ONS-2017-019, Technical Specification Bases Change 2015-09
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 NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05
ONS-2014-020, License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement, LAR No. 2013-05
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.
RS-11-136, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.1
NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
ONS-2014-020, Oconee, Units 1, 2 and 3 - License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement,
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
L-PI-10-052, License Amendment Request to Use Beacon Power Distribution Monitoring System
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
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
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
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
CP-200800411, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses
CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report
L-07-010, License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion, Draft Amendment and Safety Evaluation Comments
ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
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
DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation
RA-18-0282, Technical Specification Bases Changes
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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
ND-19-0168, Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification Revision (LAR-19-001)
ET 09-0019, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
NL-04-2205, Changes to Technical Specification Bases
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
NL-03-2266, Follow-Up Written Request for Notice of Enforcement Discretion and Request to Revise Technical Specification Surveillance Requirements 3.3.1.5 and 3.3.3.2, on an Exigent Basis
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
ULNRC-03926, Forwards Addl Info or Supporting Documentation Not Provided in Original RAI Responses,Answers to follow-up Questions & Addl Changes Identified by Licensee for ITS Sections 1.0, 3.4,3.5,3.6,3.7 & 3.9
ULNRC-06702, Enclosureplacement Version of Attachment 3 to ULNRC-06688, Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505
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 .
NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System
3F1007-03, License Amendment Request 296, Revision 2: Measurement Uncertainty Recapture Response to Request for Additional Information
L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption
NSD-NRC-97-5231, Forwards Formal Transmittal of Correspondence Previously Sent Over Period 970515-970605.W/index
3F0595-01, Application for Amend to License DPR-72,revising TSs to Allow Continuous Operation for Up to 24 Month Period
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.)
CP-202000575, (CPNPP) - Exigent License Amendment Request (LAR) 20-007 Revision to Technical Specification (TS) 3.7.8, Station Service Water System and TS 3.8.1, AC Sources - Operating
3F1195-25, Submits Discussion in Response to Concerns Re Proposed TS Change Request to Extend Most Refueling Interval Surveillances to 24 Months.Revised Copies of Instrument Drift Studies Included in Original Submittal Attached Also
NL-03-2067, Request to Revise Surveillance Requirements 3.3.1.2 and 3.3.1.3
L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization
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
NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
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
DCL-12-002, Revision to the Updated Final Safety Analysis Report Section 4.3.2.2, Power Distribution; and Technical Specification Bases 3.1.7, Rod Position Indication; 3.2.1, Heat Flux Hot Channel Factor (Fo(Z)),3.2.2,.
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
AEP-NRC-2009-45, License Amendment Request for One-Time Extension of Technical Specification Completion Times for Inoperable Train of Reactor Trip System and Engineered Safety Feature Actuation System
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
ET 06-0002, Revision to Technical Specification (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation
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-21-0042, Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System
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
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program