NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Effective Page Listing, Table of Contents, Chapter 1 Redacted, Introduction and General Description of the Plant
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 15.4, Condition Iv - Limiting Faults
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 15.3, Condition Iii - Infrequent Faults
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 15.2, Condition Ii - Faults of Moderate Frequency
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 15, Accident Analysis - Classification of Plant Conditions
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
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
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 15.0 - Accident Analyses, Pages 15.4-1 - 15A-6
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 15.0 - Accident Analyses, Pages 15-i - 15.3-76
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 1.0 - Introduction and General Description of Plant
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis
TXX-3230, Forwards Initial Responses to Instrumentation & Control Sys Branch Second Round questions,Q032.75-Q032.1102.Responses Will Be Retransmitted in Amend 13 to FSAR
L-2004-193, Proposed License Amendment Request for Additional Information Response WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit
ST-HL-AE-2683, Forwards Annotated Revs to FSAR Re Redesign of Unit Initial Core to Accomodate Revised Cycle Length of Approx 400 Efpds. Westinghouse Evaluation Concluded That LOCA Analysis Unaffected by Change
ST-HL-AE-1398, Forwards marked-up FSAR Pages in Response to Draft SER Open Item 15.4-2 Re Dropped Rod Analysis.Response Will Be Incorporated in Future FSAR Amend
NRC-95-4519, Forwards Preliminary Marked Up Radiological Sections of Chapter 15 of AP600 SSAR
A01085, Forwards Nonproprietary Response to Questions on Cycle 4 Basic Safety Rept
B10028, Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790)