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A list of all pages that have property "Title" with value "Final Safety Evaluation for Amendment No. 174". 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

  • ML21258A020  + (Final Safety Evaluation Report for Renewal of Initial Certificate and Amds. 1, 3, and 4 of CoC No 1029)
  • ML20267A654  + (Final Safety Evaluation Report for Topical Report, Framatome Topical Report ANP-10337, Revision 0, Supplement 1P, Revision 0, Deformable Spacer Grid Element)
  • ML20231A804  + (Final Safety Evaluation Report for the NuScale Standard Plant Design)
  • ML21354A195  + (Final Safety Evaluation Report for the Subsequent License Renewal Application Review (EPID No. L-2020-SLR-0000) - Issuance Letter)
  • ML21354A196  + (Final Safety Evaluation Report for the Subsequent License Renewal Application Review (EPID No. L 2020 SLR 0000) - SER)
  • ML20052F523  + (Final Safety Evaluation Report for the Subsequent License Renewal Application Review for Surry Power Station, Units 1 and 2)
  • ML23293A300  + (Final Safety Evaluation Report for the Standardized Nuhoms Horizontal Modular Storage System for Irradiated Nuclear Fuel)
  • ML21354A174  + (Final Safety Evaluation Report for the Subsequent License Renewal Application Review)
  • ML20052F521  + (Final Safety Evaluation Report for the Subsequent License Renewal Application Review)
  • ML23075A183  + (Final Safety Evaluation Report, Issuance of Materials License No. SNM-2516 for the HI-STORE Consolidated Interim Storage Facility ISFSI - Public)
  • ML092890209  + (Final Safety Evaluation Report, Related to the License Renewal of Prairie Island Nuclear Generating Plant, Units 1 and 2)
  • ML20226A080  + (Final Safety Evaluation Report, Renewed CoC No.1004, Amendment 16, Model No. Standardized NUHOMS Horizontal Storage Module (Hsm), Docket No. 72-1004)
  • ML19322A008  + (Final Safety Evaluation Transmittal Email WCAP-16097, Revision 4, Common Qualified Platform Topical Report)
  • ML21154A132  + (Final Safety Evaluation Transmittal Email)
  • ML23205A074  + (Final Safety Evaluation WCAP-17096, Revision 3)
  • ML19345F015  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation for the Pressurized Water Reactor Owners Group Topical Report PWROG-17090-NP, Revision 0, Generic Rotterdam Forging and Weld Initial Upper-Shelf Energy Determination)
  • ML24011A002  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation for the Nuclear Energy Institute Topical Report NEI 16-03, Revision 1, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools Project No. 689; Docket No. 99)
  • ML101660468  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report Materials Reliability Program (Mrp): Technical Basis for Preemptive Weld Overlays for Alloy 82/182 Butt Welds in Pwrs (MRP-169))
  • ML11098A049  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation, Topical Report NEDO-33349, Revision 1, ABWR Application to RG 1.97, Revision 4, Boiling Water Reactor Owners Group Project No. 691.Final Safety Evaluation by the Office of)
  • ML23123A088  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation for the Pressurized Water Reactor Owners Group - Topical Report WCAP-17096-NP, Revision 3, Reactor Internals Acceptance Criteria Methodology and Date Requirements)
  • ML20134M356  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report PWROG-18034-P, Revision 0, Updates to the Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bolting Distributions Under Faulted Load Condi)
  • ML19301D160  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation for Pressurized Water Reactor Owners Group Topical Report PWROG-15109-NP, Revision 0, PWR Pressure Vessel Nozzle Appendix G Evaluation EPID L-2018-TOP-0009)
  • ML19010A274  + (Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority)
  • ML18149A567  + (Final Safety Evaluation for ANP-10335P, Revision 0, Ace/Atrium 11 Critical Power Correlation (Non-Proprietary Version))
  • ML19267A051  + (Final Safety Evaluation for Amendment 49 to Topical Report NEDE-24011-P-A-27 Gestar II)
  • ML081230640  + (Final Safety Evaluation for Amendment No. 174)
  • ML18124A223  + (Final Safety Evaluation for Areva Inc. Topical Report ANP-10300P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios (Non-Proprietary Version))
  • ML18124A214  + (Final Safety Evaluation for Areva Inc. Topical Report ANP-10300P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios)
  • ML20106F242  + (Final Safety Evaluation for Argonne National Laboratory Quality Assurance Program Plan for Sodium Fast Reactor Metallic Fuel Data Qualification (CAC 001226))
  • ML070180483  + (Final Safety Evaluation for BWROG, Structural Integrity Associates Topical Report SIR-05-044, Pressure Temperature Report Methodology for Boiling Water Reactors)
  • ML23037A987  + (Final Safety Evaluation for Bechtel Quality Assurance Program for Nuclear Power Plants Topical Report, BQ-TOP-1, Revision 004)
  • ML23037A980  + (Final Safety Evaluation for Bechtel Quality Assurance Program for Nuclear Power Plants Topical Report, BQ-TOP-1, Revision 004)
  • ML16351A176  + (Final Safety Evaluation for Boiling Water Reactor Owners Group Topical Report NEDC-33347P/NEDO-33347, Revision 1, Containment Overpressure Credit for Net Positive Suction Head (NPSH))
  • ML13107A062  + (Final Safety Evaluation for Boiling Water Reactor Owners Group Topical Report BWROG-TP-11-022, Rev. 1, November 2011, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors)
  • ML13056A157  + (Final Safety Evaluation for Boiling Water Reactors Owners Group Topical Report BWROP-TP-11-023, Revision 0, November 2011, Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles)
  • ML11098A018  + (Final Safety Evaluation for Boiling Water Reactors Owners Group Topical Report NEDO-33349,Revision 1, BWR Application to RG 1.97, Revision 4)
  • ML19189A111  + (Final Safety Evaluation for EPRI Topical Reports 3002010613 and 3002010614)
  • ML19081A001  + (Final Safety Evaluation for Electric Power Research Institute Topical Report MRP-227, Revision 1, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline)
  • ML25234A193  + (Final Safety Evaluation for Electric Power Research Institute Report 3002028939, Risk-informed High-Energy Line Break Evaluation Requirements)
  • ML19276E436  + (Final Safety Evaluation for Framatome Inc. Topical Report ANP-10346, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA (Non-Proprietary Version))
  • ML19141A186  + (Final Safety Evaluation for Framatome Inc., Topical Report BAW-10227, Revision 1, Supplement 1P, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel)
  • ML18236A426  + (Final Safety Evaluation for Framatome Inc. Topical Report ANP-10341P, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations (Non-Proprietary))
  • ML20304A653  + (Final Safety Evaluation for Framatome Inc. Topical Report ANP-10323P, Revision 1, Galileo Fuel Rod Thermal-Mechanical Methodology for Pressurized Water Reactor (EPID L-2013-TOP-0003)(Letter))
  • ML19276E475  + (Final Safety Evaluation for Framatome Inc. Topical Report ANP-10346, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA (Non-Prop Version))
  • ML18120A354  + (Final Safety Evaluation for Framatome Inc. Topical Report ANP-10335P, Revision 0, Ace/Atrium 11 Critical Power Correlation)
  • ML19204A048  + (Final Safety Evaluation for Framatome Inc. Topical Report ANP-10342P, Revision 0, Gaia Fuel Assembly Mechanical Design)
  • ML19149A479  + (Final Safety Evaluation for Framatome Inc. Topical Report EMF-93-177, Revision 1, Supplement 2P, Revision 1, Mechanical Design for BWR Fuel Channels: Z4B Material)
  • EPID:L-2018-TOP-0029  + (Final Safety Evaluation for Framatome Inc. Topical Report EMF-93-177, Revision 1, Supplement 2P, Revision 1, Mechanical Design for BWR Fuel Channels: Z4B Material)
  • ML23275A043  + (Final Safety Evaluation for Framatome Topical Report ANP-10340P-A, Revision 0, Supplement 1, Revision 0, Incorporation of Chromia-Doped Fuel Properties in Framatome PWR Methods (EPID L-2021-TOP-0015) (Enclosure 2) (Nonproprietary))
  • ML23180A143  + (Final Safety Evaluation for Framatome Topical Report ANP-1034P, Revision 0, Supplement 1, Revision 0, Incorporation of Chromia-Doped Fuel Properties in Framatome PWR Methods (EPID L-2021-TOP-0015) (Letter))
  • ML23299A240  + (Final Safety Evaluation for Framatome Topical Report, ANP-10339P, Revision 0, Arita - Artemis/Relap Integrated Transient Analysis Methodology (Appendix IV) - Non-Proprietary)
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