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List of results

• ML19309B446  + (Probability Analysis of Surface Rupture Offset Beneath Getr Reactor Bldg)
• ML19274E698  + (Probability Analysis of Surface Rupture Offset Beneath Reactor Bldg,Getr)
• ML20154S432  + (Probability Based Load Combination Criteria for Design of Shear Wall Structures)
• ML20135B353  + (Probability Based Load Combination Criteria for Design of Concrete Containment Structures)
• ML20023B036  + (Probability Based Load Combination for Design of Category I Structures, Progress Rept)
• ML19347E809  + (Probability Based Load Criteria for the Design of Nuclear Structures:A Critical Review of the STATE-OF-THE-ART)
• ML20084Q919  + (Probability Based Safety Checking of Nuclear Plant Structures)
• ML20073M475  + (Probability Estimate of Temp Extremes for Seabrook,Nh)
• ML19310A645  + (Probability Estimates of Temp Extremes for Contiguous Us)
• ML20147H631  + (Probability Evaluation for Dynamic Response Combinations)
• ML20079G850  + (Probability and Consequences of Misloading Fuel in a PWR)
• ML20102A778  + (Probability and Consequences of Rapid Boron Dilution in a Pwr.A Scoping Study)
• ML20011A167  + (Probability of Containment Failure Due to Steam Explosions Following a Postulated Core Meltdown in an LWR)
• ML19242B610  + (Probability of Detecting Planar Defects in Heavy Wall Welds by Ultrasonic Techniques According to Existing Codes)
• ML20078P155  + (Probability of Detection by Bobbin Insp)
• ML20078G835  + (Probability of Detection by Bobbin Insp)
• ML20138P267  + (Probability of Disk Cracking Due to Stress Corrosion)
• ML20138B898  + (Probability of Disk Cracking Due to Stress Corrosion: Grand Gulf Unit 1)
• ML20053A571  + (Probability of Exceeding OBE Horizontal Design Response Spectrum,Midland Plant - Units 1 & 2)
• ML20246P746  + (Probability of Failure in BWR Reactor Coolant Piping.Pipe Failure Induced by Crack Growth and Failure of Intermediate Supports)
• ML20215F918  + (Probability of Failure in BWR Reactor Coolant Piping.Volume 3: Probabilistic Treatment of Stress Corrosion Cracking in 304 and 316NG Stainless Steel BWR Piping Weldments)
• ML20246P912  + (Probability of Failure in BWR Reactor Coolant Piping.Summary Report)
• ML20207H650  + (Probability of Failure of BWR Reactor Coolant Piping.Volume 4:Guillotine Break Indirectly Induced by Earthquakes)
• ML20039A676  + (Probability of Human Error in Selected Nuclear Maint Tasks)
• ML19323E667  + (Probability of Intersystem Loca:Impact Due to Leak Testing & Operational Changes)

• ML062360128  + (Probability of Nonrecovery)

• ML20132F203  + (Probability of Pipe Failure in the Reactor Coolant Loops of Westinghouse PWR Plants.Volume 4:Pipe Failure Induced by Crack Growth in West Coast Plants)
• ML20126M923  + (Probability of Pipe Failure in the Reactor Coolant Loops of Westinghouse PWR Plants.Volume 1:Summary Report)
• ML20106B827  + (Probability of Pipe Failure in the Reactor Coolant Loops of Combustion Engineering PWR Plants.Volume 1:Summary Report)
• ML20093E180  + (Probability of Pipe Failure in the Reactor Coolant Loops of Combustion Engineering PWR Plants.Vol 2:Pipe Failure Induced by Crack Growth)
• ML20211G831  + (Probability of Pipe Failure in the Reactor Coolant Loops of Babcock and Wilcox PWR Plants.Volume 1:Summary Report)
• ML20126M914  + (Probability of Pipe Failure in the Reactor Coolant Loops of Babcock and Wilcox PWR Plants.Volume 2:Guillotine Break Indirectly Induced by Earthquakes)
• ML20111B136  + (Probability of Pipe Failure in the Reactor Coolant LOOP of Westinghouse PWR Plants.Volume 3:Guillotine Break Indirectly Induced by Earthquakes)
• ML20097H694  + (Probability of Pipe Failure in the Reactor Coolant Loops of Westinghouse PWR Plants.Volume 2:Pipe Failure Induced by Crack Growth)
• ML20114A725  + (Probability of Pipe Failure in the Reactor Coolant Loops of Combustion Engineering PWR Plants,Volume 3:Double Ended Guillotine Break Indirectly Induced by Earthquakes)
• ML20010C795  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Volume 9:PRAISE Computer Code Users Manual)
• ML20031C819  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Volume 1:Summary,Load Combination Program Project I Final Report)
• ML20031A546  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Volume 2:Primary Coolant Loop Model)
• ML20010H171  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Volume 6:Failure Mode Analysis)
• ML20031C701  + (Probability of Pipe Fracture in the Primary Coolant LOOP of PWR Plant.Volume 7:Sustem Failure Probability Analysis)
• ML20031D160  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Pipe Fracture Indirectly Induced by an Earthquake)
• ML20010C797  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Volume 5:Probabilistic Fracture Mechanics Analysis)
• ML20010C796  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Volume 3:Nonseismic Stress Analysis)
• ML20010H170  + (Probability of Pipe Fracture in the Primary Coolant LOOP of a PWR Plant.Volume 4:Seismic Response Analysis)
• ML20058J701  + (Probability of Vessel Failure from PTS Events & USNRC Requirements)
• ML20151H047  + (Probable Local Precedent for Earthquakes of Magnitude 8 or 9 in Pacific Northwest, Presented at 880412-15 Meeting in Olympia,Wa)
• ENS 44870  + (Probable Loss of 3.3 Mci C-14 in Transit)
• ML20349L132  + (Probable Max Flood Hydrograph Valley Storage Not Considered at River Mile 151.1)
• ML19282C877  + (Probable Max Flood from Canon De Marquez Watershed for Designing U Tailings Impoundment Drainage Diversion Sys, Marquez,Nm,Bokum Resources Corp)
• ML20349L153  + (Probable Maximum Flood Hydrograph Valley Storage Considered at River Mile 151.1)
• ML20261B549  + (Probable Maximum Flood:Curbs,Grading & Paving West Plant Area)