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List of results

• ML19259C691  + (Assessment of Radiation Doses Resulting from Releases of Radon-222 & Radium-226 from Mining & Milling Activities. Monthly Progress Rept June 1979)
• ML19289E171  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Ra-226 from U Mining & Milling Activities, Monthly Progress Rept for Jan 1979)
• ML19262B043  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Ra-226 from U Mining & Milling Activities, Monthly Progress Rept for Sept 1979)
• ML19247A221  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Radium-226 from U Mining & Milling Activities, Interim Rept,Apr 1979)
• ML19296C112  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Ra-226 from U Mining & Milling Activities, Monthly Progress Rept for Dec 1979)
• ML19262B918  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Ra-226 from U Mining & Milling Activities, Monthly Progress Rept for Nov 1979)
• ML19225C735  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Ra-226 from U Mining & Milling Activities. Interim Rept,May 1979)
• ML19332B349  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Ra-226 from U Mining & Milling Activities. Monthly Progress Rept,Mar 1980)
• ML19249D446  + (Assessment of Radiation Doses Resulting from Releases of Rn-222 & Radium-226 from U Mining & Milling Activities, Monthly Progress Rept for Jul 1979)
• ML20094D492  + (Assessment of Radiation Effects Relating to Reactor Pressure Vessel Cladding)
• ML20085J173  + (Assessment of Radiation Risks, util-medical Dialogue Presented at 800922-23 Intl Inst of Safety & Health Forum in Washington,Dc)
• ML022560183  + (Assessment of Radiological Consequences for 1.7% Power at H. B. Robinson Unit 2 Power)
• ML20151Q139  + (Assessment of Radiological Impact of Inactive U-Mill Tailings at Grand Junction,Co)
• ML20207G089  + (Assessment of Radionuclide VAPOR-PHASE Transport in Unsaturated Tuff)
• ML20107M126  + (Assessment of Reactor Coolant Pump Instrumentation in Support of Coolant Inventory Trend Analysis)
• ML20198E479  + (Assessment of Reactor Insp Program OPP-92-01)
• ML19242B684  + (Assessment of Reactor Internals Vibration in BWR/4 & BWR/5 Plants,Amend 2, NEDO-24057-2)
• ML19345F956  + (Assessment of Reactor Internals Vibration BWR/4 & BWR/5 Plants. Corrected Copy)
• ML17334B251  + (Assessment of Reg Guide 1.99,Rev 2 Upon D.C. Cook Units 1 & 2 Adjusted Ref Temps & Pressure Temp Curves)
• ML20030B590  + (Assessment of Reinforcement on Capacity & Behavior of Masonry Walls)
• ML20069F565  + (Assessment of Relevance & Significance of Board Notifications,As Allowed by ASLB 830309 Memorandum & Order. Matters Raised by Board Notifications Should Not Be Dealt W/By Aslb.Related Correspondence)
• ML080860026  + (Assessment of Remaining Operating License Application Review Scope)
• ML17251A730  + (Assessment of Removal of Raised Floor & Mod to Fire Detection Zones for Plant Process Computer Sys (PPCS) Computer Room at Ginna Nuclear Plant, Informal Rept)
• ML20027E115  + (Assessment of Response by Region 3 to Allegations Concerning Offgas Filter Bldg,Lasalle Nuclear Station)
• NL-08-0508, Assessment of Results of Augmented Radiological Environmental Monitoring Program for the Years 2000 Through 2007  + (Assessment of Results of Augmented Radiological Environmental Monitoring Program for the Years 2000 Through 2007)
• ML20092D105  + (Assessment of Retrieval Alternatives for the Geologic Disposal of Nuclear Waste)

• ML20153B740  + (Assessment of Reverse Direction Testing of Containment Isolation Valves)
• B12902, Assessment of Reverse Direction Testing of Containment Isolation Valves  + (Assessment of Reverse Direction Testing of Containment Isolation Valves)

• ML19332F486  + (Assessment of Risk Significance of SEP Issues for Oyster Creek, Final Rept Phase II)
• ML20204G888  + (Assessment of Risk from U Mining in Virginia)
• ML20058B084  + (Assessment of Scale Effects on Vortexing,Swirl,And Inlet Losses in Large Scale Sump Models)
• ML19256F501  + (Assessment of Seismic Design Requirements for Containment Structure in Response to CA Div of Mines & Geology)
• ML20248D089  + (Assessment of Seismic Margin Calculation Methods)
• ML20065K382  + (Assessment of Selected TMI-1 Training Programs, Vol 1)
• ML20116P119  + (Assessment of Selected Trac and RELAP5 Calculations for OCONEE-1 Pressurized Thermal Shock Study)
• ML20058J854  + (Assessment of Serviceability of Filtration Systems of Reactor Containment in the Event of a Severe Accident)
• ML20207J365  + (Assessment of Severe Accident Prevention and Mitigation Features:Pwr,Large Dry Containment Design)
• ML20207J361  + (Assessment of Severe Accident Prevention and Mitigation FEATURES:PWR,ICE-CONDENSER Containment Design)
• ML20207J386  + (Assessment of Severe Accident Prevention and Mitigation Features:Bwr,Mark I Containment Design)
• ML20207J379  + (Assessment of Severe Accident Prevention and Mitigation Features:Bwr,Mark III Containment Design)
• ML20207J382  + (Assessment of Severe Accident Prevention and Mitigation Features:Bwr,Mark II Containment Design)
• ML20050B625  + (Assessment of Shift Staffing Requirements for Big Rock Point Nuclear Power Plant)
• ML20235E598  + (Assessment of Shoreham Nuclear Power Station Secondary Containment Severe Accident Mitigation Capability, Final Ltr Rept)
• ML20082U145  + (Assessment of Short THROUGH-WALL Circumferential Cracks in Pipes.Experiments and Analysis,March 1990 - December 1994)
• ML20137C447  + (Assessment of Significance of Applicant U-Bolt Sample Discussed in Applicant Motion for Summary Disposition Re Cinched-Down U-Bolts)
• ML033090345  + (Assessment of Site Visit to Cooper Nuclear Station (CNS))
• ML17138A766  + (Assessment of Sites for Augmentation Reservoir, Aug 1977)
• ML20141P071  + (Assessment of Specialized Educational Programs for Licensed Nuclear Reactor Operators)
• ML20129E180  + (Assessment of Spent Fuel Cooling)
• ML20217G981  + (Assessment of Spent Fuel Cooling, Presented at 970526-30 5th Intl Conference on Nuclear Engineering (ICONE5) in Nice, France)
• ML20217G595  + (Assessment of Spent Fuel Cooling, Presented at 961021-23, 24th Water Reactor Safety Info Meeting in Bethesda,Md)
• Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling  + (Assessment of Spent Fuel Pool Cooling)