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

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List of results

  • 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)
  • ML20039A721  + (Calculations Conducted in Developing an Audit Capability for ECCS Analysis)
  • ML061280076  + (Calculations EC-M88-021 and EC-E89-016, Station Blackout Water Requirements Form Extended Power Up-Rate)
  • ML20136B146  + (Calculations Made for Hydrogen Bubble in Reactor Vessel)
  • ML14038A030  + (Calculations Number: PRA-BC-F-11-004, Fire PRA Logic Model for Farley Nuclear Plants, Version 2)
  • ML20136B142  + (Calculations Re Containment Hydrogen Bubble)
  • ML19220C892  + (Calculations Re Dose Consequences)
  • ML20081B715  + (Calculations Re Facility Components.Supporting Documentation Encl)
  • ML19221A392  + (Calculations Re Solubility of Gas in Primary Sys)
  • ML20217B067  + (Calculations Ref in Final Site Observational Work Plan for Umtra Project New Rifle Site)
  • ML12023A080  + (Calculations Requested for License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train)
  • ML18025A181  + (Calculations Supporting Chapter 5 Amendment Request, Including NCS-2018-005, NCS-1998-039 and NCS-1998-011)
  • 05000333/FIN-2010006-02  + (Calculations for Offsite Power Availability)
  • ML20126J144  + (Calculations for PWR Std Problem 1 & 2 W/Direct Heating. Addl Documentation Encl)
  • ML19224B240  + (Calculations for Pressurizer Level,Tabulation of Telecopy Transmittals to Rc Wilson,Surveillance Performance Forms & Valve Performance Data)
  • ML052010601  + (Calculations for Sections 2.6 and 2.9 of NMC Environmental Report by Constellation Nuclear Services)
  • ML20069L858  + (Calculations in Support of a Potential Definition of Large Release)
  • ML19220C932  + (Calculations of HPCI Capacity for Heat Removal)
  • ML20065J230  + (Calculations of Hydrogen Detonations in Nuclear Containments by Random Choice Method)
  • ML19330A733  + (Calculations of Large Cold Leg Break W/Steam Generator Tube Ruptures in PWR Using TRAC-P1A Computer Program, Preliminary Assessment Rept)
  • ML20071M377  + (Calculations of Reactor Accident Consequences Version 2 CRAC2 Computer Code.Users Guide)
  • ML20032B713  + (Calculations of Signals in CODED-APERTURE Imaging of MANY- Pin Bundles of LMFBR Fuel)
  • ML19337A045  + (Calculations of Skyshine Gamma-Ray Dose Rates from Independent Spent Fuel Storage Installations Under Worst Case Accident Conditions)
  • ML20054H457  + (Calculations of Two Series of Experiments Performed at the Poolside Facility Using the Oak Ridge Research Reactor)
  • ML19220C618  + (Calculations of Vol of Hydrogen Bubble)
  • ML19221A256  + (Calculations on Population Dose & Health Effects Estimates)
  • ML20058F679  + (Calculations to Estimate Margin to Failure in TMI-2 Vessel)
  • ML20065D197  + (Calculations to Estimate the Margin to Failure in the TMI-2 Vessel)
  • 05000528/FIN-2009008-01  + (Calculations to Support the Graded Voltage Relay Setpoint)
  • ML20202C427  + (Calculations,Preliminary Design for Review,Vol I-III for U Mill Tailings Remedial Action Project,Ambrosia Lake,Nm)
  • ML072700849  + (Caldon Experience in Nuclear Feedwater Flow Measurement)
  • ML053490347  + (Caldon Inc. Proprietary Information Package, INFO-18)
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