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List of results

• ML19329A098  + (Analysis of seismically-induced Flood at Facility)
• ML20196H788  + (Analysis of the A302B and A533B Standard Reference Materials in Surveillance Capsules of Commercial Power Reactors)
• ML20128L834  + (Analysis of the Ability of Current Health Physics Instruments to Predict Dose in Exposed Individuals)
• ML20211K082  + (Analysis of the Critical Flow Model in TRAC-BF1)
• ML19343C732  + (Analysis of the Flecht Seaset Unblocked Bundle Steam Cooling and Boiloff Tests)
• ML20095C077  + (Analysis of the Impact of Inservice Inspection Using a Piping Reliability Model)
• ML20112B397  + (Analysis of the Irradiation Data for A302B and A533B Correlation Monitor Materials)
• ML20116J531  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation)
• ML20035G071  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Fire Analysis)
• ML20099D528  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary)
• ML20058E891  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis)
• ML20113H989  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis)
• ML20116J479  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis)
• ML20099D625  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification)
• ML20105C822  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices)
• ML20105C817  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report)
• ML20035E731  + (Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program.Parameter Estimation Analysis and Screening Human Reliability Analysis)
• ML20236K044  + (Analysis of the NESDIP2 and NESDIP3 Radial Shield and Cavity Experiments)
• ML20054H144  + (Analysis of the Pulsed Neutron Activation Technique)
• ML20041D063  + (Analysis of the Pulsed Neutron Activation Technique)
• ML071500212  + (Analysis of the Radiation Protection Area for Fire Molding)
• ML26043A257  + (Analysis of the Sacramento Municipal Utility Districts Updated Decommissioning Funding Plan for the Rancho Seco Independent Spent Fuel Storage Installation)
• ML24222A207  + (Analysis of the Source Term in the Main Steamlines of BWRs After Early In-Vessel Phase)
• ML20248A467  + (Analysis of the Thetis Boildown Experiments Using RELAP5/ MOD2)
• ML20101P855  + (Analysis of the Uptf Separate Effects Test 11 (STEAM-WATER Countercurrent Flow in the Broken LOOP Hot Leg) Using RELAP5/MOD2)

• ML20247A272  + (Analysis of the VENUS-3 Experiments)

• ML20098F771  + (Analysis of the Venus PWR Engineering Mockup Experiment - Phase I: Source Distribution)
• ML19210E894  + (Analysis to Demonstrate Adequate Core Cooling)
• ML20141P118  + (Analysis to Evaluate Electrical Protection Assembly & Inverter Circuits)
• ML20077S163  + (Analysis to Support Removal of FCS Toxic Gas Monitoring Sys)
• ML20003A434  + (Analysis,Conclusions and Recommendations Concerning Operator Licensing)
• ML062860241  + (Analysis: Brief Description of Issue)
• ML062860229  + (Analysis: Brief Description of Issue)
• ML062860240  + (Analysis: Briefing Description of Issue)
• ML19323H402  + (Analytic Rebalance Technique for Pressure Calculation in Two -Phase Flow Sys)
• ML20129E176  + (Analytic Studies Pertaining to Steam Generator Tube Rupture Accidents)
• ML19268A265  + (Analytical & Experimental Studies of Nonlinear Sys Modeling & Scaling, Progress Rept for May-Nov 1976)
• ML19309H618  + (Analytical & Physical Data for Pump Discharge Line Sys. Sheet 1 0f 4)
• ML20054G132  + (Analytical Assessment for Effects of Loose Parts,Zion 1)
• 05000455/FIN-2013005-04  + (Analytical Basis for PTL Curves Not Maintained Consistent With the Unit 2 Vessel Head Stud Configuration)
• ML20031F631  + (Analytical Chemistry Branch & Radiological & Environ Sciences Lab Sample Record Sheets Re Special Environ Monitoring Program.Includes Samples Received on 800924 & 1210 & 810424 & 0727)
• ML18096A911  + (Analytical Data Rept, for 920603)
• ML18096B008  + (Analytical Data Rept, for Project 28173)
• ML25149A031  + (Analytical Data Summary Report for Samples Collected from the Multipurpose Handling Facility at the San Onofre, Dated May 1, 2025)
• ML20114E764  + (Analytical Evaluation of Flaw Indication in Unit 1 Reactor Vessel Closure Head)
• GO2-05-153, Analytical Evaluation of Inservice Inspection Examination Results  + (Analytical Evaluation of Inservice Inspection Examination Results)
• ENS 43442  + (Analytical Instrument Shipped Off Site with Radioactive Sources Installed)
• ML20237A030  + (Analytical Investigation Concerning Condensation of Steam W/Low Air Content)
• ML20083L749  + (Analytical Justification for Treatment of Reactor Coolant Pumps During Accident Conditions)
• ML19322E405  + (Analytical Method for Determining Probability Distribution of Max of Combined Responses)
• ML19211D267  + (Analytical Model for Computing Air Bubble & Boundary Pressures Resulting from Safety/Relief Valve Discharge Through T-Quencher Device, Re Mark I Containment Program. Nonproprietary Version of NEDE-21878-P)