L-2011-190, WCAP-17070-NP, Revision 1, Westinghouse Setpoint Methodology for Protection Systems, Turkey Point, Units 3 & 4 (Power Uprate to 2644 Mwt - Core Power), Attachment 2 to L-2011-190
NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 4 Through Chapter 5
RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 4, Reactor
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4.1 to 4.4-66d
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions
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 4.0 - Reactor, Pages 4-i - 4.4-52
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 3 - Reactor
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 4.0 - Reactor
CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)
L-05-149, Response to Request for Additional Information in Support of LAR Nos. 327 and 197 Steam Generator Level Allowable Value Setpoints
DCL-03-011, License Amendment Request 03-01, Revision to TS 3.3.1, Reactor Trip System Instrumentation
NRC 2002-0030, License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate
NOC-AE-02001259, Additional Information to Support Request for Approval of Power Uprate & Revision to Technical Specifications
L-96-158, Rev 2 to Jm Farley Nuclear Plant Units 1 & 2 Licensing Rept for TS Changes Associated W/Revised Core Limits,Revised Trip Setpoints & Inclusion of RAOC Control Strategy
NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.
L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation
L-95-250, Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint
L-91-429, DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation
DCL-15-047, License Amendment Request 15-02 Revision of Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and Technical Specification 5.6.5. Core Operating Limits Report (Colr), For.
DCL-13-016, Attachment 5 to DCL-13-016 - WCAP-17706-NP, Revision 0, Westinghouse Setpoint Methodology as Applied to the Diablo Canyon Power Plant
NRC-2002-0094, Supplement to License Amendment Request 226, Measurement Uncertainty Recapture (MUR) Power Uprate