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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20212J919 | 30 September 1999 | System Scaling for the Westinghouse AP600 Pressurized Water Reactor and Related Test Facilities.Analysis and Results | Hydrostatic |
| ML20212J907 | 31 August 1999 | Final Report of NRC AP600 Research Conducted at Oregon State University | |
| ML20155F165 | 31 October 1998 | Iodine Volatility and Ph Control in the AP-600 Reactor | Boric Acid |
| ML20236S075 | 30 April 1998 | Technical Evaluation Rept, Westinghouse-GOTHIC Computer Code for Analyses of AP600 Containment Transients | Ultimate heat sink Coatings GOTHIC |
| ML20247M291 | 9 April 1998 | Axisymmetric Buckling Analysis for AP600 Standard Plant Containment Vessel. Rept Undtd | Safe Shutdown Earthquake Earthquake |
| ML20247M304 | 9 April 1998 | Three-dimensional Buckling Analysis for AP600 Standard Plant Containment Vessel. Rept Undtd | Safe Shutdown Safe Shutdown Earthquake Finite Element Analysis Earthquake |
| ML20247M325 | 9 April 1998 | Three-Dimensional Analysis of AP600 Standard Plant Shield Building Roof. Rept Undtd | Safe Shutdown Safe Shutdown Earthquake Hydrostatic Finite Element Analysis Earthquake |
| ML20203K795 | 31 December 1997 | Technical Evaluation Rept INEEL/EXT-97-00779, Potential for AP600 In-Vessel Retention Thought Ex-Vessel Flooding | Probabilistic Risk Assessment Finite Element Analysis Severe Accident Management Guideline |
| ML20198L093 | 6 November 1997 | Revised, Assessment of Ex-Vessel Steam Explosions in AP600 Advanced Pressurized Water Reactor | Loop seal |
| L-94-006, Phenomena Identification and Ranking Tables for Westinghouse AP600 Small Break LOSS-OF-COOLANT Accident, Main Steam Line Break, and Steam Generator Tube Rupture Scenarios | 30 June 1997 | Phenomena Identification and Ranking Tables for Westinghouse AP600 Small Break LOSS-OF-COOLANT Accident, Main Steam Line Break, and Steam Generator Tube Rupture Scenarios | Ultimate heat sink Water hammer |
| ML20141E299 | 9 March 1997 | AP600 Nuclear Island Confirmatory Analysis of Soil Structure Interaction Effects | Earthquake |
| ML20138L996 | 31 January 1997 | Piping Benchmark Problems for the Westinghouse AP600 Standardized Plant | Safe Shutdown Earthquake |
| ML20247M276 | 30 November 1996 | Confirmatory Soil-Structure Interaction Analysis of Westinghouse AP600 Nuclear Island Structures | |
| ML20116A528 | 31 January 1996 | Monte Carlo Uncertainty Analysis of Aerosol Behavior in AP600 Reactor Containment Under Conditions of Specific Design-Basis Accident,Part 3:Corcon Boundary Conditions for Aerosol Behavior | |
| ML20116A518 | 31 July 1995 | Monte Carlo Uncertainty Analysis of Aerosol Behavior in AP600 Reactor Containment,Part 2: Fixed Boundary Conditions & Known Source of Nonradioactive Aerosol | |
| ML20116A514 | 30 June 1995 | Monte Carlo Uncertainty Analysis of Aerosol Behavior in AP600 Reactor Containment Under Conditions of Specific Design - Basis Accident,Part 1 | Boric Acid Fuel cladding |
| ML20078P397 | 31 January 1995 | Human Factors Engineering Insights for Advanced Reactors Based Upon Operating Experience | Stroke time Probabilistic Risk Assessment Emergency Lighting Scram Discharge Volume Power Operated Valves Biofouling Backfit Power change Overexposure Overspeed trip Water hammer |
| ML20069M300 | 31 May 1994 | Review of the Proposed Materials of Construction for the Sbwr and AP600 Advanced Reactors | Boric Acid Weld Overlay Hydrostatic Squib Feedwater Heater Intergranular Stress Corrosion Cracking Stress corrosion cracking Turbine Missile Exclusive Use Thermal fatigue |
| ML20063D912 | 27 January 1994 | Draft Technical Rept, Human Factors Engineering Program Review Model for Advanced Npps | Probabilistic Risk Assessment Backfit |