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List of results

• ML20040A276  + (Slide Presentation Entitled NRC Reactor Operational Experience Program)
• ML20151V620  + (Slide Presentation Entitled NRC Research Prioritization, Presented at ACRS Subcommittee on Waste Mgt 880317 Meeting)
• ML19323A541  + (Slide Presentation Entitled NRC Staff Review for Fuel Load & 5% Power Ol. Draft License for Fuel Loading & Low Power Testing Encl)
• ML20003A131  + (Slide Presentation Entitled NRC Staff Review of Salem 2 for Full Power Operation)
• ML20002A286  + (Slide Presentation Entitled Near-Site Eof)
• ML19339B521  + (Slide Presentation Entitled Neutron Noise Can Be Used to Monitor Changes in BWR Dynamics)
• ML20054F588  + (Slide Presentation Entitled Nrc/Industry Pressurized Thermal Shock Meeting)
• ML20031B681  + (Slide Presentation Entitled Nuclear Power Plant Design Concepts for Sabotage Protection, Given at ACRS Subcommittee on Safety,Philosophy,Technology & Criteria 810408 Meeting in Washington,Dc)
• ML19345E097  + (Slide Presentation Entitled Odyn Licensing Basis)
• ML19345G315  + (Slide Presentation Entitled Ofc of Nuclear Regulatory Research Response for 810211 Briefing on Loft Review Group)
• ML20040A278  + (Slide Presentation Entitled Operating Reactor Events Meeting,810506)
• ML20053B595  + (Slide Presentation Entitled Plant Unique Analysis Rept,Mark I Containment Program)
• ML20002B922  + (Slide Presentation Entitled Preliminary Risk Assessment, Presentation of Results)
• ML20031A220  + (Slide Presentation Entitled Pressurized Thermal Shock of Pressure Vessels. Related Info Encl)
• ML20003D006  + (Slide Presentation Entitled Problems in Modeling of Small Break Loca)
• ML20134A530  + (Slide Presentation Entitled QA Initiatives)
• ML20003D024  + (Slide Presentation Entitled RELAP4/MOD 6 Assessment)
• ML19296D511  + (Slide Presentation Entitled Radiological Assistance Incidents)
• ML19339B528  + (Slide Presentation Entitled Reactivity from Neutron Power Spectral Density Measurements W/Cf-252)
• ML19345D815  + (Slide Presentation Entitled Reactor Primary Containment Structural Capability Investigations)
• ML20010A635  + (Slide Presentation Entitled Reactor Vessel Asymmetric Pressure Loads)
• ML19345C796  + (Slide Presentation Entitled Recirculation Pump Trip,Effects on ATWS at Big Rock Point, Presented at 801113 Meeting W/Nrc in Bethesda,Md)
• ML19345G302  + (Slide Presentation Entitled Rept of Loft Special Review Group for 810211 Meeting in Washington,Dc)
• ML19343B207  + (Slide Presentation Entitled Review Meeting on C-E Statistical Combination of Uncertainties Methodology. Proprietary Version Withheld (Ref 10CFR2.790))
• ML19323B648  + (Slide Presentation Entitled SEP Briefing Outline)

• ML19341A491  + (Slide Presentation Entitled SRP 1981 Revision Program)

• ML17272A887  + (Slide Presentation Entitled Sacrificial Shield Wall: Analysis,Design,Const of Sacrificial Shield Wall)
• ML19350D285  + (Slide Presentation Entitled Selection of Accident Sequences for Analysis)
• ML20030D918  + (Slide Presentation Entitled Sequoyah Nuclear Plant Schedule for Permanent Hydrogen Mitigation Sys,Rcs Vent Sys,Incore Thermocouples,Technical Support Ctr,Post-accident Sampling & Accident Monitoring Instrumentation)
• ML20030B910  + (Slide Presentation Entitled Severe Accident Sequence Analysis (Sasa) Program at Id Natl Engineering Lab,Egg Id)
• ML20010J475  + (Slide Presentation Entitled Shutdown Decay Heat Removal (Sdhr) Requirements)
• ML20058E808  + (Slide Presentation Entitled Six-Inch Pipe Weld QA Presentation, from 811113 Meeting W/Util)
• ML19345D902  + (Slide Presentation Entitled Startup Test Program Procedures & Progress:Trend Curves)
• ML20011A119  + (Slide Presentation Entitled Status of Development Items in TMI Action Plan,Commission Briefing)
• ML19339B524  + (Slide Presentation Entitled Status of Nuclear Plant Noise Signature Library)
• ML19340E180  + (Slide Presentation Entitled Storage of Low Level Waste at Reactor Sites)
• ML19339B517  + (Slide Presentation Entitled Summary of Fundamental Studies on Methods for Detecting,Locating & Characterizing Metallic Loose Parts in Nuclear Rcs)
• ML20037B732  + (Slide Presentation Entitled Svc Water Sys)
• ML19323G321  + (Slide Presentation Entitled Sys Interaction Discussion)
• ML19320C416  + (Slide Presentation Entitled TMI Evaluation Effort - Review of BWR Hydrogen Accommodation Capability)
• ML20078B646  + (Slide Presentation Entitled TMI-1 Once-Through Steam Generator Repair & Return to Svc)
• ML20003D011  + (Slide Presentation Entitled TRAC-P1A Assessment at Inel)
• ML20003D014  + (Slide Presentation Entitled TRAC-P1A Independent Code Assessment, Presented at Code Assessment Review Group & Advanced Code Review Group Joint Meeting)
• ML20003C999  + (Slide Presentation Entitled Tests Selected for Code Assessment, Presented at Advanced Code Review Group & Code Assessment Review Group 800626-27 Joint Meeting)
• ML20003D009  + (Slide Presentation Entitled Trac Assessment Results Obtained at BNL, Presented at Advanced Code Review Group & Code Assessment Review Group 800626-27 Joint Meeting in Silver Spring,Md)
• ML20054B994  + (Slide Presentation Entitled Zion Station Unit 1 D Steam Generator Recovery Program)
• ML20077G021  + (Slide Presentation Entitled, ACRS Full-Committee Briefing- Shoreham Status)
• ML19309F971  + (Slide Presentation Entitled, Accident Consideration Under Nepa,Secy 80-131)
• ML20010H586  + (Slide Presentation Entitled, Amends to 10CFR50 Re Hydrogen Control)
• ML19345H203  + (Slide Presentation Entitled, Amends to 10CFR50:Hydrogen Control-Certain Degraded Core Considerations)
• ML20098B571  + (Slide Presentation Entitled, Assessment of Scaling Adequacy for 1/20th Scale Test)