SR-2D3.3.1.5
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creation date: 2025-12-06T00:21:04-05:00
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SR-3.3.1.5
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IR 05000424/2003005
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ONS-2017-019, Technical Specification Bases Change 2015-09
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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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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 NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements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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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
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PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
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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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NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
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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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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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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 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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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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RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project
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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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NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
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RAIO-0719-66473, LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application
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RAIO-0219-64635, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
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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-18-0067, Request for License Amendment: Fuel Management Related Technical Specifications (LAR-18-005)
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ET 09-0019, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
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NL-04-2205, Changes to Technical Specification Bases
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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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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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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-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-04721, Technical Specification Bases Revision 3
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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
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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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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
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1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
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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)
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CNL-19-086, Supplement to Application for License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)
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ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
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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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CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
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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
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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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RAIO-0718-61158, LLC Response to NRC Request for Additional Information No. 490 (Erai No. 9556) on the NuScale Design Certification Application
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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 .
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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
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ML13052A230
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ML13137A129
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ML18208A191
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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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CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
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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
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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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NL-03-154, To the Indian Point, Unit 2, License Amendment Request for Conversion to Improved Standard Technical Specifications
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ML22259A204
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IR 05000302/2002301
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RAIO-1218-63954, LLC Supplemental Response to NRC Request for Additional Information No. 196 (Erai No. 9050) on the NuScale Design Certification Application
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ML14339A751
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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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ML19330E020
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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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NL-14-1297, Request for Enforcement Discretion from Technical Specification 3.3.6, Containment Spray and Cooling Systems
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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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ML21053A117
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ML24305A241
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NL-16-109, Indian Point 2 Improved Technical Specifications Bases
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ML20280A827
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ML20335A001
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ML21350A426
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ML22119A094
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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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ML24339B304
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ML24285A207
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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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ML20210N158
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ONS-2015-106, Technical Specification (TS) Bases Change
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ML18270A322
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ML20029C989
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NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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ML24191A311
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SR
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