Preoperational Testing of Redundant on Site Electric Power Systems to Verify Proper Load Group Assignments
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RA-16-0021, License Amendment Request Proposing an Updated Final Safety Analysis Report Revision to Reflect Electrical Power Systems Alignments for Shared Systems
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 14, Initial Test Program
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
L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 8, Electrical Systems
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 14.2, Table 14.2-1, Tests Performed Prior to Initial Reactor Fueling
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
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 10.3 Through Section 15.1
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figure 7.6.5-1 (Sheet 1 of 2) Through Figure 8.3.1-1 (Sheet 4 of 34)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 8, Electric Power
NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 14
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 14.0 - Initial Test Program
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 8.0 - Electric Power
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 8.0 - Electric Power
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
RAIO-0318-59292, LLC - Response to NRC Request for Additional Information No. 354 (Erai No. 9359) on the NuScale Design Certification Application
AECM-82-107, Responds to NRC & Submits Addl Info Re Reactor Core Isolation Cooling (RCIC) Testing.Util Proposed Three Expanded RCIC Tests & Two Addl Tests Be Performed in Lieu of Proposed Loss of Ac Power Test
B12015, Forwards Changes to Initial Test Program,Per License Condition 2.C(10).Requirement for Reactor Trip Test at 50% Plateau & Ref to pseudo-ejected Rod Test Deleted & Note to Test 25 Added.Changes Will Be Included in FSAR Amend
B11111, Forwards Response to Draft SER Open Items
B10909, Forwards Remaining Responses & Corresponding FSAR Changes to 640 Series Questions Not Forwarded by Util . Responses Will Be Formally Submitted Along W/Amend 5 by 831101
NPL-94-0264, Provides Addendum to TS Change Request 166 Re Mod to TSs 15.3.1, LCO, 15.3.14, Fire Protection Sys, 15.3.7, Auxiliary Electrical Sys & 15.4.6, Emergency Power Sys Periodic Tests, Per 940607 Meeting W/Nrc
TXX-6745, Forwards Revised Environ Qualification Program,Addressing Mild Environs for Plant
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
LD-91-067, Forwards Response to NRC 910729 Request for Addl Info Re Engineering SSAR - Design Certification Covering IEEE Stds, Offsite Power Sys,Control Room Indication of Emergency Diesel Generator Operational Status & Dc Power Sys