LR-N15-0078, Annual Radioactive Effluent Release Report
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, List of Current Pages and Master Table of Contents
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, List of Current Pages
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3.7.B.2-27 Through 3D-17
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, List of Effective Pages
L-08-231, Updated Final Safety Analysis Report, Rev. 17, List of Effective Pages
WM 08-0003, Updated Safety Analysis Report (Usar), Revision 21, Chapter 1.0, List of Effective Pages
L-2008-061, Annual Radioactive Effluent Release Report for Period of January 1, 2007 Through December 31, 2007
RBG-47895, Supplement to the Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)
RAIO-0218-58804, LLC - Response to NRC Request for Additional Information No. 137 (Erai No. 8973) on the NuScale Design Certification Application
ULNRC-03913, Forwards Rev OL-10 to Callaway Plant FSAR Std Plant & Site Addendum, Per Requirements of 10CFR50.4(b)(6)
ET-NRC-92-3789, Forwards Westinghouse Response to NRC 920923,1001,09 & 28 Requests for Addl Info on AP600
RBG-37400, Forwards Rev 5 to River Bend Station Updated Sar. Rev Covers Period 910301-920301
PY-CEI-NRR-0010, Forwards Draft FSAR Pages for App 3A & 3B.Change Provides Description of Safety Relief Valve & LOCA-related Hydrodynamic Load Definition for Mark III Containment Re SER Outstanding Issue 9, Pool Dynamic Loads
RBG-33450, Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-900301
RAIO-0318-59255, LLC Supplemental Response to NRC Request for Additional Information No. 151 (Erai No. 8974) on the NuScale Design Certification Application
RAIO-0419-65223, LLC Supplemental Response to NRC Request for Additional Information No. 201 (Erai No. 8975) on the NuScale Design Certification Application
RBG-45940, License Amendment Request (LAR) 2001-43, High Energy Line Break Analysis Method
RAIO-1218-63955, LLC Response to NRC Request for Additional Information No. 132 (Erai No. 8971) on the NuScale Design Certification Application
NSD-NRC-96-4873, Forwards Responses to Open Items to leak-before-break Open Items,Dser Section 3.6.4.Westinghouse Needs Info from NRC Evaluation of Waterhammer Loads