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A list of all pages that have property "Title" with value "Calculation, Advanced BWR Certification Program". 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

  • ML19220C711  + (Calculation of Reactor Accident Consequences.Presents Dispersion Data & Health Consequences)
  • ML19220C721  + (Calculation of Reactor Accident Consequences.Presents Dispersion Data & Health Consequences)
  • ML19220C725  + (Calculation of Reactor Accident Consequences.Presents Dispersion Data & Health Consequences)
  • ML19220C691  + (Calculation of Reactor Accident Consequences.Presents Dispersion Data & Health Consequences)
  • ML19283B659  + (Calculation of Release of Radioactive Matls in Gaseous Effluents from Nuclear Powered Merchant Ships (NMS-GEFF Code))
  • ML19296A610  + (Calculation of Releases of Radioactive Matls in Gaseous & Liquid Effluents from Boiling Water Reactors)
  • ML19256A891  + (Calculation of Releases of Radioactive Matls in Gaseous Liquid Effluents from Bwrs)
  • ML20128C640  + (Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code))
  • Information Notice 1997-55, Calculation of Surface Activity for Contaminated Equipment & Materials  + (Calculation of Surface Activity for Contaminated Equipment & Materials)
  • ML20034D813  + (Calculation of Thermal Utilization by Collision Probability Method Including Scattering & Sources in Annuli Surrounding Fuel)
  • ML20128G949  + (Calculation of Weights Due to Fire Protection Matl)
  • 05000263/FIN-2011002-02  + (Calculation of Work Hours during Fatigue Rule Implementation)
  • ML17332A727  + (Calculation of X/Q Valves for Control Room Intakes)
  • ML20214R072  + (Calculation of the Power Distribution in the Venus PWR MOCK-UP Benchmark Using TWO-GROUP Diffusion Theory)
  • ML19254F545  + (Calculation to Determine Min Spacing Between Pairs of Fuel Assemblies Subsequent to MC4A Shipping Accident)
  • ML093360324  + (Calculation, 0800368.301, Rev 0, Material Properties for Davis-Besse Unit 1, RCP Suction, RCP Discharge, Cold Leg Drain and Core Flood Nozzles Preemptive Weld Overlay Repairs)
  • ML093360325  + (Calculation, 0800368.311, Rev. 0, Design Loads for the 28 I.D. Reactor Coolant Pump (RCP) Suction and Discharge Nozzles)
  • ML093360326  + (Calculation, 0800368.320, Rev. 1, Optimized Weld Overlay Sizing for the 28 I.D. Outlet/Discharge Reactor Coolant Pump Nozzle)
  • ML093360327  + (Calculation, 0800368.322, Rev. 1, Finite Element Models of the Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair)
  • ML093360328  + (Calculation, 0800368.323, Rev. 1, Thermal and Unit Mechanical Stress Analyses for Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair)
  • ML093360329  + (Calculation, 0800368.324, Rev. 0, Residual Stress Analysis of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair)
  • ML093360330  + (Calculation, 0800368.325, Rev. 0, ASME Code, Section III Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair)
  • ML093360331  + (Calculation, 0800368.326, Rev. 0, Crack Growth Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair)
  • L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches)  + (Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches))
  • ML090720869  + (Calculation, ALION-CAL-TVA-2739-03, Rev. 4, Watts Bar Reactor Building GSI-191 Debris Generation Calculation)
  • ML20116L280  + (Calculation, Advanced BWR Certification Program)
  • ML032190668  + (Calculation, Alternative Source Term Impact on NUREG-0737 Equipment Qualification, Vital Area Access, & Areas of Continuous Occupancy, Psat 3019CF.QA.09)
  • ML070110290  + (Calculation, Alternative Source Term, H21C094, U1 MSLB, AST Methodology)
  • ML102030116  + (Calculation, CN-MRCDA-08-51, Revision 1, Evaluation of Bottom Mounted Instrumentation Conduits for a Postulated Closure Head Assembly Drop Event, Enclosure 2 to NRC 2010-0102)
  • ML042930454  + (Calculation, Calculation of Eab and LPZ X/Q Values Using Pavan with the 1996 - 1999 Meteorological Data)
  • ML042930391  + (Calculation, Columbia Fuel Handling Accident Offsite and Control Room Doses Using Regulatory Guide 1.183 Source Terms)
  • ML042930485  + (Calculation, Columbia Offsite and Control Room Doses for LOCA Using AST and NRC Methods)
  • ML042930388  + (Calculation, Control Rod Drop Accident Offsite and Control Room Doses)
  • ML093410541  + (Calculation, DC00040-110, Revision 0, Post LOCA Sump Ph Effect from Miscellaneous Sources)
  • ML042930379  + (Calculation, Dose Calculation Database)
  • E910-04-023, Calculation, E900-03-014, Rev 0, Shonka Line Shack & Warehouse/Garage Pads FSS Survey Design  + (Calculation, E900-03-014, Rev 0, Shonka Line Shack & Warehouse/Garage Pads FSS Survey Design)
  • ML060120485  + (Calculation, EC-RADM-1126, Crhe and Off Site Fha/Eha Doses - Ast)
  • ML032190660  + (Calculation, Main Steam Line Break Accident Done for Vermont Yankee, Psat 3019CF.QA.06)
  • ML042930307  + (Calculation, Main Steamline Break Accident Off-Site and Control Room Doses)
  • ML032190656  + (Calculation, Pool Handling Accident Dose for Vermont Yankee, Psat 3019CF.QA.05)
  • ML032190652  + (Calculation, Post LOCA Suppression Pool Ph for Vermont Yankee, Psat 3019CF.QA.04)
  • ML042930715  + (Calculation, Post-LOCA Suppression Pool Ph)
  • ML032190663  + (Calculation, Radiological Evaluation of a Control Rod Drop Accident, Psat 3019CF.QA.07)
  • ML032190666  + (Calculation, Radiological Evaluation of a DBA-Loss of Coolant Accident, Psat 3019CF.QA.08)
  • GO2-04-170, Calculation, Secondary Containment Drawdown  + (Calculation, Secondary Containment Drawdown)
  • ML20045H147  + (Calculational Approach for Substatially Complete Containment Example Problem)
  • ML20064N980  + (Calculational Methodology for Equipment Qualification Radiation Dose)
  • ML20138A749  + (Calculational Methods for Analysis of Postulated UF6 Releases)
  • ML20138A754  + (Calculational Methods for Analysis of Postulated UF6 Releases)
  • Regulatory Guide 1.190  + (Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence)
  • ML20044A949  + (Calculations & Data to Support Remedial Action Plan & Final Design for Stabilization of Inactive U Mill Tailings at Green River,Ut)
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