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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
- NRC Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes + (Reporting Requirements on Primary Coolant Iodine Spikes)
- 10 CFR 26.169, Reporting Results + (Reporting Results)
- 10 CFR 50.75, Reporting and Recordkeeping for Decommissioning Planning + (Reporting and recordkeeping for decommissioning planning)
- 10 CFR 15.26 + (Reporting claims)
- 29 CFR 1904.39, Reporting fatalities, hospitalizations, amputations, and losses of an eye as a result of work-related incidents to OSHA + (Reporting fatalities, hospitalizations, amputations, and losses of an eye as a result of work-related incidents to OSHA)
- 10 CFR 26.139, Reporting Initial Validity and Drug Test Results + (Reporting initial validity and drug test results)
- NRC Generic Letter 91-03, Reporting of Safeguards Events + (Reporting of Safeguards Events)
- NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability + (Reporting of Safeguards Events)
- 10 CFR 37.57, Reporting of Events + (Reporting of events)
- 10 CFR 37.81, Reporting of Events + (Reporting of events)
- 10 CFR 73.71, Reporting of Safeguards Events + (Reporting of safeguards events)
- 10 CFR 40.60, Reporting Requirements + (Records, Reports, and Inspections)
- 10 CFR 70.50, Reporting Requirements + (Special Nuclear Material Control Records, Reports, and Inspections)
- 10 CFR 72.75, Reporting Requirements for Specific Events and Conditions + (Reporting requirements for specific events and conditions)
- 10 CFR 20.2201 + (Reports)
- 10 CFR 4.341, Reports + (Reports)
- 10 CFR 35.3045, Report and Notification of a Medical Event + (Reports)
- 10 CFR 36.83, Reports + (Reports)
- 10 CFR 40.64, Reports + (Reports)
- 10 CFR 71.95, Reports + (Reports)
- 10 CFR 75.31, General Requirements + (Reports)
- 10 CFR 95.57, Reports + (Reports)
- 10 CFR 140.6, Reports + (Reports)
- 10 CFR 76.120, Reporting Requirements + (Reports and Inspections)
- 10 CFR 70.52, Reports of Accidental Criticality + (Reports of accidental criticality)
- 10 CFR 72.74, Reports of Accidental Criticality Or Loss of Special Nuclear Material + (Reports of accidental criticality or loss of special nuclear material)
- 10 CFR 60.73, Reports of Deficiencies + (Reports of deficiencies)
- 10 CFR 63.73, Reports of Deficiencies + (Reports of deficiencies)
- 10 CFR 20.2203 + (Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits)
- 10 CFR 20.2206 + (Reports of individual monitoring)
- 10 CFR 74.11, Reports of Loss Or Theft Or Attempted Theft Or Unauthorized Production of Special Nuclear Material + (General Reporting and Recordkeeping Requirements)
- 10 CFR 20.2204 + (Reports of planned special exposures)
- 10 CFR 20.2207 + (Reports of transactions involving nationally tracked sources)
- 10 CFR 7.17, Reports Required for Advisory Committees + (Reports required for advisory committees)
- 10 CFR 20.2205 + (Reports to individuals of exceeding dose limits)
- 10 CFR 60.65, Representation + (Representation)
- 10 CFR 63.65, Representation + (Representation)
- 10 CFR 72.206, Representation + (Representation)
- 10 CFR 63.332, Representative Volume + (Representative volume)
- 10 CFR 55.59, Requalification + (Requalification)
- EPID:L-2019-LLR-0013 + (Request Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (Request 2-TYP-4-RV-05, Revision 0))
- NRC Generic Letter 78-03, Request For Information On Cavity Annulus Seal Ring + (Request For Information On Cavity Annulus Seal Ring)
- NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) + (Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f))
- NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells + (Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells)
- EPID:L-2018-LLA-0270 + (Request for Additional Information License Amendment Request 18-04 Csa)
- EPID:L2020 + (Request for Additional Information Regarding Steam Generator Tube Inspection Reports (EPIDs L2020-LRO-0055, L-2020-LRO-0082, and L2020-LRO-0083))
- EPID:L-2017-TOP-0067 + (Request for Additional Information Regarding Topical Report ANP-10346P, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA)
- EPID:L-2023-LRO-0058 + (Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports)
- EPID:L-2018-LLA-0139 + (Request for Additional Information for License Amendment Request for Global Nuclear Fuel-Americas (Enterprise Project Identification L-2018-LLA-0139))
- EPID:L-2017-TOP-0064 + (Request for Additional Information for Westinghouse Electric Company Topical Report WCAP-16260-P/WCAP-16260-NP, Revision 2, the Spatially Corrected Inverse Count Rate Method for Subcritical Reactivity Measurement)
- NRC Generic Letter 80-15, Request for Additional Management and Technical Resources Information + (Request for Additional Management and Technical Resources Information)
- EPID:L-2021-LLA-0204 + (Request for Alternate Disposal Approval and Exemption for Specific Columbia Fuel Fabrication Waste)