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A list of all pages that have property "Title" with value "Technical Evaluation Rept:Std Modular Htgr". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20235V152  + (Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2)
  • ML20094A484  + (Technical Evaluation Rept,Rev 6 for Plant Odcm)
  • ML20140C780  + (Technical Evaluation Rept,Second Interval Inservice Insp Program,Arkansas Nuclear Power Plant Unit 1)
  • ML20141D243  + (Technical Evaluation Rept,Second Interval Inservice Insp Program for Quad Cities Nuclear Power Station,Units 1 & 2)
  • ML20141F627  + (Technical Evaluation Rept,Second Interval Inservice Insp Program,Peach Bottom Units 2 & 3)
  • ML20132D046  + (Technical Evaluation Rept,Second Interval Inservice Insp Program for Pilgrim Nuclear Power Station,Unit 1)
  • ML20210T251  + (Technical Evaluation Rept,Second Ten-Year Interval Pump & Valve Inservice Testing Program, for Perry Nuclear Power Plant)
  • ML20003C810  + (Technical Evaluation Rept,Submerged Demineralization Sys)
  • ML19324A625  + (Technical Evaluation Rept,TMI-1,Evaluation of Revised TMI-1 Response to Generic Ltr 81-12,Alternate Safe Shutdown Capability)
  • ML19247E204  + (Technical Evaluation Rept,Tech Specs Change for AR Nuclear One,Unit 2,Docket 50-368, Preliminary Rept)
  • ML18040A226  + (Technical Evaluation Rept,Technical Basis for Reduction of Torus Shell Condensation Oscillation Loads for Niagra Mohawk Power Corp Nine Mile Point Unit 1)
  • ML20207E206  + (Technical Evaluation Rept,Tmi Action - NUREG-0737 (II.D.1), Byron Units 1 & 2)
  • ML20245E927  + (Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing, Oconee Units 1,2 & 3)
  • ML20245H152  + (Technical Evaluation Rept,Tmi Action-NUREG-0737 (II.D.1), Relief & Safety Valve Testing,Beaver Valley Unit 2)
  • ML20207K243  + (Technical Evaluation Rept,Tmi Action-NUREG-0737 (II.D.1), Relief & Safety Valve Testing,Yankee Rowe)
  • ML17291B140  + (Technical Evaluation Rept,Wppss Plant No 2,Pump & Valve Ist,Rev 0,Second Ten-Yr Interval)
  • ML20217K132  + (Technical Evaluation Rept- CENPD-137,Suppl 2P, Calculative Methods for ABB CE Small Break LOCA Evaluation Model)
  • ML20010E423  + (Technical Evaluation Rept:Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation & Other Safety Feature Signals)
  • ML20080A661  + (Technical Evaluation Rept:Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01)
  • ML20071B069  + (Technical Evaluation Rept:Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01)
  • ML20077A028  + (Technical Evaluation Rept:Evaluation of Utility Responses to Suppl 1 to NRC Bulletin 90-01:Beaver Valley-1/-2)
  • ML20085K467  + (Technical Evaluation Rept:Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01,Braidwood-1/2)
  • ML20195G527  + (Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R)
  • ML20080L686  + (Technical Evaluation Rept:Pp&L,Susquehanna Steam Electric Station,Pump & Valve Inservice Testing Program,Rev 10,Unit 1 Second 10-Yr Interval,Rev 7,Unit 2 Second 10-Yr Interval)
  • ML20076K941  + (Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co)
  • ML20236C806  + (Technical Evaluation Rept:Std Modular Htgr)
  • ML17309A747  + (Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001:St.Lucie-1/-2)
  • ML20079S078  + (Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Hatch-1/-2)
  • ML20105D246  + (Technical Evaluation Rept;Pump & Valve Inservice Testing Program Farley Nuclear Power Plant,Units 1 & 2 Southern Nuclear Operating Co)
  • ML20058P235  + (Technical Evaluation Rept;Technical Evaluation of Snpc Statistical Setpoint/Transient Methodology Topical Rept EMF-92-081(P))
  • ML17291A137  + (Technical Evaluation Summary of First 10-Year Interval Inservice Insp Relief Requests for WNP-2)
  • ML051450522  + (Technical Evaluation for Evaluation of Pressure Entering the Enclosure Building Filtration Region on Main Steam Safety Valve Lift Millstone Unit 2)
  • ML12346A463  + (Technical Evaluation for the Endorsement of NEI 99-01, Revision 6)
  • ML17213A498  + (Technical Evaluation of Adequacy of Station Electric Distribution Sys Voltages for St Lucie Nuclear Power Plant, Unit 1)
  • ML20049J618  + (Technical Evaluation of Adequacy of Station Electric Distribution Sys Voltages for AR Nuclear One,Unit 1)
  • ML20050B282  + (Technical Evaluation of Adequacy of Station Electric Distribution Sys Voltages for Haddam Neck Nuclear Power Plant)
  • ML13317A893  + (Technical Evaluation of Adequacy of Station Electric Distribution Sys Voltages for San Onofre Nuclear Generating Station,Unit 1,Selected Issues Program)
  • ML17309A218  + (Technical Evaluation of Adequacy of Station Electric Distribution Sys Voltages for Re Ginna Nuclear Power Station,Unit 1, Informal Rept)
  • ML20209D225  + (Technical Evaluation of Bartlett Nuclear Portable Solidification Station Topical Rept, Informal Rept)
  • ML20239A550  + (Technical Evaluation of Bg&E Topical Rept:Retran Computer Code Reactor Transient Analysis Model Qualification)
  • ML20235P082  + (Technical Evaluation of Bg&E Topical Rept:Retran Computer Code Reactor Transient Analysis Model Qualification)
  • ML20117P789  + (Technical Evaluation of Bg&E Topical Rept:Retran Computer Code Reactor Transient Analysis Model Qualification)
  • ML18029A539  + (Technical Evaluation of Browns Ferry Nuclear Plant, Plant-Unique Analysis Rept)
  • ML20085J054  + (Technical Evaluation of Brunswick Units 1 & 2,Plant-Unique Analysis Rept)
  • ML20236C524  + (Technical Evaluation of Comanche Peak Steam Electric Station 1982 Hydro Test & ASME Section XI VT-2 Test)
  • ML20217K757  + (Technical Evaluation of Combustion Engineering Owners Group Joint Application for Safety Injection Tanks & Low Pressure Safety Injection System Allowed Outage Time (AOT) Extension)
  • ML20206R619  + (Technical Evaluation of Comm Ed Dcrdr of Dresden Station, Units 2 & 3)
  • ML19325C158  + (Technical Evaluation of Dcrdr)
  • ML20236D381  + (Technical Evaluation of Dcrdr Info Supplementing Summary Rept for Fort St Vrain Nuclear Generating Station)
  • ML20236D374  + (Technical Evaluation of Dcrdr Info Supplementing Summary Rept for Fort St Vrain Nuclear Generating Station)
  • ML20205Q540  + (Technical Evaluation of Dcrdr Summary Rept for Rancho Seco Nuclear Generating Station)
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