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A list of all pages that have property "Title" with value "Final Safety Evaluation for GEH QAPD Revision 15 Review". 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

  • 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)
  • ML21286A598  + (Final Safety Evaluation for Framatome Topical Report ANP-10349P, Revision 0, Galileo Implementation in LOCA Methods (EPID L-2020-TOP-0059) (Letter))
  • ML23023A116  + (Final Safety Evaluation for Framatome Topical Report EMF-2310, Revision 1 Supplement 2P, Revision 0, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors (EPID L-2022-TOP-0008) Letter)
  • ML22353A089  + (Final Safety Evaluation for Framatome Topical Report BAW-10227P, Revision 2, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel (EPID L-2019-TOP-0054) - Letter)
  • ML23058A118  + (Final Safety Evaluation for Framatome Topical Report ANP-10311P, Revision 1, Supplement 1P, Revision 0, Cobra Flx: Orfeo-HMP Critical Heat Flux Correlation - Letter)
  • ML23233A139  + (Final Safety Evaluation for Framatome Topical Report Anp 10339P, Revision 0, Arita - Artemis/Relap Integrated Transient Analysis Methodology (EPID L 2018-TOP-0034) Letter)
  • ML23053A053  + (Final Safety Evaluation for Framatome Topical Report ANP-10353P, Revision 0, Increased Enrichment for PWRs (Letter))
  • ML23299A232  + (Final Safety Evaluation for Framatome Topical Report, ANP-10339P, Revision 0, Arita - Artemis/Relap Integrated Transient Analysis Methodology - Non-Proprietary)
  • ML19052A572  + (Final Safety Evaluation for Framatome, Inc. Topical Report ANP-10332P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios (Non-Proprietary Version))
  • ML20350B363  + (Final Safety Evaluation for GE-Hitachi Nuclear Energy, Proposed Revision 16 to Topical Report, NEDO-11209A, Revision 15, GE-Hitachi Nuclear Energy Quality Assurance Program Description)
  • ML20140A322  + (Final Safety Evaluation for GE-Hitachi Nuclear Energy (GEH) Topical Report, NEDO-11209A, Quality Assurance Program Description (QAPD) Review)
  • ML19232A085  + (Final Safety Evaluation for Global Nuclear Fuel - Americas, LLC, Proposed Amendment 47 to NEDE-24011-P-A-27, General Electric Standard Application for Reactor Fuel (Gestarii) Supporting Implementation of TSTF-564)
  • ML17332A296  + (Final Safety Evaluation for Global Nuclear Fuel - Americas, LLC, Proposed Amendment 44 to NEDE-24011-P-A-24)
  • ML18204A025  + (Final Safety Evaluation for Global Nuclear Fuel - Americas, LLC, Proposed Amendment 43 to NEDE-24011-P-A-23, General Electric Standard Application for Reactor Fuel (Gestarii) Section 3.4)
  • ML19199A053  + (Final Safety Evaluation for Global Nuclear Fuel - Americas, LLC, Proposed Amendment 48 to Nede-24011-P-A-26,- General Electric Standard Application for Reactor Fuel (Gestarii) - EPID L-2018-TOP-0040))
  • ML20023A285  + (Final Safety Evaluation for Global Nuclear Fuel - Americas, LLC (Gnf) Licensing Topical Report Nede 33885P, Revision 0, Gnf Control Rod Drop Accident Application Methodology)
  • ML23234A158  + (Final Safety Evaluation for Hi-2210161, Revision No. 4, Topical Report on the Radiological Fuel Qualification Methodology for Dry Storage Systems)
  • ML21125A186  + (Final Safety Evaluation for Holtec International Topical Report HI-2200343 Revision 2, Topical Report for Allowance of Heat Load Patterns in HI-STORM 100 and Hi STORM FW Systems)
  • ML23048A326  + (Final Safety Evaluation for Kairos Fuel Qualification TR)
  • ML18129A024  + (Final Safety Evaluation for Licensing Topical Report Nede 33005P-A / NEDO-33005-A, Tracg Application for Emergency Core Cooling Systems / Loss-Of-Coolant-Accident Analysis for BWR/2-6 Satisfaction of Limitation 10.7)
  • ML19072A113  + (Final Safety Evaluation for Licensing Topical Report, NEDC-33353P, Licensing Topical Report Application of Gnf Ziron to Gnf Fuel Designs)
  • ML24305A007  + (Final Safety Evaluation for MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline)
  • ML18257A014  + (Final Safety Evaluation for Mitsubishi Electric Total Advanced Controlled Platform Topical Report and Supporting Documents (CAC No. MF4228, EPID L-2014-Top-0006) (Non-Proprietary))
  • ML19199A182  + (Final Safety Evaluation for NEDC-33173P Supplement 6 - Applicability of GE Methods to Expanded Operating Domains - Removal of the Safety Limit Minimum Critical Power Raito (SLMCPR) Penalty)
  • ML091130034  + (Final Safety Evaluation for NEI 07-08, Generic FSAR Template for ALARA)
  • ML083530745  + (Final Safety Evaluation for NEI 07-09, Revision 4, Generic Final Safety Analysis Report Template Guidance for Offsite Dose Calculation Manual (ODCM) Program Description)
  • ML24011A001  + (Final Safety Evaluation for NEI 16-03 Rev.1)
  • ML100770137  + (Final Safety Evaluation for NEI Topical Report WCAP-16294-NP, Rev. 0, Risk-informed Evaluation of Changes to Technical Specification Required Endstates for Westinghouse NSSS (Nuclear Steam Supply System) Pwrs (Pressurized Water Reactors,) a)
  • ML20027A082  + (Final Safety Evaluation for NuScale Power, LLC (Public and NON-Public Versions))
  • ML18338A031  + (Final Safety Evaluation for NuScale Power, TR-0915-17564-P, Subchannel Analyses Methodology, Revision 2)
  • ML25094A096  + (Final Safety Evaluation for NuScale TR-0716-50350-P, Revision 3, Rod Ejection Accident Methodology (Public))
  • ML062700012  + (Final Safety Evaluation for Nuclear Energy Institute (NEI) Industry Guidance Document NEI 04-10, Revision 0, Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies)
  • ML090510379  + (Final Safety Evaluation for Nuclear Energy Institute Topical Report NEI 07-03, Generic Final Safety Analysis Report Template Guidance for Radiation Protection Program Description, Revision 7)
  • ML092720253  + (Final Safety Evaluation for Nuclear Energy Institute Topical Report NEI 08-08, Generic Final Safety Analysis Report (FSAR) Template Guidance for Life-Cycle Minimization of Contamination, Revision 3 (Project No. 689))
  • ML16354A486  + (Final Safety Evaluation for Nuclear Energy Institute Topical Report NEI 16-03 - Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools)
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