TS-3.1.7

TS-3.1.7

TS-3.0.3, TS-3.0.4, TS-3.1.6, TS-3.1.7, TS-3.3.1.1, TS-3.3.3, TS-3.3.4, TS-3.3.6, TS-3.3.6.3, TS-3.4.1, TS-3.4.3, TS-3.5.1, TS-3.5.2, TS-3.5.3, TS-3.6.2.5, TS-3.7.1, TS-3.7.1.2, TS-3.7.3, TS-3.7.5, TS-3.7.7, TS-3.8.1

	Start date	Site	Title	System
ML25287A025	14 October 2025	Browns Ferry	Alternative Request BFN-IST-06	Standby Liquid Control
CNL-25-108, American Society of Mechanical Engineers Operation and Maintenance Code Request for Alternative BFN-IST-06	18 September 2025	Browns Ferry	American Society of Mechanical Engineers Operation and Maintenance Code Request for Alternative BFN-IST-06	Reactor Pressure Vessel Standby Liquid Control Control Rod
JAFP-25-0046, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation	5 September 2025	FitzPatrick	License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation	Reactor Coolant System High Pressure Coolant Injection Reactor Protection System Reactor Core Isolation Cooling Primary containment Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Reactor Water Cleanup Emergency Core Cooling System Main Steam Line Reactor Water Recirculation Control Rod Main Steam
ML25212A186	21 August 2025		Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2025	Residual Heat Removal Standby Liquid Control Main Steam Line
PMNS20251033, Meeting with Tennessee Valley Authority to Discuss a Proposed Emergency License Amendment Request for Browns Ferry Nuclear Plant, Unit 3	18 August 2025	Browns Ferry	Meeting with Tennessee Valley Authority to Discuss a Proposed Emergency License Amendment Request for Browns Ferry Nuclear Plant, Unit 3	Standby Liquid Control
ML25104A095	5 August 2025	Hope Creek	Issuance of Amendment No. 239 Revise Technical Specification Actions for Reactor Coolant System Safety/Relief Valves	Reactor Coolant System Feedwater Reactor Protection System Main Steam Isolation Valve Reactor Core Isolation Cooling Reactor Pressure Vessel Core Spray Automatic Depressurization System Standby Liquid Control Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Rod Main Steam
ML25162A001	30 June 2025		Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: July 8, 2025	Containment Spray
ML25182A196	30 June 2025	Sequoyah	Revisions to the Technical Requirements Manual	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater HVAC Reactor Pressure Vessel Residual Heat Removal Control Rod
ML25086A296	2 June 2025	Catawba Harris Robinson	Adoption of (TSTF) Traveler TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable	Steam Generator Reactor Coolant System Control Rod
ML25085A422	22 May 2025	05200050	SDAA - FSER Chapter 16 - Technical Specifications	Steam Generator Reactor Coolant System Feedwater Secondary containment Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Primary containment Shutdown Cooling HVAC Reactor Pressure Vessel Residual Heat Removal Automatic Depressurization System Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Control Rod Main Steam Containment Spray
WBL-25-030, Of the Unit 2 Cycle 7 Core Operating Limits Report (COLR)	13 May 2025	Watts Bar	Of the Unit 2 Cycle 7 Core Operating Limits Report (COLR)	Reactor Coolant System Control Rod
IR 05000461/2025010	8 May 2025	Clinton	Comprehensive Engineering Team Inspection Report 05000461/2025010	Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve High Pressure Core Spray Core Spray Standby Liquid Control Main Steam
WBL-25-027, Of the Unit 1 Cycle 20 Core Operating Limits Report (COLR) and Revision 0 of the Unit 2 Cycle 7 COLR	6 May 2025	Watts Bar	Of the Unit 1 Cycle 20 Core Operating Limits Report (COLR) and Revision 0 of the Unit 2 Cycle 7 COLR	Reactor Coolant System Control Rod
IR 05000282/2025001	5 May 2025	Prairie Island	Integrated Inspection Report 05000282/2025001 and 05000306/2025001	Feedwater Emergency Diesel Generator Auxiliary Feedwater Core Spray Residual Heat Removal
ML25086A180	2 May 2025	Fermi	– Amendment 231 to Adopt TSTF-505, TSTF-439, TSTF-591	Reactor Coolant System Feedwater Service water High Pressure Coolant Injection Reactor Protection System Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Pressure Vessel Core Spray Residual Heat Removal Automatic Depressurization System Standby Liquid Control Emergency Equipment Cooling Water Residual Heat Removal Service Water Steam Jet Air Ejector Emergency Core Cooling System Main Steam Line Safety Relief Valve Moisture Separator Reheater Control Rod Main Turbine Bypass System
NL-23-0928, Application to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation	18 April 2025	Hatch	Application to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation	High Pressure Coolant Injection Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Shutdown Cooling Reactor Pressure Vessel Reactor Water Cleanup Standby Liquid Control Main Steam Line
L-2025-069, Cycle 35 Core Operating Limits Report	9 April 2025	Turkey Point	Cycle 35 Core Operating Limits Report	Reactor Coolant System Control Rod
ML25099A279	9 April 2025	05200050	LLC - Part 4, US460 Generic Technical Specifications, Revision 2, Volume 1 - Specifications	Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Reactor Pressure Vessel Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam
ML25083A289	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 8, Revision 1, Appendices a and B
ML25083A287	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 7, Revision 1, Appendices a and B
ML25083A291	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 9, Appendices a and B
ML25083A285	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 6, Revision 1, Appendices a and B
ML25101A035	3 April 2025	Susquehanna	Technical Specifications Bases, Manual	Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Standby Liquid Control Remote shutdown Residual Heat Removal Service Water Emergency Core Cooling System Main Steam Line Main Condenser Control Rod Main Steam Main Turbine Bypass System
ML24242A053	10 February 2025	07201025	7. Proposed Renewed CoC No. 1025 Amendment No. 8 Revision 1, Appendices a and B
ML24242A049	10 February 2025	07201025	3. Proposed Renewed CoC No. 1025 Amendment No. 6 Revision 1, Appendices a and B
ML24242A055	10 February 2025	07201025	9. Proposed Renewed CoC No. 1025 Amendment No. 9, Appendices a and B
NRC-25-0007, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, TSTF-439.	4 February 2025	Fermi	Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, TSTF-439.	Standby Liquid Control
ML24305A241	7 January 2025		SDAA Chapter 16 Technical Specifications SE with No Open Items	Steam Generator Reactor Coolant System Feedwater Secondary containment Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Primary containment Shutdown Cooling HVAC Reactor Pressure Vessel Residual Heat Removal Automatic Depressurization System Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Control Rod Main Steam Containment Spray
ML24285A207	17 December 2024	Watts Bar	Amendment Nos. 170 and 76 Regarding the Revision of Technical Specifications 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, and 5.9.5 by Adopting Various Technical Specifications Task Force Travelers	Steam Generator Reactor Coolant System Feedwater Safety Parameter Display System Emergency Core Cooling System Control Rod
WBL-24-050, Of Cycle 20 Core Operating Limits Report (COLR)	19 November 2024	Watts Bar	Of Cycle 20 Core Operating Limits Report (COLR)	Control Rod
L-2024-175, Cycle 34 Core Operating Report	24 October 2024	Turkey Point	Cycle 34 Core Operating Report	Reactor Coolant System Control Rod
IR 05000277/2024002	4 September 2024	Peach Bottom	Reissued Integrated Inspection Report 05000277/2024002 and 05000278/2024002	Reactor Coolant System Feedwater Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Core Spray Residual Heat Removal Standby Liquid Control Reactor Building Closed Loop Cooling Main Steam Line Safety Relief Valve Main Condenser Control Rod Main Steam
ML24227A549	14 August 2024	Peach Bottom	Integrated Inspection Report 05000277/2024002 and 05000278/2024002	Reactor Coolant System Feedwater Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Core Spray Residual Heat Removal Standby Liquid Control Reactor Building Closed Loop Cooling Main Steam Line Main Condenser Control Rod Main Steam
L-2024-122, Core Operating Limits Report	12 August 2024	Turkey Point	Core Operating Limits Report	Reactor Coolant System Control Rod
ML24183A108	8 August 2024	Quad Cities	– Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b	Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Control Room Emergency Ventilation Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Residual Heat Removal Service Water Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Low Pressure Coolant Injection
ML24214A002	1 August 2024	Vogtle	Final SRO Written Exam Vogtle Units 3 and 4 2024-301 Combined (Redacted for Public Release)	Steam Generator Reactor Coolant System Feedwater Service water Main Turbine Shutdown Cooling Residual Heat Removal Main Steam Line Main Condenser Control Rod Main Steam Extraction steam
ML24176A120	29 July 2024	Grand Gulf	Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b	Service water Reactor Protection System Reactor Core Isolation Cooling Primary containment Shutdown Cooling High Pressure Core Spray Residual Heat Removal Automatic Depressurization System Standby Liquid Control Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Room Envelope Containment Spray Low Pressure Coolant Injection
ML24197A240	24 July 2024		Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 6, 2024	Reactor Coolant System Emergency Diesel Generator Primary containment Reactor Pressure Vessel Reactor Water Cleanup Control Room Emergency Air Temperature Control System
ML24179A129	24 June 2024	Oconee Mcguire Catawba Harris Brunswick Robinson McGuire	Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1
NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information	14 June 2024	Farley	RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information	Reactor Coolant System Core Spray Residual Heat Removal Control Room Emergency Filtration System
ML24151A009	11 June 2024	07201015	Conditions for Cask Use and Technical Specifications, Renewed Amendment 1 - Appendix a & B
ML24151A010	11 June 2024	07201015	Conditions for Cask Use and Technical Specifications, Renewed Amendment 2 - Appendix a & B
ML24151A025	11 June 2024	07201015	Conditions for Cask Use and Technical Specifications, Renewed Initial Certificate - Appendix a & B
RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications	24 May 2024	Byron Braidwood	Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications	Steam Generator Reactor Coolant System Reactor Protection System Control Rod
RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable	23 May 2024	Catawba Harris Robinson	Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable	Reactor Coolant System Control Rod
ML24081A007	16 May 2024	River Bend	Issuance of Amendment No. 213 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b	Service water Reactor Protection System Reactor Core Isolation Cooling Primary containment Shutdown Cooling High Pressure Core Spray Residual Heat Removal Automatic Depressurization System Standby Liquid Control Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Room Envelope Control Rod
ML24135A091	9 May 2024	Turkey Point	Periodic Update to the Updated Final Safety Analysis Report, Chapter 14, Appendices a Through G	Steam Generator Reactor Coolant System Control Rod Containment Spray
ML24191A288	6 May 2024	Callaway	Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Operating License Amendment Index	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Residual Heat Removal Control Room Emergency Ventilation Fuel Pool Cooling and Cleanup Main Steam Safety Valve Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Control Rod Main Steam Containment Spray
ML24191A316	6 May 2024	Callaway	Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter 3.1, Reactivity Control Systems	Reactor Coolant System Control Rod
L-2024-072, Cycle 33 Core Operating Limits Report	1 May 2024	Turkey Point	Cycle 33 Core Operating Limits Report	Reactor Coolant System Control Rod
L-2024-073, Cycle 34 Core Operating Limits Report	1 May 2024	Turkey Point	Cycle 34 Core Operating Limits Report	Reactor Coolant System Control Rod
NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint	19 April 2024	Hatch	Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint	Reactor Coolant System Feedwater High Pressure Coolant Injection Main Steam Isolation Valve Reactor Core Isolation Cooling Reactor Pressure Vessel Residual Heat Removal Standby Liquid Control Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Rod Main Steam
ML24108A038	16 April 2024	Davis Besse	Submittal of Core Operating Limits Report, Cycle 24, Revision 0	Steam Generator Reactor Protection System Control Rod
IR 05000259/2023004	6 February 2024	Browns Ferry	Integrated Inspection Report 05000259/2023004; 05000260/2023004 and 05000296/2023004	High Pressure Coolant Injection Emergency Diesel Generator Reactor Core Isolation Cooling Core Spray Residual Heat Removal Standby Liquid Control Residual Heat Removal Service Water Control Room Envelope Control Rod
IR 05000263/2023004	31 January 2024	Monticello	Integrated Inspection Report 05000263/2023004	Reactor Coolant System Feedwater High Pressure Coolant Injection Shutdown Cooling HVAC Core Spray Residual Heat Removal Standby Gas Treatment System Stator Water Cooling Standby Liquid Control Main Steam Line Main Condenser Control Rod Main Steam Low Pressure Coolant Injection
ML23333A139	13 December 2023	Nine Mile Point	NMP1 Retake FY23 Proposed Examination Submittal	Reactor Coolant System Feedwater High Pressure Coolant Injection Emergency Diesel Generator Primary containment Main Turbine Reactor Recirculation Pump Core Spray Reactor Building Ventilation Reactor Water Cleanup Main Condenser Control Rod Containment Spray
ML23256A339	12 December 2023	Nine Mile Point	NMP1 FY23 Retake Administered Examination Files	Reactor Coolant System Feedwater High Pressure Coolant Injection Emergency Diesel Generator Primary containment Main Turbine Reactor Recirculation Pump Core Spray Reactor Building Ventilation Reactor Water Cleanup Main Condenser Control Rod Containment Spray
GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation	5 December 2023	Columbia	Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation	Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Reactor Water Cleanup Standby Liquid Control Main Steam Line
WBL-23-055, Of the Unit 2 Cycle 6 Core Operating Limits Report	22 November 2023	Watts Bar	Of the Unit 2 Cycle 6 Core Operating Limits Report	Control Rod
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