Search by property

Jump to navigation Jump to search

This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

Search by property

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

â§Ľshowingresultsâ§˝

View (previous 50 | next 50) (20 | 50 | 100 | 250 | 500)


    

List of results

  • 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)
  • ML20086K511  + (LOCA Analysis for Single Loop Operation)
  • 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)
  • 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)
  • ML20127H608  + (LOCA Simulation in the National Research Universal Reactor Program.Postirradiation Examination Results for the Third Materials Test (MT-3) - Second Campaign)
  • ML20073K769  + (LOCA Simulation in the National Research Universal Reactor Program.Data Report for the Third Materials Experiment (MT-3))
  • ML20084C713  + (LOCA Simulation in the National Research Universal Reactor Program: Postirradiation Examination Results for the Third Materials Experiment (MT-3))
  • ML19318B367  + (LOCA Test Series - Test TC-1, Test Results Rept)
  • ML19269E498  + (LOCA Test Series Test LOC-3 Experiment Predictions)
  • ML19263B867  + (LOCA Test Series to Test Loc 3 Experiment Operating Specification. Specifies Procedure to Test Nuclear Fuel Rods Under off-normal Accident Conditions)
  • ML19332B148  + (LOCA Test Series,TC-3,Experiment Operating Spec)
  • ML19276F349  + (LOCA Test Series,Test LOC-5,Experiment Operating Spec)
  • ML19332A072  + (LOCA Test Series,Test LOC-6,Thermal Fuels Behavior Program, Experiment Operating Spec)
  • ML19254D824  + (LOCA Test Series:Test LOC-5 Experiment Predictions, Interim Rept for Sept 1979)
  • ML19249D466  + (LOCA Test Series:Test Loc 5,Experiment Operating Spec, for Aug 1979)
  • ML20138N994  + (LOCA Test of Svc Topcoated W/Phenoline 305 Finish)
  • ML20138P002  + (LOCA Testing of Carbo Weld 11 W/Various Topcoats, Final Rept)
  • ML20138P100  + (LOCA Testing of Carbo Zinc 11 Over SSPC-SP6 Blast, Abstract Rept)
  • ML20138N692  + (LOCA Testing of Carbo Zinc 11 Over SSPC-SP6 Blast, First Rept)
  • ML20138P005  + (LOCA Testing of Carbo Zinc 11 at Low Film Thicknesses, Topcoated W/Phenoline 305,Phenoline 368WG & Carboline 191 Hb, Final Rept)
  • ML20138N974  + (LOCA Testing of Carbo Zinc 11 at Various Thicknesses, Untopcoated & Topcoated W/Phenoline 305, Interim Rept. Related Documentation Encl)