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List of results

• ML24080A343  + (IMC Appendix C2, Fuel Facility Health Physics Inspector Technical Proficiency Training & Qualification)
• ML23219A028  + (IMC IP Update Presentation Final)
• ML24086A538  + (IMC-1248, Appendix G Qual Card for Louis Caponi)
• ML23074A170  + (IMC1245 Appendix C9, Senior Reactor Analyst Training and Qualification Program)
• ML20203M269  + (IMC1245 Appendix D4 Electrical Advanced Level Training and Qualification Journal)
• ML20034C496  + (IMPACTS-BRC,VERSION 2.0.Program Users Manual)
• ML20095B822  + (IMPACTS-BRC,VERSION 2.1.Codes and Data Verification)
• ML22320A088  + (IMRDD-MMR-22-03, Release 01, Quality Assurance Program Description for the University of Illinois at Urbana?Champaign Research and Test Reactor)
• ML23038A242  + (IMRDD-MMR-23-01-NP, Release 1, University of Illinois Urbana-Champaign High Temperature Gas-cooled Research Reactor: Fuel Qualification Methodology)
• ML24101A415  + (IMRDD-MMR-23-06, Revision 2, University of Illinois Urbana-Champaign High Temperature Gas-cooled Research Reactor: Micro Modular Reactor (Mmrtm) Principal Design Criteria - Topical Report)
• ML24208A068  + (IMRDD-MMR-23-06-A, Release 02, University of Illinois Urbana-Champaign High Temperature Gas-cooled Research Reactor: Micro Modular Reactor (Mmr Tm) Principal Design Criteria)
• ML022960036  + (IMS Systems Registration Certificate NR-1120-D-101-S Dated 10/22/02)
• ML19326B178  + (IMS Systems Transmittal Letter for Ssd Certificate NR-1120-D-101-S Ssd 19-29)
• ML23199A176  + (IMS Systems, Inc Response to Request Withholding Proprietary Information - Ssd 23-07)
• IR 015000037/2020002  + (IMS Systems, Inc. - NRC Inspection No. 15000037/2020-002 Acknowledgement)
• ML23188A027  + (IMS Systems, Inc. Third RAI Ssd Case 23-07)
• ML18164A013  + (IMS Systems, Inc., Letter Transmitting Amended Registration Certificate NR-1120-D-101-S, Ssd Case No. 18-10)
• ML20342A275  + (IMS Sytems Ltr Re Reply to Notice of Violation)
• ML20099K809  + (IN-CORE Fuel Freezing and Plugging Experiments:Preliminary Results of Sandia Tran Series I Experiments)
• ML19347E189  + (IN-PILE Calorimetry in the Joint Sandia/Kfk EQUATION-OF- State Experiments on Nuclear Fuels)
• ML20246J479  + (IN-PILE Observation of Fuel and Clad Relocation During LMFBR CORE-DISRUPTIVE Accidents)
• ML20033A834  + (IN-PILE POWER-COOLING-MISMATCH Testing of a NINE-ROD Fuel Assembly - Results of Test PCM-7)
• ML20116P190  + (IN-PLACE Thermal Annealing of Nuclear Reactor Pressure Vessels)
• ML20072J032  + (IN-PLANT Considerations for Optimal Offsite Response to Reactor Accidents)
• ML20127P363  + (IN-PLANT Source Term Measurements at Brunswick Steam Electric Station)

• ML20037D629  + (IN-PLANT Source Term Measurements at Four Pwrs)

• ML20137X735  + (IN-PLANT Source Term Measurements at Prairie Island Nuclear Generating Station)
• ML20032A474  + (IN-PLANT Source Term Measurements at Rancho Seco Station)
• ML20215L094  + (IN-SITU Stress Measurements in the Earths Crust in the Eastern United States)
• ML20062A688  + (IN-VESSEL ZIRCALOY-OXIDATION/HYDROGEN-GENERATION Behavior During Severe Accidents)
• Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors  + (IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors)
• Information Notice 2010-23, IN: Malfunctions of Emergency Diesel Generator Speed Switch Circuits  + (IN: Malfunctions of Emergency Diesel Generator Speed Switch Circuits)
• 05000341/FIN-2007003-06  + (INADEQUATE DETERMINATION OF MAXIMUM ALLOWABLE TEMPERATURE FOR HPCI PUMP OPERATION ( Section 1R21.3.b.6))
• 05000341/FIN-2007003-07  + (INADEQUATE DETERMINATION OF MINIMUM FLOW SETTING FOR HPCI PUMP (Section 1R21.4.B.1))
• ML042440776  + (INDUSTRY-PROPOSED Material, Environment, Aging Effects, and Program Combinations for the GALL Report Update)
• ML20209E016  + (INEEL/EXT-99-00116, Summary & Evaluation of NRC-Sponsored Stellite 6 Aging & Friction Tests)
• ML20210D846  + (INEEL/EXT-99-00415, Technical Evaluation Rept(Rev 1) on Proposed Alternative to Iwe/Iwl Containment Insp,Comanche Peak Electric Station)
• ML18331A318  + (INEEL/INT-99-00126, ICP Report - Criticality Safety Evaluation of TMI-2 Canister Transportation and Storage)
• ML023570266  + (INES Rating of Davis-Besse Reactor Head Degradation Event (to: Commissioner Assistants; from: J W Craig))
• ML20031D422  + (INL (Kerr))
• ML20030B772  + (INL (Windes) ASME Considerations for Htr Graphite and Composite Components)
• ML20030B774  + (INL (Wright) - Qualification of Materials for Elevated Temperature Nuclear Components)
• ML22178A157  + (INL Nsuf Presentation for June 27, 2022 Public Meeting on Harvesting)
• ML20350B659  + (INL Report: Development of Dry Cask Risk Tools)
• ML24016A067  + (INL-NMED Study on Fixed Gauge Failure Events)
• ML21140A330  + (INL/CON-17-41453, On-Line Monitoring of I&C Transmitters and Sensors for Calibration Verification & Response Time Testing Was Successfully Implemented at Atr)
• ML12276A079  + (INL/EXT-10-20739, Resolution of SPAR Model Technical Issues)
• ML22353A565  + (INL/EXT-20-58896, Development of Dry Cask Risk Tools: a Risk Assessment Tool for Reviewal of License Action Requests, Revision 1)
• ML20324A110  + (INL/EXT-20-58896, Revision 0, Development of Dry Cask Risk Tools, 11/16/2020 COB)
• ML21124A112  + (INL/EXT-21-62220, Chemical Compositional Analysis and Micro-structural Characterization of Harvested Zorita Reactor Pressure Vessel (RPV) Internals)
• ML23354A276  + (INL/RPT-23-72874, Overlapping Domain Coupling of Multidimensional and System Codes in Neams - Pronghorn and SAM)