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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

• Howie Crouch  + (Howie Crouch)
• Huan Li  + (Huan Li)
• Huda Akhavannik  + (Huda Akhavannik)
• Huilung Liu  + (Huilung Liu)
• Human Performance, Operator Licensing & ITAAC Branch  + (Human Performance, Operator Licensing & ITAAC Branch)
• 10 CFR 63.322, Human Intrusion Scenario  + (Human intrusion scenario)
• 10 CFR 63.321, Individual Protection Standard for Human Intrusion  + (Human-Intrusion Standard)
• Humboldt Bay  + (Humboldt Bay)
• Hunterston  + (Hunterston)
• 10 CFR 2.1101, Purpose  + (Hybrid Hearing Procedures for Expansion of Spent Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors)
• Hydrogen  + (Hydrogen)
• EPID:L-2019-JLD-0011  + (Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update)
• 10 CFR 71.73, Hypothetical Accident Conditions  + (Hypothetical accident conditions)
• 10 CFR 73 Appendix C, Ii. Nuclear Power Plant Safeguards Contingency Plans  + (Appendix C to Part 73-Nuclear Power Plant Safeguards Contingency Plans)
• 10 CFR 75.8, Iaea Inspections  + (IAEA inspections)
• NRC Generic Letter 80-05, IEB 79-01b Environmental Qualification of Class 1E Equipment  + (IEB 79-01b Environmental Qualification of Class 1E Equipment)
• NRC Generic Letter 80-16, IEB 79-01b Environmental Qualification of Class 1E Equipment  + (IEB 79-01b Environmental Qualification of Class 1E Equipment)
• NRC Generic Letter 80-82, IEB 79-01b Supplement 2 Environmental Qualification of Class 1E Equipment  + (IEB 79-01b Supplement 2 Environmental Qualification of Class 1E Equipment)
• NRC Generic Letter 80-89, IEB 79-01b Supplement 3 Environmental Qualification of Class 1E Equipment  + (IEB 79-01b Supplement 3 Environmental Qualification of Class 1E Equipment)
• NRC Generic Letter 80-04, IEB 80-01 Operability of ADS Valve Pneumatic Supply  + (IEB 80-01 Operability of ADS Valve Pneumatic Supply)
• NRC Generic Letter 80-08, IEB 80-02 Inadequate Quality Assurance for Nuclear Supplied Equipment  + (IEB 80-02 Inadequate Quality Assurance for Nuclear Supplied Equipment)
• NRC Generic Letter 80-11, IEB 80-03 Loss of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells  + (IEB 80-03 Loss of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells)
• NRC Generic Letter 80-12, IEB 80-04 Analysis of a PWR Main Steam Sine Break with Continued Feedwater Addition  + (IEB 80-04 Analysis of a PWR Main Steam Sine Break with Continued Feedwater Addition)
• NRC Generic Letter 80-21, IEB 80-05 Vacuum Condition Resulting in Damage to Chemical Volume Control System Holdup Tanks  + (IEB 80-05 Vacuum Condition Resulting in Damage to Chemical Volume Control System Holdup Tanks)
• NRC Generic Letter 80-25, IEB 80-06 Engineering Safety Feature (ESF) Reset Controls  + (IEB 80-06 Engineering Safety Feature (ESF) Reset Controls)

• NRC Generic Letter 80-27, IEB 80-07 BWR Jet Pump Assembly Failure  + (IEB 80-07 BWR Jet Pump Assembly Failure)

• NRC Generic Letter 80-28, IEB 80-08 Examination of Containment Liner Penetration Welds  + (IEB 80-08 Examination of Containment Liner Penetration Welds)
• NRC Generic Letter 80-31, IEB 80-09 Hydramotor Actuator Deficiencies  + (IEB 80-09 Hydramotor Actuator Deficiencies)
• NRC Generic Letter 80-36, IEB 80-10 Contamination of Non-Radioactive System and Resulting Potential for Unmonitored, Uncontrolled Release to Environment  + (IEB 80-10 Contamination of Non-Radioactive System and Resulting Potential for Unmonitored, Uncontrolled Release to Environment)
• NRC Generic Letter 80-39, IEB 80-11 Masonry Wall Design  + (IEB 80-11 Masonry Wall Design)
• NRC Generic Letter 80-42, IEB 80-12 Decay Heat Removal System Operability  + (IEB 80-12 Decay Heat Removal System Operability)
• NRC Generic Letter 80-43, IEB 80-13 Cracking in Core Spray Spargers  + (IEB 80-13 Cracking in Core Spray Spargers)
• NRC Generic Letter 80-54, IEB 80-14 Degradation of Scram Discharge Volume Capability  + (IEB 80-14 Degradation of Scram Discharge Volume Capability)
• NRC Generic Letter 80-55, IEB 80-15 Possible Loss of Hotline With Loss of Off-Site Power  + (IEB 80-15 Possible Loss of Hotline With Loss of Off-Site Power)
• NRC Generic Letter 80-58, IEB 80-16 Potential Misapplication of Rosemount Inc. Models 1151/1152 Pressure Transmitters with "A" Or "D" Output Codes  + (IEB 80-16 Potential Misapplication of Rosemount Inc. Models 1151/1152 Pressure Transmitters with "A" Or "D" Output Codes)
• NRC Generic Letter 80-63, IEB 80-17 Failure of Control Rods to Insert During a Scram at a BWR  + (IEB 80-17 Failure of Control Rods to Insert During a Scram at a BWR)
• NRC Generic Letter 80-66, IEB 80-17 Supplement 1 Failure of Control Rods to Insert During a Scram at a BWR  + (IEB 80-17 Supplement 1 Failure of Control Rods to Insert During a Scram at a BWR)
• NRC Generic Letter 80-68, IEB 80-17 Supplement 2 Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR  + (IEB 80-17 Supplement 2 Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR)
• NRC Generic Letter 80-79, IEB 80-17 Supplement 3 Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR  + (IEB 80-17 Supplement 3 Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR)
• NRC Generic Letter 80-111, IEB 80-17 Supplement 4, Failure of Control Rods to Insert During a Scram at a BWR  + (IEB 80-17 Supplement 4, Failure of Control Rods to Insert During a Scram at a BWR)
• NRC Generic Letter 80-69, IEB 80-18 Maintenance of Adequate Minimum Flow Through Centrifugal Charging Pumps Following Secondary Side Helb  + (IEB 80-18 Maintenance of Adequate Minimum Flow Through Centrifugal Charging Pumps Following Secondary Side Helb)
• NRC Generic Letter 80-70, IEB 80-19 Failures of Mercury-Wetted Matrix Relays in RPS of Operating Nuclear Power Plants Designed by GE  + (IEB 80-19 Failures of Mercury-Wetted Matrix Relays in RPS of Operating Nuclear Power Plants Designed by GE)
• NRC Generic Letter 80-71, IEB 80-20 Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches  + (IEB 80-20 Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches)
• NRC Generic Letter 80-92, IEB 80-21 Valve Yokes Supplied by Malcolm Foundry Company, Inc.  + (IEB 80-21 Valve Yokes Supplied by Malcolm Foundry Company, Inc.)
• NRC Generic Letter 80-97, IEB 80-23 Failures of Solenoid Valves Manufactured by Valcor Engineering Corporation  + (IEB 80-23 Failures of Solenoid Valves Manufactured by Valcor Engineering Corporation)
• NRC Generic Letter 80-98, IEB 80-24 Prevention of Damage Due to Water Leakage Inside Containment  + (IEB 80-24 Prevention of Damage Due to Water Leakage Inside Containment)
• NRC Generic Letter 80-112, IEB 80-25 Operating Problems with Target Rock Safety Relief Valves  + (IEB 80-25 Operating Problems with Target Rock Safety Relief Valves)
• IEEE-450  + (IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications)
• 10 CFR 73 Appendix C, Ii. Nuclear Power Plant Safeguards Contingency Plans  + (Appendix C to Part 73-Nuclear Power Plant Safeguards Contingency Plans)
• EPID:L-2023-LLR-0063  + (ILT 23-1 (2024-301) Exam Outline Submittal SVP Letter 23-0036)
• 10 CFR 12  + (IMPLEMENTATION OF THE EQUAL ACCESS TO JUSTICE ACT IN AGENCY PROCEEDINGS)