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List of results

• ML20126E151  + (Slide Presentation Entitled, Heat Loss Analysis for Mark III Containment Geometries, & Assessment of Effects of Flow Blockage (Due to Equipment,Piping,Etc) on Hydrogen Combustion Phenomena in Mark III Containment)
• ML20098B538  + (Slide Presentation Entitled, Hydrogen Source Term for BWR Degraded Core Accidents)
• ML19309G454  + (Slide Presentation Entitled, Identification of Issues Pertaining to Seismic & Geologic Siting Regulation,Policy & Practice for Nuclear Power Plants)
• ML20003A083  + (Slide Presentation Entitled, Inadvertent Boron Dilution)
• ML20049A637  + (Slide Presentation Entitled, Independent Design Review Program for WNP-1/4 & WNP 3/5,Supply Sys Meeting W/Nrc)
• ML20091K290  + (Slide Presentation Entitled, Industry Evaluation of Operating Shift Experience Requirements, Presented at 840224 Meeting Before Commissioners in Washington,Dc)
• ML20091K277  + (Slide Presentation Entitled, Industry Evaluation of Operating Shift Experience Requirements, Presented at 840224 Meeting Before Commissioners in Washington,Dc)
• ML19321A380  + (Slide Presentation Entitled, Lead Plant Generic T-Quencher Methodology)
• ML19323H136  + (Slide Presentation Entitled, Limerick Preliminary Risk Assessment,Technical Program Description)
• IA-87-113, Slide Presentation Entitled, Limited Application of Latin Hypercube Sampling for NUREG-1150  + (Slide Presentation Entitled, Limited Application of Latin Hypercube Sampling for NUREG-1150)
• ML20214X263  + (Slide Presentation Entitled, Limited Application of Latin Hypercube Sampling for NUREG-1150)
• ML20004E559  + (Slide Presentation Entitled, Mark II Main Vent Lateral Loads:Multivent)
• ML19339A738  + (Slide Presentation Entitled, Matl Aging Seminar)
• ML19331C141  + (Slide Presentation Entitled, Mechanical Dispersion of Core Matl)
• ML19350D643  + (Slide Presentation Entitled, Methods for Calculating Mass & Energy Release for Suppression Pool Temp Response to Safety Relief Valve Discharges)
• ML19316A799  + (Slide Presentation Entitled, Millstone Feedwater Spargers Upgrade Program)
• ML19305B764  + (Slide Presentation Entitled, Monticello Feedwater Nozzle Bypass Leakage Temp Monitoring)
• ML19312E854  + (Slide Presentation Entitled, NRC Caseload Forecast Panel Meeting, Re Status of Facility Const)
• ML20092F722  + (Slide Presentation Entitled, NRC Incident Investigation Team Entrance Presentation)
• ML19296C462  + (Slide Presentation Entitled, NRC Operations Ctr)
• ML19344E784  + (Slide Presentation Entitled, NRC Staff Review of Sequoyah (TVA) for Full Power Operation - Commission Briefing, 800821)
• ML19296C458  + (Slide Presentation Entitled, NRC Staff Review of TVA Sequoyah Nuclear Plant for Fuel Load & 50% Power Ol)
• ML19336A268  + (Slide Presentation Entitled, NRC Staff Review of Joseph M Farley Unit 2 Fuel Load & Low Power License)
• ML19290E663  + (Slide Presentation Entitled, NRC Staff Review of TVA Facility for Fuel Load & 5% Power Ol)
• ML20031B629  + (Slide Presentation Entitled, Nutech Feedwater Nozzle Bypass Leakage Monitoring Sys)

• ML20010J307  + (Slide Presentation Entitled, Open Issue Status)

• ML20081G101  + (Slide Presentation Entitled, Overview of Midland Independent Design & Const Verification Program, Presented to P Keshishian & G Gower)
• ML19347F023  + (Slide Presentation Entitled, Oyster Creek Core Spray Sparger Replacement)
• ML20052G818  + (Slide Presentation Entitled, Peer Advisory Panel on Operator Qualifications)
• ML20154B889  + (Slide Presentation Entitled, Performance of L Grade Stainless Steel Recirculation Outlet Safe Ends at Peach Bottom-3. List of Attendees Encl)
• ML20030D629  + (Slide Presentation Entitled, Plan for Prioritization & Resolution of Generic Items,Commission Briefing,810902)
• ML19322E631  + (Slide Presentation Entitled, Points to Consider Before Making Decision on Inerting)
• ML20098B581  + (Slide Presentation Entitled, Preliminary Assessment of Thermal Environ in Mk III Wetwell Based on 1/20th Scale Test Results)
• ML20009B881  + (Slide Presentation Entitled, Presentation to Auxiliary Sys Branch on CESSAR-F)
• ML19347F332  + (Slide Presentation Entitled, Presentation to NRC on Ceco PWR Fuel Mgt Capability)
• ML20127F896  + (Slide Presentation Entitled, Presentation of Operational Readiness)
• ML20052C710  + (Slide Presentation Entitled, Pressurized Thermal Shock Integration Study)
• ML20041F568  + (Slide Presentation Entitled, Pressurized Thermal Shock (PTS) USI A-49 Status Report to Us Nuclear Regulatory Commission,Mar 9,1982)
• ML20038C402  + (Slide Presentation Entitled, Pressurized Thermal Shock of Pressure Vessels,Commission Briefing)
• ML19341C467  + (Slide Presentation Entitled, Probabilistic Risk Assessment of Big Rock Point Plant)
• ML20010E372  + (Slide Presentation Entitled, Prompt Public Notification - Proposed Change of Implementation Date)
• ML20031F440  + (Slide Presentation Entitled, Prompt Public Notification Decision on Enforcement Actions)
• ML19322E638  + (Slide Presentation Entitled, Proposed Interim Hydrogen Control Requirements for Small Containment)
• ML19309A698  + (Slide Presentation Entitled, Proposed NRC Enforcement Policy)
• ML19332D423  + (Slide Presentation Entitled, Public Workshop on Technical & Policy Considerations for Nuclear Power Plant License Renewal,891113-14)
• ML20050A486  + (Slide Presentation Entitled, QA & Design Control)
• ML19309H301  + (Slide Presentation Entitled, Qualification & Testing Evaluation Program, mid-yr Review)
• ML20134A760  + (Slide Presentation Entitled, Quality Performance Review from 820427 Meeting)
• ML19320D342  + (Slide Presentation Entitled, Reactor Licensing Schedule Performance Evaluation Cys 1976,1977,1978. Related Documentation Encl)
• ML19323F461  + (Slide Presentation Entitled, Reactor Vessel Asymmetric Pressure Loads, from 800507 Meeting W/Util)
• ML20053B045  + (Slide Presentation Entitled, Review of McGuire Operating History)