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A list of all pages that have property "Title" with value "LOCA Analysis for Single Loop Operation". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML20261J297  + (LN-14-170 Series 1 Transportation Casks Cask Assembly & Misc Details.Sheet 1 of 1)
  • ML20266G847  + (LN-14-170 Series 1 Transportation Casks:Secondary Lid Details & Assembly. Sheet 1)
  • ML20266G834  + (LN-14-170 Series 1 Transportation Casks:Cask Assembly and Misc Details. Sheet 1)
  • ML20266G856  + (LN-14-170 Series 1 Transportation Casks:Optional 29 Inch Dia Secondary Lid Opening Including SST Liner. Sheet 1)
  • ML20266G836  + (LN-14-170 Series 1 Transportation Casks:Cask Body Details & Assembly. Sheet 1)
  • ML20266G852  + (LN-14-170 Series 1 Transportation Casks:Optional Stainless Steel Liner. Sheet 1)
  • ML20266G841  + (LN-14-170 Series Transportation Casks:Primary Lid Details & Assembly. Sheet 1)
  • ML20266H411  + (LN-142 Transportation Casks Cask General Arrangement. Sheet 1 of 2.Drawing Consists of 2 Aperture Cards)
  • ML20266H414  + (LN-142 Transportation Casks Cask General Arrangement. Sheet 2 of 2.Drawing Consists of 2 Aperture Cards)
  • ML22355A010  + (LO-132285 NuScale Power, LLC Requests Safeguards Reference Materials)
  • ML20100E835  + (LOCA & Seismic Analysis)
  • ML20081A779  + (LOCA & Seismic Analysis,Brunswick Steam Electric Plant)
  • ML20138P014  + (LOCA Amercoat D-6/Phenoline 305 Finish & Comanche Peak LOCA FSAR Curve, Final Rept)
  • ML19317H199  + (LOCA Analyses Annual Rept,FY77)
  • ML19246B788  + (LOCA Analyses at 1,500 MW Using Exxon Nuclear Co WREM-IIA PWR ECCS Evaluation Model,Large Break Example Problem)
  • ML20207G773  + (LOCA Analysis)
  • ML19354C423  + (LOCA Analysis Rept for Facility, Class 1,Revision 1)
  • ML19337A822  + (LOCA Analysis Rept for Millstone Unit 1 Nuclear Power Station)
  • ML20040G819  + (LOCA Analysis Rept for Pilgrim Nuclear Power Station. Errata & Addenda Sheets)
  • ML20214Q182  + (LOCA Analysis Update)
  • ML20083N209  + (LOCA Analysis Using Exem/Pwr ECCS Model)
  • ML20030A631  + (LOCA Analysis W/Automatic Depressurization & NFS Demonstration Fuel)
  • ML19254E829  + (LOCA Analysis at 1500 MW Using Exxon WREM-IIA PWR ECCS Evaluation Model)
  • ML20002A363  + (LOCA Analysis for Core 12 of Yankee Nuclear Power Station)
  • ML20041B128  + (LOCA Analysis for Peach Bottom APS Unit 2, Errata 7)
  • ML25105A282  + (LOCA Analysis of FFRD for Westinghouse 2-Loop, 3-Loop and 4-Loop Plants Audit Report)
  • ML25105A283  + (LOCA Analysis of FFRD for Westinghouse 2-Loop, 3-Loop and 4-Loop Plants Audit Report Cover Letter)
  • ML20094E943  + (LOCA Aspects of C-E Advanced LWR - Sys 80+)
  • ML20141B927  + (LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps)
  • ML20112H515  + (LOCA ECCS Analysis MAPLHGR Results)
  • ML20063E155  + (LOCA ECCS Limiting Break & Exposure Sensitivity Analysis for ENC XN-1 & XN-2 Reloads at Prairie Island Unit 1 w/5% Steam Generator Tubes Plugged Using ENC Wrem Iia PWR Model)
  • ML19350C391  + (LOCA ECCS Reanalysis for DC Cook Unit 1 Using ENC Wrem 11A PWR ECCS Evaluation Model)
  • 05000361/LER-1998-003, LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003)  + (LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003))
  • ML112770237  + (LOCA Frequencies for STP GSI-191( Final))
  • ML113060615  + (LOCA Frequencies for STP Nuclear Operating Company GSI-191)
  • ML112350883  + (LOCA Initiating Event Frequencies and Uncertainties Status Report)
  • ML19246A699  + (LOCA Mass & Energy Release for Containment Design, Revision 1)
  • ML24178A410  + (LOCA NRC 898 for Updated Resource Estimate and RAI Schedule)
  • ML20138P103  + (LOCA Phenoline 305 Primer/Phenoline 305 Finish, Final Rept)
  • ML20085F942  + (LOCA Prevention & Protection)
  • ML20059H599  + (LOCA Recovery Guideline)
  • ML20083K111  + (LOCA Rept)
  • ML20091B591  + (LOCA Rept for Monticello Nuclear Generating Plant)
  • ML23265A145  + (LOCA Revised NRC Form 898 for Resource Estimate)
  • ML20209F635  + (LOCA Seismic Structural Response of Exxon Nuclear Co 9X9 BWR Jet Pump Fuel Assembly)
  • ML20069H971  + (LOCA Simulation in NRU Program - Data Report for Thermal Hydraulic Experiment (TH-3))
  • ML20085E123  + (LOCA Simulation in NRU Program.Data Report for the Fourth Materials Experiment (MT-4))
  • ML20070G409  + (LOCA Simulation in NRU Program.Data Report for Thermal- Hydraulic Experiment 2 (TH-2))
  • ML20072E202  + (LOCA Simulation in NRU Program:The Continuous Measurement of Coolant Liquid Level During the MT-4 Experiment in the NRU Reactor)
  • ML20031G523  + (LOCA Simulation in the NRU Reactor.Materials Test-1)
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