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List of results

• ML19350D287  + (Slide Presentation Entitled Aqueous Iodine Chemistry)
• ML20052C019  + (Slide Presentation Entitled Assumptions for Thermal Analysis of Preamplifier Unit)
• ML20052F103  + (Slide Presentation Entitled Briefing on Crbr Containment Isolation Sys)
• ML20003C996  + (Slide Presentation Entitled Code Assessment Strategy & Code Acceptance Criteria (Tentative), Presented at Code Assessment Review Group & Advanced Code Review Group 800626-27 Joint Meeting in Silver Spring,Md)
• ML20042B974  + (Slide Presentation Entitled Commission Briefing on AEOD Program & Capabilities to Perform Trend & Pattern Analyses)
• ML18087A710  + (Slide Presentation Entitled Commission Briefing Re Salem Event on 830225)
• ML20039G772  + (Slide Presentation Entitled Commission Briefing on TMI-1 status,811221)
• ML20052F115  + (Slide Presentation Entitled Containment Filtration Sys)
• ML20052F122  + (Slide Presentation Entitled Containment Isolation Sys)
• ML20052F110  + (Slide Presentation Entitled Containment Sys)
• ML20052F124  + (Slide Presentation Entitled Containment Testing)
• ML19339B527  + (Slide Presentation Entitled Continuous Reactor Surveillance Sys)
• ML20024B494  + (Slide Presentation Entitled Control Room Indications)
• ML19339B535  + (Slide Presentation Entitled Development of Reactor Coolant Pump Monitoring & Diagnostic Sys)
• ML20010A642  + (Slide Presentation Entitled Differential Pressure Fourier Components)
• ML19350D294  + (Slide Presentation Entitled Effect of Accident Loads on Performance of Engineered Safety Features)
• ML20037B552  + (Slide Presentation Entitled Effect on Steam Environ on Core Spray Nozzle Angles)
• ML20052F135  + (Slide Presentation Entitled Emergency Plant Svc Water Sys)
• ML19340D740  + (Slide Presentation Entitled Encl Bldg Presentation)
• ML20033A902  + (Slide Presentation Entitled Equipment Qualification Program)
• ML19330B006  + (Slide Presentation Entitled Essential Elements of Viable QA Program)
• ML19350D288  + (Slide Presentation Entitled Estimation of Aerosol Sources from Core Melt Accident Sequences for Sotri)
• ML20003D005  + (Slide Presentation Entitled Experience Gained in Providing Small Break Test Data from Loft & Semiscale, Presented at Code Assessment Review Group & Advanced Code Review Group 800626 Meeting)
• ML20052F130  + (Slide Presentation Entitled Failed Fuel Monitoring)
• ML20052F272  + (Slide Presentation Entitled Findings Through IE Bulletin 80-14 on SDIV Level Switch Procedures. Related Info Encl)

• ML20004F248  + (Slide Presentation Entitled Fire Protection Design)

• ML19350D289  + (Slide Presentation Entitled Fission Product Transport in Primary Sys to Containment)
• ML19350D290  + (Slide Presentation Entitled Fission Product Transport Through Containment)
• ML19309D566  + (Slide Presentation Entitled Fundamental Lesson)
• ML20040F656  + (Slide Presentation Entitled GE Risk Analysis BWR Core Thermocouples)
• ML19340F088  + (Slide Presentation Entitled General Considerations on Use of PRA in Regulatory Process)
• ML20066B606  + (Slide Presentation Entitled IP Quality Program-Update)
• ML20066B604  + (Slide Presentation Entitled IP Quality Recovery Program)
• ML20032E521  + (Slide Presentation Entitled Independent Design Review of Containment Sys, Vol 2)
• ML20101U208  + (Slide Presentation Entitled Independent QA Evaluation of Palo Verde Nuclear Generating Station Units 1,2 & 3. Related Documents Encl)
• ML19339B515  + (Slide Presentation Entitled Introduction for 1980 Surveillance & Noise Diagnostics Research Review Group Meeting)
• ML20042B975  + (Slide Presentation Entitled LER Info & Data Flow Process)
• ML20003D020  + (Slide Presentation Entitled Large Sys Blowdown Simulations Using Computer Codes)
• ML19320C760  + (Slide Presentation Entitled Lead Plant Generic T-Quencher Methodology)
• ML19339C814  + (Slide Presentation Entitled Limerick Generating Station Preliminary Risk Assessment)
• ML20040F107  + (Slide Presentation Entitled Limerick Generating Station, Preliminary Risk Assessment, Presentation of Results on 801209.Monthly Title List Encl)
• ML20003D000  + (Slide Presentation Entitled Measurement Requirements for Assessment of Small Break LOCA Codes)
• ML20090B388  + (Slide Presentation Entitled Midland Project QA Organizational Change, Presented at 820112 Meeting in Glen Ellyn,Il)
• 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)