for Criticality Safety +
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances +
- Information Notice 2018-10, Thermal Sleeve Flange Wear Leads to Stuck Control Rod at Foreign Nuclear Plant +
- Information Notice 2008-10, Response to Indications of Potential Tampering Vandalism or Malicious Mischief +
- Information Notice 1988-10, Memorandum of Understanding Between NRC and Osha Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988. +
- Information Notice 1986-10, Feedwater Line Break +
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 +
- Information Notice 2014-10, Unfused DC Ammeter Circuits and Potential for Fire Events +
- Information Notice 2002-10, Manual Reactor Trip and Steam Generator Water Level Setpoint Uncertainties +
- Information Notice 2019-10, Failures Reported in Eaton/Cutler Hammer A200 and Freedom Series Contactors +
- Information Notice 2009-10, Transformer Failures - Recent Operating Experience +
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion +
- Information Notice 2005-10, Changes to 10 CFR Part 71 Packages +
- Information Notice 2003-10, Criticality Monitoring System Degradation at Bwx Technologies, Inc., Nuclear Products Division Lynchburg, VA +