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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.

List of results

• BVY 04-071, Calculation VYC-2314, Rev. 0, Ccn 02, Minimum Containment Overpressure for Non-LOCA Events  + (Calculation VYC-2314, Rev. 0, Ccn 02, Minimum Containment Overpressure for Non-LOCA Events)
• ML042080475  + (Calculation VYC-2314, Revision 0 and Ccn 01, Minimum Containment Overpressure for Non-LOCA Events)
• ML042080469  + (Calculation VYC-808, Rev. 6 & Ccns 01, 03, 04 and 05, Core Spray & Residual Heat Removal Pump Net Positive Suction Head Margin Following a Loss of Coolant Accident with Fibrous Debris on the Intake..)
• ML12171A320  + (Calculation WBNTSR-009, Control Room Operator and Offsite Doses from a Fuel Handling Accident, Revision 14 (Enclosure 2))
• ML11160A215  + (Calculation Worksheet, Construction Scenario Dose to Inadvertent Intruder)
• ML23135A194  + (Calculation XX-E-013 Rev. 4, CN003, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML23135A206  + (Calculation XX-E-013, Rev 4, CN004, Post-Fire Safe Shutdown (PFSSD) Analysis)
• WO 23-0006, Calculation XX-E-013, Rev 4, CN005, Post-Fire Safe Shutdown (PFSSD) Analysis  + (Calculation XX-E-013, Rev 4, CN005, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML23135A195  + (Calculation XX-E-013, Rev 4, CN006, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML23135A202  + (Calculation XX-E-013, Rev 4, CN007, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML23135A197  + (Calculation XX-E-013, Rev 4, CN009, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML23135A200  + (Calculation XX-E-013, Rev. 4, CN002, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML23135A198  + (Calculation XX-E-013, Rev. 4, CN008, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML23135A203  + (Calculation XX-E-013, Rev. 4, Post-Fire Safe Shutdown (PFSSD) Analysis)
• ML043630467  + (Calculation YA-CALC-00-004-04, Analysis of Dose to Future Residents from Soil, Concrete & Steel Debris Deposited at the Waste Control Specialists Disposal Facility)
• ML070110294  + (Calculation for Alternative Source Term H21C090, Ul FHA, AST Methodology, (Fuel Handling Accident))
• ML070110285  + (Calculation for Alternative Source Term, H21C087, Unit 1 LOCA Secondary Containment Bypass Piping Data)
• ML070110323  + (Calculation for Alternative Source Term, H21C078, Unit 1 MSLB Puff Release Atmospheric Relative Concentrations)
• ML070110310  + (Calculation for Alternative Source Term, H21C084, Post-LOCA Suppression Chamber (Torus) Water Ph Analysis)
• ML070110305  + (Calculation for Alternative Source Term, H21C096, Ul CRDA, AST Methodology)
• ML070110321  + (Calculation for Alternative Source Term, H21C076, X/Qs for Releases from NMP Units 1 & 2 (CNS Calcs NMPAST-01-001 & NMPAST-02-001))
• ML20106J792  + (Calculation for Checking Functional Status of Beam B4 & Cheek Plate Connection at Right End of Beam B10 in Quad Cities,Unit 1 Southeast,Rhr Corner Room)
• ML042680151  + (Calculation for Contaminated Concrete for the License Termination Plan (LTP))
• ML042680146  + (Calculation for Contaminated Concrete for the License Termination Plan (LTP))
• ML042680149  + (Calculation for Contaminated Concrete for the License Termination Plan (LTP))

• L-08-349, Calculation for Contingency Flaw Evaluation Support  + (Calculation for Contingency Flaw Evaluation Support)

• ML20128K119  + (Calculation for LOCA Block Start)
• ML20087A529  + (Calculation of Absorbed Doses to Water Pools in Severe Accident Sequences)
• ML20151W801  + (Calculation of Activity Ratio of Total U to U-235 in Residual U at Framatome Cogema Fuels Wet Weather Stream)
• Regulatory Guide 1.109  + (Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I)
• ML20092B161  + (Calculation of Byron D4 SG Tube Support Plate Differential Pressures During MSLB W/RELAP5M2)
• ML19347B474  + (Calculation of Canon Experiment Using Trac Code)
• ML20205F047  + (Calculation of DBA-1 Pcrv Penetration Leak Rate)
• ML20034D812  + (Calculation of Effective Resonance Integral for Multiple, UO-2 Rods W/Various Coolants)
• ML20234D883  + (Calculation of Failure Importance Measures for Basic Events and Plant Systems in Nuclear Power Plants)
• ML20087K704  + (Calculation of Fluid Circulation Patterns in the Vicinity of Submerged Jets Using Orsmac)
• ML20034C758  + (Calculation of Gamma Skin Dose for Na-24 Skin Contamination Incident)
• ML20027D239  + (Calculation of Health Effects Per Curie Release for Comparison W/Epa Values Incorporated in Establishing 40CFR191 Guidelines)
• ML20010H104  + (Calculation of Loft Reactor Decay Heat, Technical Rept)
• ML21265A550  + (Calculation of Negative Void Coefficient of MNRC Core)
• ML17157A809  + (Calculation of Offsite & Control Room Doses for 25 Gpm & 50 Gpm Water Equivalent Steam Leaks Using Design Basis Assumptions)
• ML19318A257  + (Calculation of Overall Flow Loss Coefficient for Vent Sys of Torus/Lightbulb Containment)
• ML19312D664  + (Calculation of Particulate Dispersion in Design-Basis Tornadic Storm)
• ML19350D478  + (Calculation of Particulate Dispersion in DBT Storm from Atomic Intl Nuclear Development Facility,Santa Susana,Ca. Prepared for DOE)
• ML19284A862  + (Calculation of Particulate Dispersion in Design-Basis Tornadic Storm from Exxon Nuclear Co,Richland,Wa)
• ML22019A122  + (Calculation of Permeability by the Falling Head Method)
• ML20058J474  + (Calculation of Probability of Onset of Brittle Failure of Vessels Under Pressure)
• ML20133D980  + (Calculation of Psl LOSP Initiator Event Frequency & Confidence Limits)
• ML19220C718  + (Calculation of Reactor Accident Consequences,Dispersion Data & Health Consequences)
• ML19220C719  + (Calculation of Reactor Accident Consequences.Presents Dispersion Data & Health Consequences)
• ML19220C710  + (Calculation of Reactor Accident Consequences.Presents Dispersion Data & Health Consequences)