SR-2D3.3.1
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SR-3.3.1
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ONS-2017-019, Technical Specification Bases Change 2015-09
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CNL-17-026, Application to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (390-WBN-TS-17-04)
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CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)
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ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change
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CNS-16-031, Technical Specification Bases Changes
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CNL-18-012, Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)
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CNL-18-006, Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)
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RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles
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MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
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ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05
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CNL-14-150, Response to Requests for Additional Information, Developmental Revision I Technical Specification (Section 3.3) and Technical Specification Bases (Limiting Condition for Operation B 3.0.6)
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DCL-14-036, Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement
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GO2-14-043, License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level-High
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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
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CP-201201129, License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
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DCL-12-050, Attachment 2 to DCL-12-050, Final Safety Analysis Report Changes for Process Protection System Replacement
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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.
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L-MT-12-027, License Amendment Request: Provide Restoration Period Before Declaring Average Power Range Monitors Inoperable When Surveillance Requirement 3.3.1.1.2 Not Met
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NL-12-0662, Response to NRC Request for Additional Information (RAI) on License Amendment Request (LAR) for Technical Specification (TS) Table 3.3.1-1 in Response to Westinghouse NSAL 09-01, Rod Withdrawal at Power
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NL-12-0016, Response to NRC Request for Additional Information on License Amendment Request for Technical Specification Table 3.3.1.1 in Response to Westinghouse NSAL 09-01, Rod Withdrawal at Power
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NG-12-0034, Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
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ULNRC-05832, Revision of Technical Specification 3.3.8, TAC No. ME5173
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RS-11-136, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.1
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NL-11-1057, License Amendment Request for Technical Specification Table 3.3.1-1
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NG-11-0299, Response to Request for Additional Information Related to an Amendment to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
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RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
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GNRO-2011/00055, Request for Additional Information Regarding Extended Power Uprate
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GNRO-2011/00042, Responses to NRC Requests for Additional Information Re License Amendment Request for Power Range Neutron Monitoring System
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NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
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GNRO-2011/00013, Request for Additional Information Regarding Extended Power Uprate
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TSTF-13-05, Transmittal of TSTF-536, Revision 0, Resolve CE Digital TS Inconsistencies Regarding CPCs and Ceacs
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L-2018-054, Turkey Point, Units 3 and 4 - 2017 Annual Radioactive Effluent Release Report
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NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
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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
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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 5 of 8
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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
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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
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NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
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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
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ULNRC-05781, Callaway Plant NFPA 805 Transition Report, Attachment N - Technical Specification Changes
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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
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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
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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
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NL-09-1431, License Amendment Request for Technical Specification Table 3.3.1-1
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NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
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L-MT-09-047, Supplement to Extended Power Uprate License Amendment Request: Revision to Proposed Technical Specification Changes in Response to Staff Comments
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CP-200900492, License Amendment Request (LAR) 09-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
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NL-09-0154, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position
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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
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RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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L-MT-08-070, Response to September 16, 2008, Request for Additional Information for License Amendment Request for Power Range Neutron Monitoring System Upgrade
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L-MT-08-049, Submittal of Response to Requests for Additional Information for License Amendment Request for Power Range Neutron Monitoring System Upgrade
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RS-08-091, Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency
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SBK-L-08039, License Amendment Request 08-01, Application for Change to the Technical Specification Surveillance Requirements for Nuclear Instrumentation
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RS-08-026, Response to NRC Request for Additional Information Concerning Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function
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GNRO-2007/00073, Technical Specification Bases Update to the NRC for Period Dated December 03, 2007
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RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions
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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
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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
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GNRO-2007/00018, Supplement to Amendment Request, Changes to the Local Power Range Monitor (LPRM) Calibration Frequency
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ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
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ULNRC-05280, Proposed Revision to Technical Specification 3.7.2 Main Steam Isolation Valves and Revision to Technical Specification 3.7.3 Main Feedwater Isolation Valves and Main Feedwater Regulating Valve Bypass Valves to Remove Valve Isolation Time
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ULNRC-05233, Application for Amendment to Facility Operating License NPF-30
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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
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NRC-2011-0040, Sholly Report for Fr Publication on February 22, 2011
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TSTF-19-06, TSTF Comments on Draft Safety Evaluations for Traveler TSTF-569, Revision 1, Revise Response Time Testing Definition
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L-2019-053, License Amendment Request 269, Modify Reactor Trip System (RTS) Turbine Trip Instrumentation Requirements and Resolve Two Non-Conservative Requirements
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RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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NL-05-1381, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 3.b, Power Range Neutron Flux- High Negative Rate
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ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project
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LR-N05-0336, Request for Changes to Technical Specifications Relocation of Response Time Testing Time Limits to the Updated Final Safety Analysis Report
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ULNRC-05145, Technical Specification Revisions Associated with the Steam Generator Replacement Project
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CPSES-200500155, License Amendment Request (LAR) 04-015 Revision to Technical Specification 3.3.1 Reactor Trip System Instrumentation and 3.3.2 Engineered Safety Feature Actuation System Instrumentation (Esffas)
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NL-19-1063, Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition
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RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions
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ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term
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ET 17-0016, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses
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ND-19-0168, Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification Revision (LAR-19-001)
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ND-18-0364, Supplement to Request for License Amendment: Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes (LAR-17-024S2)
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ET 06-0030, Additional Information Related to Revision to Technical Specification (TS) 3.3.1 Reactor Trip System (RTS) Instrumentation
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ET 06-0002, Revision to Technical Specification (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation
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NL-04-2205, Changes to Technical Specification Bases
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PLA-5756, Proposed Amendment No. 266 to License NPF-14 and Proposed Amendment No. 231 to License NPF-22: Incorporation of TSTF-16 and Editorial Changes
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BSEP 04-0015, Supplement to Request for License Amendments Regarding Core Flow Operating Range Expansion
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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
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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
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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
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DCL-03-137, Response to NRC Request for Additional Information Regarding License Amendment Request 03-02, Response Time Testing Elimination and Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
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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
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DCL-03-111, License Amendment Request 03-12 Revision to Technical Specifications 3.3.1, RTS Instrumentation, and 3.3.2, ESFAS Instrumentation, Enclosures 1 - 4
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ULNRC-04856, Technical Specification Bases, Revision 4
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CPSES-200300095, (CPSES) - License Amendment Request (LAR) 03-01, Revision to Technical Specification (TS) Bases
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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
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ULNRC-04743, Revision to SG Water Level Low Low LCO Applicability & Allowable Values in TS 3.3.1 & 3.3.2
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ULNRC-04721, Technical Specification Bases Revision 3
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DCL-02-097, License Amendment Request 02-05, Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement
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RS-02-151, Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High)
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CNL-19-095, Application to Modify the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (SQN-TS-19-04)
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ULNRC-04638, Response Time Testing Elimination
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ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 8
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ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date
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ULNRC-06702, Enclosureplacement Version of Attachment 3 to ULNRC-06688, Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505
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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 .
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L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response
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RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition
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L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles
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DCL-22-059, License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
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Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long- Term Stability Solution Hardware
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NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System
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ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications
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BECO-LTR-96-094, Discusses power-flow Stability Tech Specs Re Installation of BWROG Enhanced Option 1A
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3F1007-03, License Amendment Request 296, Revision 2: Measurement Uncertainty Recapture Response to Request for Additional Information
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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
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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
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NSD-NRC-97-5231, Forwards Formal Transmittal of Correspondence Previously Sent Over Period 970515-970605.W/index
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TSTF-18-06, TSTF Response to NRC Questions on TSTF-569, Revise Response Time Testing Definition
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L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
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ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
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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.)
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GNRO-2015/00059, Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/2013
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00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
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NL-03-2067, Request to Revise Surveillance Requirements 3.3.1.2 and 3.3.1.3
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NL-05-0233, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11. Reactor Coolant Pump Breaker Position
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ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term
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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,
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ULNRC-05821, Union Electric Co. Application for Amendment to Facility Operating License NPF-30 (Ldcn 10-0036) Revision of Technical Specification 3.3.8 TAC ME5173)
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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
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NL-22-0764, – Units 1 & 2, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology
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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)
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ET 02-0029, Revision to Technical Specification Surveillance Requirements 3.3.1.2 and 3.3.1.3 Re Reactor Trip System Instrumentation
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LER-1998-007-03, :on 981215,inadequate Surveillances Were Found. Caused by Wiring Error & Improperly Performed Response Time Testing.Wiring Error Corrected & Procedures Changed to Allow Online Testing
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Requirements of TS Re Surveillance Testing of Electronic Circuits,Per GL 96-01.Specific Cause of Omission Not Known.Procedures Revised
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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
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LER-1996-001, :on 960120,test Interval to Test Area Radiation Monitors Exceeded Due to Inattention to Controls for Identifying & Performing Required Surveillance Tests.Test Procedure Reissued & Completed
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NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
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NSD-NRC-97-5236, Forwards SSAR Section of short-term Availability Controls for Listed Systems/Functions Under Specified Conditions of Operations
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CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
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AEP-NRC-2019-39, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition
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L-PI-24-051, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) Definitions and Adopt Plant Specific Methods for Response Time Testing (Rtt)
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ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
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CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
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00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
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label: GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
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TSTF-18-02, Technical Specifications Task Force - Transmittal of TSTF-569, Revision 0, Revise Response Time Testing Definition
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TSTF-15-06, Transmittal of TSTF-546, Revision 0, Revise APRM Channel Adjustment Surveillance Requirement
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RS-12-199, Bryson, Units 1 and 2, Response to RAI Related to License Amendment Request to Revise Technical Specifications to Exclude Solid State Protection System (Ssps) Input Relays from Channel Operational Test Surveillance for
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page: https://kanterella.com/RS-2D12-2D199-2C_Bryson-2C_Units_1_and_2-2C_Response_to_RAI_Related_to_License_Amendment_Request_to_Revise_Technical_Specifications_to_Exclude_Solid_State_Protection_System_-28S…
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NL-08-068, Indian Point, Units 1, 2 and 3 - 2007 Annual Radioactive Effluent Release Report
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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,.
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page: https://kanterella.com/DCL-2D12-2D002-2C_Revision_to_the_Updated_Final_Safety_Analysis_Report_Section_4.3.2.2-2C_Power_Distribution-3B_and_Technical_Specification_Bases_3.1.7-2C_Rod_Position_Indicatio…
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CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
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ML092250339
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ML081010193
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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
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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) ..
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ML041140453
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ML040350114
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DCL-04-008, Response to NRC Request for Additional Information Regarding License Amendment Request 03-02, Response Time Testing Elimination and Revision to Technical Specification 3.3.1. Reactor Trip System (RTS) Instrumentation
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page: https://kanterella.com/DCL-2D04-2D008-2C_Response_to_NRC_Request_for_Additional_Information_Regarding_License_Amendment_Request_03-2D02-2C_Response_Time_Testing_Elimination_and_Revision_to_Technical_S…
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DCL-03-142, Response to NRC Request for Additional Information Regarding License Amendment Request 03-06, Revision to Technical Specification 3.8.1, AC Sources - Operating
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NL-03-154, To the Indian Point, Unit 2, License Amendment Request for Conversion to Improved Standard Technical Specifications
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05000528/LER-2001-005, Re Inadequate Surveillance Test for Time Response Testing of Hl Log Power Trip Function
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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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NRC-13-0004, License Amendment Request for Measurement Uncertainty Recapture (MUR) Power Uprate
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DCL-03-162, Response to NRC Request for Additional Information Regarding License Amendment Request 03-02, Response Time Testing Elimination and Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
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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
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CP-202100394, Supplement to License Amendment Request (LAR) 20-006
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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
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L-2025-020, License Amendment Request 279, Extend Surveillance Test Intervals in Support of Transition to 24 Month Fuel Cycles
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NL-16-109, Indian Point 2 Improved Technical Specifications Bases
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PLA-5803, Supplemental Information Related to Revised Response to Generic Letter 94-02: Long-term Stability Solution
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L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle
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CNL-21-001, Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01)
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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
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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
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NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
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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
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NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5
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