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List of results

• ML25204A020  + (Review of Composites for High-Temperature Nuclear Applications)
• ML24129A189  + (Review of Computer Code Development and Validation for Non-Light-Water Reactors)
• ML20128P122  + (Review of Computer Models of Containment Aerosol Deposition. Supporting Documentation Encl)
• ML20211P873  + (Review of Connecticut Yankee (Haddam Neck) Nuclear Power Plant Probabilistic Safety Study, Interim Rept)
• ML22332A460  + (Review of Continuity of Resident Inspector/Senior Resident Inspector Site Staffing Metric)
• ML19347F013  + (Review of Contract NRC-10-78-580 Awarded to Tera Advanced Svcs Corp for Implementation & Operation of Dcs. Rept Partially Withheld:Commercial Info (Ref FOIA Exemption 4))
• ML20034A511  + (Review of Contracting for Consultants)
• ML20197C598  + (Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analyses, Technical Evaluation Rept)
• ML20044E670  + (Review of Core-Concrete Thermophysical Properties)
• ML20136D647  + (Review of Cost Analysis Contained in Dec 1984 Draft of Regulatory Analysis of Recommendations Concerning Operator Shift Scheduling & Overtime in Nuclear Power Plants)
• ML20136D124  + (Review of Cost Analysis Contained in Regulatory Analysis for USI A-40, Seismic Design Criteria)
• ML20136D242  + (Review of Cost Analysis Contained in Value Impact Analysis for Rev 2 of Reg Guide 1.99)
• ML20132D408  + (Review of Cost Analysis Contained in Value Impact Analysis for Rev 2 of Reg Guide 1.99)
• ML20136D614  + (Review of Cost Burden Associated W/10CFR50 Regulatory Requirements)
• ML19274D878  + (Review of Cotter Corp Responses to Evaluation of Tailing Mgt Program & Suppl to Design Rept Is Complete.Furnishes Comments Re Responses & Proposed Changes in Tailings Mgt Plan)
• ML20136G222  + (Review of Crgr)
• IA-85-715, Review of Crgr  + (Review of Crgr)
• ML20148F605  + (Review of Criteria for Packaging Plutonium for Transport by Air, Rept Pf Ad Hoc Committee on Transportation of Plutonium by Air)
• ML19294A774  + (Review of Critical Experiments Performed for Fuel Cycle Safety Guidance, Quarterly Progress Rept)
• ML19249B932  + (Review of Critical Experiments Performed for Fuel Cycle Safety Guidance, Quarterly Progress Rept)
• ML19260B290  + (Review of Critical Experiments Performed for Fuel Cycle Safety Guidance, Quarterly Progress Rept for Jul-Sept 1979)
• ML19261D390  + (Review of Critical Experiments Performed for Fuel Cycle Guidance Safety, Quarterly summary,Jan-Mar 1979)
• ML19291B962  + (Review of Critical Experiments Performed for Fuel Cycle Safety Guidance, Informal Quarterly Progress Rept)
• ML20197B782  + (Review of Criticality Safety of Proposed Surface Density Criteria in 780322 Amend Appl Reveals Need for Info of Fundamental Supporting Nature.Requested Info Should Be Provided If Vendor Wishes to Continue This Approach)
• IR 05000353/2013005  + (Review of Cross-Cutting Aspect for Finding 05000353-13-005-001 - Letter to Mr. Thomas Dougherty, Site Vice President)

• LG-14-079, Review of Cross-Cutting Aspect for Finding 05000353/2013005-01  + (Review of Cross-Cutting Aspect for Finding 05000353/2013005-01)

• ML20081D099  + (Review of Crystal River Nuclear Generating Station Unit 3 Emergency Feedwater System Reliability Analysis)
• ML042440352  + (Review of Crystal River, Unit 3, Amendment Request Regarding Integrated Leakage Rate Testing Surveillance Interval Extension to 20 Years)
• ML20023E223  + (Review of Current & Projected Expenditures & Manpower Utilization for Gpu Nuclear Corp)
• ML20080K128  + (Review of Current Analysis Methodology for Reinforced Concrete Structural Evaluations)
• ML20141G677  + (Review of Current Basis for Predicting Severe Accident Source Terms W/Special Emphasis on NRC Source Term Reassessment Program (NUREG-0956))
• ML20058L816  + (Review of Current Literature Related to Generic Safety Issue 15)
• ML20136G107  + (Review of Current Understanding of Potential for Containment Failure from In-Vessel Steam Explosions)
• ML092240259  + (Review of Cycle 14 Steam Generator Tube Inservice Inspection Reports)
• ML072220350  + (Review of Cycle 14 Steam Generator Tube Inservice Inspection Summary Reports)
• ML062710314  + (Review of Cycle 15 Steam Generator Tube Inservice Inspection Summary Reports)
• ML19249B155  + (Review of Cycle 22 - 180-Day Steam Generator Tube Inspection Report)
• ML19035A042  + (Review of DOE Draft Mexican Hat Seep Monitoring Evaluation Report)
• ML20052F890  + (Review of DOE Waste Package Program Subtask 1.2 - Assessment of West Valley Waste Package Program, Draft Rept)
• ML20141D935  + (Review of DOE Waste Package Program.Semiannual Report Covering the Period April 1985-September 1985)
• ML20141E049  + (Review of DOE Waste Package Program.Semiannual Report Covering the Period October 1984 - March 1985)
• ML20100E325  + (Review of DOE Waste Package Program.Subtask 1.1 - National Waste Package Program April 1984-September 1984)
• ML20100E335  + (Review of DOE Waste Package Program.Subtask 1.1 - National Waste Package Program.October 1983 - March 1984)
• ML20074A971  + (Review of DOE Waste Package Program.Subtask 1.1 - National Waste Package Program Parts 1 and 2)
• ML20073C335  + (Review of DOE Waste Package Program.Subtask 1.1 - National Waste Package Program.April 1982 - September 1982)
• ML20097C803  + (Review of DOE Waste Package Program.Subtask 1.1 - National Waste Package Program,April 1983 - September 1983)
• ML20041G005  + (Review of DOE Waste Package Program.Subtask 1.1 - National Waste Package Program)
• ML20078F377  + (Review of DOE Waste Package Program.Subtask 1.1 - National Waste Package Program,October 1982 - March 1983)
• ML20133L711  + (Review of DOE Yucca Mountain Site Characterization Ofc Thermohydrologic Testing & Modeling Program)
• ML20138C419  + (Review of DOE/ID-10541 & Supporting Documentation)
• ML20138C210  + (Review of DOE/ID-10541, Lower Head Integrity Under In-Vessel Steam Explosion Loads)