SR-2D3.3.2.4
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IR 05000261/2001005
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CNS-16-015, Technical Specification Bases Changes
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CNS-15-098, Technical Specification Bases Changes
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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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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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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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NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
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ULNRC-05737, Completion Time Extensions for TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Functions, TAC No. ME2822 (LDCN 09-0039 Supplement)
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CP-201800115, License Amendment Request 17-001 Revision to Technical Specification 3.3.2. ESFAS Instrumentation
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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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NL-18-0733, Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information
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NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 6
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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 2 of 9
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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 4 of 8
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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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ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)
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RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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NL-08-0769, Response to NRC Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) 3.3.2, ESFAS Instrumentation, and TS 3.5.4. Refueling Water Storage Tank (Rwst).
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RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project
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ULNRC-05145, Technical Specification Revisions Associated with the Steam Generator Replacement Project
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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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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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ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1
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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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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-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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NL-03-052, Response to Request for Additional Information Regarding Section 3.3, Instrumentation, of the Improved Technical Specification (ITS)
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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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RNP-RA/02-0066, Request for Amendment Re Increase Authorized Reactor Core Power Level from 2399 Mwt to 2339 Mwt (Approximately 1.7 Percent)
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CPSES-200201164, Comanche Response to Request for Additional Information to License Amendment Request (LAR) 01-008: Revision to Technical Specification (TS) 3.3.2, ESFAS Instrumentation and 3.3.6, Containment Ventilation Isolation Instrumentation
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CNL-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27)
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RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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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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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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RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.
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CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
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ULNRC-05731, Completion Time Extensions for TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Functions (LDCN 09-0039 Supplement)
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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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ET-NRC-93-3924, Forwards Responses to Request for Addl Info on AP600,per NRC 930312 & 0413 Ltrs
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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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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-0719-66472, LLC Supplemental Response to NRC Request for Additional Information No. 520 (Erai No. 9642) on the NuScale Design Certification Application
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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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CNS-14-128, License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable
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CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
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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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CPSES-200501761, Response to Request for Additional Information for License Amendment Request 04-002: Revision to Technical Specification 3.3.2 Engineered Safety Features Actuation System Instrumentation
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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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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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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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CNL-25-028, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for (SQN-TS-23-02 & WBN-TS-23-08) (EPID L-2023-LLA-0175
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NSD-NRC-98-5702, Forwards Formal Transmittal of Correspondence W Previously Sent to NRC Informally Over Period 980223-0316.Index of Attached Matl,Encl Per Request
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L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle
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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-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
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