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A list of all pages that have property "Title" with value "Review of Advanced Reactor Computer Code Evaluations". Since there have been only a few results, also nearby values are displayed.

Showing below up to 27 results starting with #1.

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List of results

  • ML12160A371  + (Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to Fukushima Daiichi Nuclear Plant Accident)
  • ML12159A149  + (Review of 60-day Response to Request for Information)
  • ML12159A288  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Related to Fukushima Dai-ichi Accident)
  • ML121600029  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12159A591  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12159A377  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12159A366  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12159A355  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12157A552  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML121600140  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12159A493  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12159A237  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML12158A362  + (Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident)
  • ML20148F450  + (Review of 780719 Lic Amend Appl.Appl Requested Change in Licensee Name to Energy Sys Group,Rockwell Intl Corp. Recommends Issuance of Lic Amend)
  • ML20197B564  + (Review of 780927 Lic Amend Appl to Increase Possession Limit of C-252 from 1.2 Milligrams to 3.0 Milligrams as Requested by Babcock & Wilcox.Increase Poses No Safety or Environ Problems)
  • ML20148L959  + (Review of 781720 Texas Instr Plan for Future Decontamination of Places of Use & Sites Authorized by Special Nuc Matl Lic SNM-23.Plan Is Found to Provide Satisfactory Assurance That Health,Safety & Environ Will Be Protected)
  • ML18044A339  + (Review of 791031 Proposal Re Startup Physics Test Program. Complete Program Acceptable)
  • ML20154S082  + (Review of 860225 Application for Amend to License SNM-778, Authorizing Reorganization of Line Organization Which Indirectly Affects Safety Organization.Approval Recommended)
  • ML031120705  + (Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001)
  • ML20151S566  + (Review of 971003 Entergy River Bend Ampacity Derating RAI Response, Ltr Rept to USNRC 980120 Rev 1)
  • ML19261D130  + (Review of ANSI Std Affected by NRC Position Re Question 421.40 Will Not Be Complete Until 790604)
  • ML20058E955  + (Review of ASME Code Criteria for Control of Primary Loads on Nuclear Piping System Branch Connections and Recommendations for Additional Development Work)
  • 05000338/LER-1983-022-03, Review of ASME XI Iwv Program Identified 126 Valves Exercised &/Or Stroke Timed at Incorrect Frequency.Caused by Implementation of Fragmented Program  + (Review of ASME XI Iwv Program Identified 126 Valves Exercised &/Or Stroke Timed at Incorrect Frequency.Caused by Implementation of Fragmented Program)
  • ML18150A363  + (Review of Additive Manufacturing for Reactor Materials & Components (Amy Hull))
  • ML22143A928  + (Review of Advanced Manufacturing Techniques and Qualification Processes for Light Water Reactors - Electron Beam Welding)
  • ML20351A217  + (Review of Advanced Manufacturing Techniques and Qualification Processes for Light Water Reactors - Laser Powder Bed Fusion Additive Manufacturing)
  • ML24137A055  + (Review of Advanced Manufacturing Technologies for Fusion Reactor Materials)
  • ML19302F015  + (Review of Advanced Reactor Computer Code Evaluations)
  • ML20030A171  + (Review of Advanced Reactor Computer Code Evaluations)
  • ML21053A024  + (Review of Advanced Reactor Computer Code Evaluations)
  • ML21088A409  + (Review of Advanced Reactor Computer Code Evaluations)
  • ML23348A182  + (Review of Advanced Reactor Content of Application Project/Technology-Inclusive Content of Application Project Guidance)
  • ML19289E477  + (Review of Amend 18 to License SNM-1067 Issued 790213 Indicates Overpayment of Review Fee.Refund Will Be Sent)
  • ML17138A470  + (Review of Amend 55 to Sections 13.2 & 13.5 of FSAR Is Complete.Amend Is Not Acceptable for Cold License Eligibility Per 10CFR55.25.Addl Info Required for Review Is Encl)
  • ML20197C627  + (Review of Amend Appl Re Lacrosse BWR Fuel assemblies,790922 Gen Elec Ltr to Nrc,Is in Progress.Questions Re Fuel Arrangement & Discrepancy in Calculations Are Propounded)
  • ML19289E100  + (Review of Amend Application Concludes Proposed Spacing Criterion Provides Assurance of Nuclear Criticality Safety Under Defined Conditions)
  • ML19274C891  + (Review of Amended Security Plan,Revision 4,dtd 781106 Has Identified Several Areas Where Addl Info Is Needed or Deficiencies Exist.Encl Withheld (Ref 10CFR2.790))
  • ML111610163  + (Review of Amendment 22 of Safety Analysis Report - Period from 10/6/2008 Through 3/18/2010)
  • ML22119A247  + (Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review)
  • ML17354A431  + (Review of Ampacity Ratings for Power Cables in Conduits & Trays w/Thermo-Lag 330-1 Covering)
  • ML14357A136  + (Review of Analysis of Capsule Withdrawal Schedule from Reactor Vessel Radiation Surveillance Program)
  • ML063310245  + (Review of Analytical Evaluation)
  • SVPLTR 12-0043, Review of Analytical Evaluation of Reactor Pressure Vessel Closure Flange Weld Indication  + (Review of Analytical Evaluation of Reactor Pressure Vessel Closure Flange Weld Indication)
  • ML20043B377  + (Review of Anna (Advance Neutron Noise Analysis) Software Sys for BWR Stability Measurements)
  • ML19220B923  + (Review of App I Submitted on 760714 Is Complete.If Applicant Elects to Do Cost/Benefit Analysis,Addl Info Will Be Required Re Agricultural Productivity in 50 Mile Radius)
  • ML17324B219  + (Review of App R Procedures for Post-Fire Remote Emergency Shutdown Outside Control Room,Dc Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept)
  • ML21320A007  + (Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary))
  • ML23283A305  + (Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary))
  • ML20147A902  + (Review of Appl Gives No Basis for Antitrust Action. (Encl to 7809220136))
  • 05000461/FIN-2009003-04  + (Review of Applicability of TSSR 3.0.3 to Mulitple Missed Surveillance Intervals for Excess Flow Check Valves)
  • ML051800288  + (Review of Application for Release of Part of Site for Unrestricted Use - R. E. Ginna Nuclear Power Plant)
  • ML19209D241  + (Review of Application of Strategic Analysis to Matl Accounting:Consensus Rept by Peer Review Group)
  • ML18081A998  + (Review of Aquatic Sampling Programs in DE River Estuary from 1958-1979,w/Special Ref to Capture of Shortnose Sturgeon)
  • ML063560288  + (Review of Arizona Public Service Company Letter Dated November 16, 2006, Involving the Remaining Corrective Actions for the Containment Sump Voiding Yellow Finding)
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