RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)
RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
TSTF-13-05, Transmittal of TSTF-536, Revision 0, Resolve CE Digital TS Inconsistencies Regarding CPCs and Ceacs
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)
L-07-010, License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion, Draft Amendment and Safety Evaluation Comments
NRC 2006-0033, License Amendment Request 245; Technical Specification 3.3.4, Loss of Power Diesel Generator Start Instrumentation
JAFP-01-0133, ITS: 3.3.4.1 Anticipated Transient Without Scram Recirulation Pump Trip (ATWS-RPT) Instrumentation
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
RAIO-0219-64635, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
JAFP-02-0124, Revision K to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications
RBG-46325, License Amendment Request, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
NSD-NRC-97-5133, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period 970416-0502,including Draft of SSAR Markup for LOOP Issue & Open Item Status
NUREG-1434, Forwards Changes Collected by NRC Since Publication of Rev 0 to Sts.Changes Considered Minor & Included Under One Traveler
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
PNP 2024-027, Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations
ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
RAIO-0419-65262, LLC - Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
RAIO-0119-64281, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
RAIO-0519-65603, LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
RAIO-0318-59200, LLC Supplemental Response to NRC Request for Additional Information No. 228 (Erai No. 9034) on the NuScale Design Certification Application
05000425/LER-2011-001, Regarding Inoperable Core Exit Thermocouple Indicator on the B Train Remote Shutdown Panel
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program