SR-2D3.3.2.5
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05000446/LER-2002-002, Condition Prohibited by Technical Specifications
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CNL-17-066, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17)
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DCL-16-104, Technical Specification Changes for License Amendment Request 13-02, Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1..
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CNS-16-015, Technical Specification Bases Changes
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NL-17-0611, Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow
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CNS-15-098, Technical Specification Bases Changes
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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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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-15-156, 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 3 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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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 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
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NRC 2009-0066, License Amendment Request 261 Supplement 1 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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TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
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L-07-017, License Amendment Requests Nos. 334 and 205
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ULNRC-06485, License Amendment Request to Revise Technical Specifications for Testing of Main Turbine Control Slave Relay (LDCN 18-0025)
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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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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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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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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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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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CNL-22-003, Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010)
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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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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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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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CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
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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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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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TSTF-10-20, Response to NRC Request for Additional Information Regarding TSTF-432, Revision 0, Change in Technical Specifications End States (WCAP-16294)
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ET 08-0039, Revision to TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, TS 3.7.2, Main Steam Isolation Valves (Msivs), and Addition of New TS 3.7.19, Secondary System Isolation Valves
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ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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05000446/LER-2008-002, For Comanche Peak, Unit 2, Regarding P-14 Trip Function for Steam Generator 2-02 Narrow Range Level Channel Inoperable Due to Mispositioned Hand Switch
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RS-08-037, Application for License Amendment to Revise the Numbering of Two Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements
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DCL-07-002, Response to Request for Additional Information on License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement
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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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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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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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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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CPSES-200502434, Licence Amendment Request (LAR) 05-010, Revision to Technical Specification 3.3.2, ESFAS Instrumentation, 3.5.2, ECCS-Operating, and 3.6.7, Spray Additive System
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NSD-NRC-98-5561, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status of Column of Oits, Provided in Table 1
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NL-15-181, Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mod
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