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A list of all pages that have property "Title" with value "Updated Probabilistic Risk Analysis (PRA) Model". 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

  • PNP 2013-046, Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation  + (Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation)
  • ML110060692  + (Updated Palisades Reactor Vessel Pressurized Thermal Shock Evaluation)
  • ML20216C418  + (Updated Paper Entitled, Spreadsheet Model for Evaluation of Substatistical Confidence in Nuclear ISI Plans. Rev of 970624 Paper)
  • ML20209C566  + (Updated Part 21 Interim Rept to Rept 98-029 Re Locbart Computer Code Error.Caused by Logic Error in Locbart.Locbart Calculations,With Corrected Code Version,Have Been Performed for Number of Typical Large Break LOCA Transients)
  • ML20041E290  + (Updated Part 21 Rept 81-05 Re Min Separation Requirements for Certain Components of 4160-volt Switchgear,Initially Reported on 811002.Detailed Analysis Ongoing.Extension of 90 Days Needed to Complete Investigation)
  • ML20099F388  + (Updated Part 21 Rept Re Missile Door Calculation Errors. Initially Reported on 840705.Calculations & Designs Reconciled W/Respective Customers.Doors Qualified as Meeting Original Project Design Requirements)
  • ML19339C187  + (Updated Part 21 Rept Re Performance of Addl Interference Checking of All Sizes of Vendor Part 2541/modified 2540. Sizes -6,-15 & -120 Assemblies Contain Potential Interference Which May Hinder Function of Unit)
  • ML20083A747  + (Updated Part 21 Rept on Status of RCIC Sys Equipment Room Cooler & Automatic Restart of Chillers,Per 830429 & 0630 Ltrs.Safe Shutdown Sys Review Completed on Perry Nuclear Project.Results Provided)
  • ML12198A060  + (Updated Performance Assessment for the Low-Level Waste Facility, Radioactive Material License No. R04100)
  • ML101890676  + (Updated Permit Info Re Kewaunee LRA FSEIS)
  • PLA-6835, Updated Personnel Information  + (Updated Personnel Information)
  • PLA-6705, Updated Personnel Information  + (Updated Personnel Information)
  • ML123550039  + (Updated Plans and Schedule for ONS Standby Shutdown Facility Design Review Project)
  • NRC-13-0018, Updated Plans for Restoration of the South Reactor Feedpump  + (Updated Plans for Restoration of the South Reactor Feedpump)
  • ML18130A949  + (Updated Policy Issue Table for Non-Light Water Reactors - May 2018)
  • ML16295A148  + (Updated Policy Statement on Training and Qualification of Nuclear Power Plant Personnel--ACRS Comments)
  • ML20136A339  + (Updated Post-Shutdown Decommissioning Activities Report and Irradiated Fuel Management Plan)
  • ML24157A367  + (Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter)
  • ML24256A042  + (Updated Post-Shutdown Decommissioning Activities Report, Rev. 6)
  • ML20087P652  + (Updated Potential Significant Deficiency Rept SD-47 Re Possibly Underdesigned Seismic Duct Welds.Initially Reported on 831109.Calculations on Required Weld Strength Being Reviewed.Next Rept by 840608)
  • ML20116N303  + (Updated Prediction of Frequency of Aircraft Crashes at TMI-1 Site)
  • ML22346A268  + (Updated Presentation Slides for Pre- Application Meeting for Planned Submittal of GE Hitachi Nuclear Energy BWRX-300 Instrumentation and Controls Architecture Topical Report NEDC-33925P)
  • ML21187A171  + (Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit)
  • ML21187A170  + (Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit)
  • ML032521478  + (Updated Pressure Temperature Limits Report and Topical Reports for SQN Technical Specification Change No. 00-14)
  • ML20202E053  + (Updated Probabilistic Seismic Hazard Analysis for Paducah Gaseous Diffusion Plant in Paducah,Ky,Final Rept. Page 4-35 of Incoming Submittal Was Not Included)
  • Information Notice 2010-19, Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States  + (Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States)
  • ML21272A278  + (Updated Projected Financial Statements for Spinco Consolidated)
  • ML19296A625  + (Updated Projections of Radwaste to Be Generated by Us Nuclear Power Industry)
  • ML20070T406  + (Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Univ of Florida Test Reactor Conversion from High Enriched U to Low Enriched U)
  • ML20205E473  + (Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel)
  • ML20101L349  + (Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel)
  • ML20217M658  + (Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from Heu to LEU Fuel)
  • ML20091C045  + (Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Univ of Florida Training Reactor Conversion from HEU to LEU Fuel)
  • ML20033G615  + (Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Univ of Florida Training Conversion High to Low Enriched U Fuel)
  • ML20035B842  + (Updated Proposal Submitted to Nuclear Regulatory Commission to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel)
  • ML18223A005  + (Updated Proposed License Condition Regarding License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components)
  • ML20245H033  + (Updated Proposed Tech Spec Page 5-5 Re Spent Fuel Storage Capacity)
  • ML20052G192  + (Updated Proposed Tech Spec Pages,Incorporating All Recent License Amends & NRC Requests Re Single Loop Operation)
  • ML18058B830  + (Updated Proposed Tech Specs Pages Re Shutdown Cooling)
  • ML20210A705  + (Updated Proposed Tech Specs Re Steam Generator Plugging Limit to Include Plugging of Tubes W/Defects Greater than Distance of 1.25 Inches Below Top of Tubesheet)
  • ML20009C836  + (Updated QA Manual for Transport of Radioactive Matls)
  • ML17331A312  + (Updated QA Program Description for Cook Nuclear Plant)
  • ML17332A893  + (Updated QA Program Description for Cook Nuclear Plant)
  • ML17334B400  + (Updated QA Program Description for Cook Nuclear Plant)
  • ML17328A662  + (Updated QA Program Description for Cook Nuclear Plant)
  • ML17329A470  + (Updated QA Program Description for Cook Nuclear Plant)
  • ML17328A072  + (Updated QA Program Description for Cook Nuclear Plant Jul 1989)
  • ML17334B511  + (Updated QA Program Description for DC Cook Nuclear Plant)
  • ML20217J470  + (Updated QA Program Description for DC Cook Nuclear Power Plant)
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