ONS-2017-019, Technical Specification Bases Change 2015-09
ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change
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 NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements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
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
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-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
2CAN070902, Response to Request for Additional Information for the Technical Specification Change to Modify RCS Flow Verification
2CAN060901, Response to Request for Additional Information for the Technical Specification Change to Modify RCS Flow Verification
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
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
CNL-18-104, Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals
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
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
NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
RAIO-0719-66473, LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application
RAIO-0219-64635, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
ND-19-0168, Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification Revision (LAR-19-001)
ND-18-0067, Request for License Amendment: Fuel Management Related Technical Specifications (LAR-18-005)
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
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
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
DCL-02-125, License Amendment Request 02-06 Revisions to Technical Specifications 3.3.1 Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ULNRC-04721, Technical Specification Bases Revision 3
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
NSD-NRC-97-5231, Forwards Formal Transmittal of Correspondence Previously Sent Over Period 970515-970605.W/index
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 .
L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response
NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System
1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure
1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
3F1007-03, License Amendment Request 296, Revision 2: Measurement Uncertainty Recapture Response to Request for Additional Information
DCL-03-011, License Amendment Request 03-01, Revision to TS 3.3.1, Reactor Trip System Instrumentation
CNL-18-090, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified Intervals (390-WBN-TS-2018-14)
CNL-19-086, Supplement to Application for License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)
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
RAIO-0718-61158, LLC Response to NRC Request for Additional Information No. 490 (Erai No. 9556) on the NuScale Design Certification Application
CNL-18-102, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified .
05000244/LER-1996-005, :on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs Revised
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
DCL-04-029, Response to NRC RAI Regarding License Amendment Request 02-06, Revisions to Technical Specifications 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) ..
NL-03-154, To the Indian Point, Unit 2, License Amendment Request for Conversion to Improved Standard Technical Specifications
RAIO-1218-63954, LLC Supplemental Response to NRC Request for Additional Information No. 196 (Erai No. 9050) on the NuScale Design Certification Application
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-14-1297, Request for Enforcement Discretion from Technical Specification 3.3.6, Containment Spray and Cooling Systems
CP-202100394, Supplement to License Amendment Request (LAR) 20-006
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-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ
ONS-2015-106, Technical Specification (TS) Bases Change
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases