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List of results

• ML19099A312  + (Design Certification Testing Inspection of Nuscale Power, LLC, Emergency Core Cooling System Valve Design Demonstration Testing)
• ENS 54864  + (Design Change Altered Basis for ITAAC)
• ML21139A044  + (Design Change Form C-DCF-G-00397)
• ML21139A043  + (Design Change Form C-DCF-G-00400)
• 05000293/FIN-2016011-06  + (Design Change Not Appropriately Reviewed by Entergy)
• ML20343A375  + (Design Change Notice No. 028 - Revised Wedge Design)
• ML050060114  + (Design Change Package 80062466 Revision 3 Extended Power Uprate Piping Vibration Monitoring, Installation Package, 12/23/2004)
• ML050060110  + (Design Change Package 80062466 Revision 2 Extended Power Uprate Piping Vibration Monitoring Installation Package, 12/10/2004)
• ML050060054  + (Design Change Package 80062466 Revision 1 Extended Power Uprate Piping Vibration Monitoring Installation Package, 10/19/2004)
• 05000298/FIN-2012003-06  + (Design Changes Not Appropriately Approved by the Licensee)
• ML16204A232  + (Design Changes Proposed by Asea Brown Boveri - Combustion Engineering Relating to the Certification of the System 80+ Design)
• ML16204A245  + (Design Changes Proposed by Generic Electric Nuclear Energy Relating to the Certification of the U.S. Advanced Boiling Water Reactor Design)
• ML19321B094  + (Design Charts for Class of Nonlinear Sys W/Gaps Under Variety of Dynamic Loads)
• ML17258A424  + (Design Codes,Design Criteria & Loading Combinations, Technical Evaluation Rept)
• ML13333B111  + (Design Codes,Design Criteria & Loading Combinations (SEP,III-7B), Technical Evaluation Rept)
• ML20052H228  + (Design Codes,Design Criteria & Loading Combinations,Sep Topic III-7.B, Technical Evaluation Rept)
• ML20077J930  + (Design Codes,Design Criteria & Loading Combinations (SEP, III-7.B),RE Ginna Nuclear Power Plant, Final Technical Evaluation Rept)
• ML20052B581  + (Design Codes,Design Criteria, & Loading Combinations (SEP III-7.B) Jersey Central Power & Light Co,Oyster Creek Nuclear Generating Station, Technical Evaluation Rept)
• ML20054E276  + (Design Concept and Testing of an IN-BUNDLE Gamma Densitometer for Subchannel Void Fraction Measurements in the Thtf Electrically Heated Rod Bundle)
• ML19345D195  + (Design Concepts for Independent Central Alarm Station and Secondary Alarm Station Intrusion Detection Systems)
• Regulatory Guide 5.42  + (Design Consideration for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Dry Process Operations)
• ML20081J400  + (Design Considerations for LONG-TERM Stabilization of Uranium Mill Tailings Impoundments)
• Regulatory Guide 5.8  + (Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Drying and Fluidized Bed Operations)
• Regulatory Guide 5.25  + (Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Wet Process Operations)
• Regulatory Guide 6.3  + (Design Construction, and Use of Radioisotopic Power Generators for Certain Land and Sea Applications)

• 10 CFR 50 Appendix B Criterion III, Design Control  + (Design Control)

• 05000341/FIN-2011002-02  + (Design Control Measures Failed to Ensure Adequacy of the Design Relating to the Reactor Building Crane Support Structure and Reactor Building Superstructure)
• 05000282/FIN-2015002-04  + (Design Control Measures not Implemented to Ensure Group E Pressurizer Heaters Remain Operational Post-Fire)
• 05000327/FIN-2014007-03  + (Design Control Requirements not met During Safety-Related Circuit Breaker Replacements)
• ML19260C534  + (Design Criteria & Conceptual Design Descriptions for Technical Support Ctr. Leak Rate Test Results Encl)
• ML19344D667  + (Design Criteria & Conceptual Design Description for Technical Support Ctrs for Facilities)
• ML19326D859  + (Design Criteria & Description,Technical Support Ctr)
• ML19309G498  + (Design Criteria & Test Rept Stress Evaluation of AFL-GE Package Dwg. 908E615 Revison 1, Model 9136)
• ML20079C343  + (Design Criteria BFN-50-C-7100,Attachment F, Browns Ferry Nuclear Plant Detailed Design Criteria for Structrual & Miscellaneous Steel/Components for Class I & II Structures)
• ML102240383  + (Design Criteria Document No. WB-DC-30-29, Revision 8, Plant Integrated Computer System (ICS) Dated August 10, 2009, Enclosure 1)
• ML17261B020  + (Design Criteria Ginna Station Steam Generator Containment Penetration)
• ML19345F592  + (Design Criteria for Effluent Monitoring,Sampling & Analysis)
• ML19350E617  + (Design Criteria for Hot Chemical Lab)
• ML20064C280  + (Design Criteria for Hydrogen Ignitor Sys, Rev 0)
• ML19331C834  + (Design Criteria for Interim Solid Waste Staging Facility for Gpu Corp,TMI-2)
• ML20092A679  + (Design Criteria for Lifting Sys for TN-40 Dry Storage Cask at Praire Island)
• ML20248B538  + (Design Criteria for Masonry Wall Evaluation. W/Two Oversize Drawings)
• ML18041A104  + (Design Criteria for Reanalysis of Safety-Related Masonry Walls,Nine Mile Point Unit 1)
• ML19330A090  + (Design Criteria for Reinforced Concrete Block Walls)
• ML20059H958  + (Design Criteria for Soil-Structure Interaction Analysis of Reactor/Containment Bldg at Gpun Oyster Creek Nuclear Generating Station)
• ML19256A357  + (Design Criteria for Vault Automation in SNM Storage)
• ML20008F821  + (Design Criteria for the Nuclear Data Link Communication Subsystem)
• ML20054A583  + (Design Criteria for the Spacing of Nozzles and Reinforced Openings in Cylindrical Nuclear Pressure Vessels and Pipe)
• ML20054D457  + (Design Criteria for the Spacing of Nozzles and Reinforced Openings in Cylindrical Nuclear Pressure Vessels and Pipe)
• ML17139D083  + (Design Criteria,500 Kv Steel Pole Structure Transmission Lines)
• ML17249A603  + (Design Criteria,Spent Fuel Cooling Sys, Revision 1)