CNS-16-031, Technical Specification Bases Changes
MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
ULNRC-05975, Revision to TS LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4, 5 and 6 License Amendment Request LDCN 13-0003
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
DCL-12-050, Attachment 2 to DCL-12-050, Final Safety Analysis Report Changes for Process Protection System Replacement
RS-12-048, License Amendment Request to Revise Technical Specifications (TS) 3.3.1,Reactor Trip System (RTS) Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, To.
NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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 1 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8
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
NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
TSTF-10-02, Transmittal of TSTF-521, Revision 0, Exclusion of Time Constants from Channel Operation Tests in Specifications 3.3.1 and 3.3.2
NRC 2010-0022, License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
NL-09-1431, License Amendment Request for Technical Specification Table 3.3.1-1
NL-09-136, Indian Point 3 Nuclear Power Plant 2009 Amendment Update to the Final Safety Analysis Report (Fsar), Revision 03
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
CP-200900492, License Amendment Request (LAR) 09-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
NL-09-0154, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
NL-08-163, (IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 21
NL-08-1519, Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.8
NL-08-1365, Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.8
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
PLA-6254, Proposed License Amendments 285 & 253, Extended Power Uprate Application Regarding Withdrawal of Change to Technical Specification SR 3.3.1.1.8 - Calibration Frequency for Lprms
WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)
NL-05-1381, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 3.b, Power Range Neutron Flux- High Negative Rate
ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project
NL-05-0233, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11. Reactor Coolant Pump Breaker Position
NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
ND-19-0168, Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification Revision (LAR-19-001)
ET 06-0002, Revision to Technical Specification (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation
NL-04-2205, Changes to Technical Specification Bases
BSEP 04-0015, Supplement to Request for License Amendments Regarding Core Flow Operating Range Expansion
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
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
WO 03-0059, Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.)
NL-03-2067, Request to Revise Surveillance Requirements 3.3.1.2 and 3.3.1.3
DCL-03-016, License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation
ULNRC-04721, Technical Specification Bases Revision 3
ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 8
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions
CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .
L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response
RBG-43161, Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power
RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies
RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications
NL-08-1688, Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.8
NSD-NRC-97-5231, Forwards Formal Transmittal of Correspondence Previously Sent Over Period 970515-970605.W/index
RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8
RA-24-0110, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical.
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
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
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
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
CPSES-200600097, Revision to Technical Specifications 3.3.1, Reactor Trip System Instrumentation, 3.3.2, ESFAS Instrumentation, 3.4.5, RCS Loops-Mode 3, 3.4.6, RCS Loops-Mode 4, and 3.4.7, RCS Loops-Mode 5, Loops Filled
NRC 2014-0075, Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
NL-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
CPSES-200701323, License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System
DCL-09-009, License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
DCL-24-118, License Amendment Request 24-06, Revision to Technical Specification 1.1 and Addition of 5.5.21 to Use Online Monitoring Methodology