SR-2D3.3.2.9
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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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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-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-15-128, 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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ULNRC-05687, Application for Amendment to Technical Specification 3.3.2 Function 6.g Engineered Safety Feature Actuation System, Instrumentation: Auxiliary Feedwater Actuation on Trip of All Main Feedwater Pump (LDCN 10-0011)
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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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L-09-096, License Amendment Request No. 08-008, Elimination of Recirculation Spray Pump Response Time Surveillance Requirement
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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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ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project
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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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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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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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IR 05000327/2022001
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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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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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ULNRC-05608, ULNRC-05608, Revision of Technical Specification 3.3.2 and 3.7.3 (License Amendment Request OL-1289)
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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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NRC-2009-0553, Biweekly Sholly Report for Federal Register Publication on December 15, 2009
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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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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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05000328/LER-2021-002, Turbine Trio Function Inoperable Due to Slow to Close Turbine Throttle Valve
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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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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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MNS-14-043, (Mns), Units 1 and 2, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Proposed Changes to Technical Specification (TS) 3.3.2, in Support of Compliance with NRC Order EA-12-049
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ML18208A191
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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 10-0010, License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps
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wiki page sort key: ET 10-0010, License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps

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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wiki page sort key: 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

ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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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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ML091540083
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ML101540416
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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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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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wiki page sort key: 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

ML022910269
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ML14339A764
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ML11187A341
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ML22259A204
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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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CNL-15-181, 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 - Mode 4
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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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05000327/LER-2022-002, Turbine Trip Function Inoperable Due to Slow to Close Turbine Throttle Valve
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ML22210A118
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ML20236N630
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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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ML21053A117
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ML020580696
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ML25051A210
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ML21033B071
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ML21158A284
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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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page: https://kanterella.com/CPSES-2D200701323-2C_License_Amendment_Request_07-2D006-2C_Revision_to_Technical_Specification_3.1.4-2C_Rod_Group_Alignment_Limits-2C_Table_3.3.1-2D1-2C_Reactor_Trip_System_Inst…
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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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page: https://kanterella.com/CPSES-2D200502434-2C_Licence_Amendment_Request_-28LAR-29_05-2D010-2C_Revision_to_Technical_Specification_3.3.2-2C_ESFAS_Instrumentation-2C_3.5.2-2C_ECCS-2DOperating-2C_and_3.6.7…
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ML24191A311
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ML24191A288
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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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ML23258A148
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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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