AEP-NRC-2012-93, Response to NRC Bulletin 2012-01, Design Vulnerability in Electric Power System
L-2018-054, Turkey Point, Units 3 and 4 - 2017 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-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Appendices 3A Through 3I
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
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the Plant
RS-14-029, Braidwood Station, 2011 Benthos Monitoring and Historical Fish and Benthos Comparisons
LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
L-08-231, Updated Final Safety Analysis Report, Rev. 17, List of Effective Pages
LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
WM 08-0003, Updated Safety Analysis Report (Usar), Revision 21, Chapter 1.0, List of Effective Pages
LR-N08-0096, 2007 Radioactive Effluent Release Report for January 1, 2007 to December 31, 2007
L-2008-061, Annual Radioactive Effluent Release Report for Period of January 1, 2007 Through December 31, 2007
RAIO-0118-58468, LLC Response to NRC Request for Additional Information No. 128 (Erai No. 8966) on the NuScale Design Certification Application
RAIO-0218-58804, LLC - Response to NRC Request for Additional Information No. 137 (Erai No. 8973) on the NuScale Design Certification Application
LR-N04-0117, Stations, Radioactive Effluent Release Report
L-2003-077, Annual Radioactive Effluent Release Report
LIC-02-0120, Attachment 2, Pump and Value Inservice Testing Program Plan, Fourth Ten-Year Interval, Rev 0
RBG-37400, Forwards Rev 5 to River Bend Station Updated Sar. Rev Covers Period 910301-920301
TXX-5006, Forwards Revised FSAR Pages Scheduled for Future FSAR Amend. Changes Resulted from Requalification of Class 2 & 3 Piping & Class 1,2 & 3 Pipe Supports
PY-CEI-NRR-0336, Clarifies & Resolves NRC Concerns Re Design for LOCA-related Hydrodynamic Loads (SER Open Item 9).Draft Acceptance Criteria for Mods to Pool Dynamic Load Design, Info Re Submerged Drag Loads & Proposed Revs to FSAR Encl
PY-CEI-NRR-0351, Provides Further Info Re Pool Dynamic Loads (SER Open Item 9).Sufficient Design Margin Exists Between Original Design Basis Pressure & Impact Pressure as Calculated by Modified Methodology
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
RAIO-0519-65641, LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application
L-92-100, 1991 Annual Radiological Environ Operating Rept
RAIO-1118-63624, LLC Response to NRC Request for Additional Information No. 164 (Erai No. 8935) on the Nuscale Design Certification Application
RAIO-1217-57887, LLC Response to NRC Request for Additional Information No. 237 (Erai No. 9002) 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