Design Limits and Loading Combinations for Metal Primary Reactor Containment Systems Components
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LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Sections 3.6 Through 3.11
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
RS-16-248, Byron/Braidwood Nuclear Stations, Submittal of Revision 16 to Updated Final Safety Analysis Report and Updated Fire Protection Report (Fpr), Amendment 27
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3.7.B.2-27 Through 3D-17
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and Systems
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
ST-HL-AE-2093, Forwards Revised FSAR Section 3.12, Conformance W/Nrc Reg Guides. Section Updated to Reflect Util Position on All Applicable Reg Guides
ST-HL-AE-1447, Forwards Response to Draft SER or FSAR Item F 3.8-2 Re Identification of Codes,Stds & Specs Applicable to Design. Changes Will Be Incorporated in Future FSAR Amend
TXX-8833, Responds to NRC Re Open Items Noted in Insp Repts 50-445/87-37 & 50-446/87-28.Results of Engineering Functional Evaluation of Items Identified in Ci Grimes 880208 & s Scheduled for Completion in May 1988
05000254/LER-1993-013-04, :on 930729,identified Deviation from TS & Reg Guide 1.52 Requirements for Methyl Iodide Testing of Charcoal Sample Canisters.Caused by Failure to Implement Proper Canister Testing.Canisters Tested by Nucon
RAIO-0918-61923, LLC Response to NRC Request for Additional Information No. 433 (Erai No. 9474) on the NuScale Design Certification Application