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List of results
- ML20215A859 + (Pressurized MELT Ejection Into Scaled Reactor Cavities)
- ML20029C127 + (Pressurized MELT Ejection Into Water Pools)
- ND-19-0356, Pressurized Thermal Shock (PTS) Evaluation + (Pressurized Thermal Shock (PTS) Evaluation)
- ML20140A671 + (Pressurized Thermal Shock Evaluation Per 10CFR50.61 for Reactor Vessels in Byron & Braidwood Units 1 & 2)
- ML20138Q698 + (Pressurized Thermal Shock Evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant)
- ML20137M662 + (Pressurized Thermal Shock Evaluation of the H.B. Robinson Unit 2 Nuclear Power Plant)
- ML20140C562 + (Pressurized Thermal Shock Evaluation of the H.B. Robinson Unit 2 Nuclear Power Plant)
- ML20137M863 + (Pressurized Thermal Shock Evaluations in Accordance W/10CFR50.61 for B&W Owners Group Reactor Pressure Vessels)
- ML20149D729 + (Pressurized Thermal Shock Probabilistic Fracture Mechanics Sensitivity Analysis for Yankee Rowe Reactor Pressure Vessel)
- ML20081K555 + (Pressurized Thermal Shock Risk Study)
- ML20259C766 + (Pressurized Thermal Shock:Anticipated Trips)
- ML20259C771 + (Pressurized Thermal Shock:Anticipated Trips)
- ML20259C802 + (Pressurized Thermal Shock:Excessive Main Feedwater)
- ML20259C798 + (Pressurized Thermal Shock:Excessive Main Feedwater)
- ML20259C805 + (Pressurized Thermal Shock:Excessive Main Feedwater)
- ML20259C776 + (Pressurized Thermal Shock:Secondary Depressurization)
- ML20259C795 + (Pressurized Thermal Shock:Secondary Depressurization)
- ML20259C792 + (Pressurized Thermal Shock:Secondary Depressurization)
- ML20259C787 + (Pressurized Thermal Shock:Secondary Depressurization)
- ML20259C782 + (Pressurized Thermal Shock:Secondary Depressurization)
- ML20084C847 + (Pressurized Thermal Shock:Tempest Computer Code Simulation of Thermal Mixing in the Downcomer of a Pressurized Water Reactor)
- ML12278A100 + (Pressurized Water Reactor (PWR) Internals Aging Management Program Plan)
- ML12278A099 + (Pressurized Water Reactor (PWR) Internals Aging Management Program Plan)
- ML043280631 + (Pressurized Water Reactor Containment Sump Evaluation Methodology)
- ML20024C475 + (Pressurized Water Reactor Electric Generating Plant)
- ML24069A006 + (Pressurized Water Reactor Gadolinia Pin Location Optimization Study)
- ONS-2016-047, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A); Submittal of Information to Resolve Licensee Action Item 6 + (Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A); Submittal of Information to Resolve Licensee Action Item 6)
- ML19282B339 + (Pressurized Water Reactor Lateral Core Response Routine (Fuel Assembly Mechanical Response Code)-FAMREC)
- ML15308A093 + (Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program)
- ML22354A197 + (Pressurized Water Reactor Owners Group - Request for Withholding Information from Public Disclosure Related to Implementation of Transmitter On-Line Monitoring)
- ML22361A156 + (Pressurized Water Reactor Owners Group Topical Report PWROG-21001-P/NP, Revision 0, Hydrogen-Based Transient Cladding Strain Limit)
- ML063600237 + (Pressurized Water Reactor Owners Group/ Boiling Water Reactor Owners Group, for Information Only - WCAP-16678-NP, Revision 0 Project to Update Section 2, Generic Knowledge and Abilities, of NUREG-1122 and NUREG-1123, (PA-OSC-0139))
- ML20055F489 + (Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod. Response to Public Comments - 2nd Comment Period)
- ML092180396 + (Pressurized-Water Reactor Owners Group Topical Report BAW-2374, Revision 2, Risk-Informed Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in Reactor Coolant System Upper Hot)
- ML20054L493 + (Pressurizer & Safety Relief Line Piping & Support Evaluation & Action Plan, Interim Rept)
- 05000361/LER-2009-003, Pressurizer Auxiliary Spray Failed Inservice Test + (Pressurizer Auxiliary Spray Failed Inservice Test)
- 05000313/FIN-2016007-11 + (Pressurizer Block Valve Not Installed in the Qualified Environmental Configuration)
- ML20260C198 + (Pressurizer Charge Line)
- 05000364/LER-2023-003, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits + (Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits)
- 05000364/LER-2023-001, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits + (Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits)
- ML20245B510 + (Pressurizer Code Safety Valve Reliability)
- ML20147E204 + (Pressurizer Component Studies w/RELAP4/Mod6. Interim Rept Presenting Results of Code Use for Pressurizer Component During Blowdown Phase of loss-of-coolant Accident)
- ML20260C204 + (Pressurizer Discharge Line. Sheet 1 of 2)
- 3F0207-07, Pressurizer Dissimilar Welds and Reactor Coolant System Leakage Monitoring + (Pressurizer Dissimilar Welds and Reactor Coolant System Leakage Monitoring)
- ML20263F291 + (Pressurizer Electromatic Relief Valve & Reactor Coolant System High Point Vents Logic)
- 05000269/FIN-2011017-01 + (Pressurizer Heater Breaker Installation That Would not have Functioned During Certain SSFCredited Events)
- ENS 40296 + (Pressurizer Heater Bundle Diaphragm Plate Degraded Condition)
- ENS 42847 + (Pressurizer Heater Capacity Less than Tech Spec Limit)
- ML20212B576 + (Pressurizer Heater Incident,Task 832)
- ML20235Q730 + (Pressurizer Heater Incident,Task 852)
- ML040780377 + (Pressurizer Heater Sleeve Leak Discussion Documentation)