TS-3.3.1.1

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
ML25268A108	26 September 2025	Hatch	Authorization of Relief Request RR-V-1 - Sixth Inservice Testing Interval	Reactor Protection System Control Rod
ML25268A301	25 September 2025	Browns Ferry	Core Operating Limits Report for Unit 1 Cycle 16 Operation, Revision 1; Unit 2 Cycle 24 Operation, Revision 1; and Unit 3 Cycle 22 Operation, Revision 1	Feedwater Reactor Protection System Safety Relief Valve Moisture Separator Reheater Control Rod
RA-25-0197, Cycle 25 Core Operating Limits Report (Colr), Revision 2	22 September 2025	Brunswick	Cycle 25 Core Operating Limits Report (Colr), Revision 2	Feedwater Reactor Protection System Main Steam Isolation Valve Main Turbine Emergency Core Cooling System Safety Relief Valve Control Rod Main Turbine Bypass System
ML25247A004	17 September 2025	Vogtle	SNC Slides - Pre-Submittal Meeting - Vogtle 3 and 4 - TSTF-505, 50.69, and TSTF-425 LARs	Reactor Protection System Automatic Depressurization System Main Steam Safety Valve Control Room Envelope
ML25258A105	15 September 2025	Grand Gulf	(GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision 1	Feedwater
PLA-8189, Supplement to License Amendment Requesting Revision to Technical Specifications for Reactor Vessel Water Level 3 and Level 8 Allowable Values - PLA-8189	10 September 2025	Susquehanna	Supplement to License Amendment Requesting Revision to Technical Specifications for Reactor Vessel Water Level 3 and Level 8 Allowable Values - PLA-8189	Feedwater Reactor Protection System Reactor Core Isolation Cooling Primary containment Main Turbine Reactor Pressure Vessel Emergency Core Cooling System
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
RS-25-132, Supplement to Clinton Response to Request for Additional Information Related to Response Time Testing License Amendment Request	20 August 2025	Clinton	Supplement to Clinton Response to Request for Additional Information Related to Response Time Testing License Amendment Request	Reactor Protection System Main Steam Isolation Valve Primary containment Main Steam Line Main Condenser Main Steam
ML25220A290	18 August 2025	Crane	June 30, 2025, Summary of Public Meeting with Constellation Energy Generation, LLC Regarding a Planned License Amendment Request to Revise the License and Technical Specifications to Support Reauthorization of Power Operations
05000458/LER-2025-003, Turbine Control Valve Closure Results in Loss of Safety Function	14 August 2025	River Bend	Turbine Control Valve Closure Results in Loss of Safety Function	Control Rod Main Steam
RS-25-129, Response to Request for Additional Information Related to License Amendment Request for Clinton Power Station to Approve a Methodology for Testing MSIV Closure RPS Response Time	13 August 2025	Clinton	Response to Request for Additional Information Related to License Amendment Request for Clinton Power Station to Approve a Methodology for Testing MSIV Closure RPS Response Time	Reactor Protection System Main Steam Isolation Valve Primary containment Main Steam Line Main Condenser Main Steam
ML25178C663	30 June 2025	Crane	Crane Clean Energy Center - Presentation for Pre-submittal Meeting on Planned LAR to Restore Operating License and TS	Steam Generator HVAC
ML25182A205	30 June 2025	Hope Creek	ITS Email Exchange Regarding Editorial Discrepancies	Control Rod
RS-25-103, License Amendment Request for Proposed Change to the USAR to Approve Alternate Method of Verifying MSIV Closure Reactor Protection System Response Time	26 June 2025	Clinton	License Amendment Request for Proposed Change to the USAR to Approve Alternate Method of Verifying MSIV Closure Reactor Protection System Response Time	Reactor Coolant System Reactor Protection System Main Steam Isolation Valve Main Turbine Main Steam Line Main Steam
ML25162A064	23 June 2025	Susquehanna	Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications	Feedwater Reactor Protection System Reactor Core Isolation Cooling Primary containment Main Turbine Reactor Pressure Vessel Emergency Core Cooling System
ML25139A124	22 May 2025		Enforcement Program Annual Report, Calendar Year 2024 (Public)	Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Rod Worth Minimizer Control Rod
ML25134A161	14 May 2025	Hope Creek	Enclosure 2, Volume 7: Hope Creek Generating Station - Improved Technical Specifications Conversion ITS Section 3.2 Power Distribution Limits, Revision 1	Reactor Protection System Intermediate Range Monitor Main Steam Line Control Rod
ML25134A169	14 May 2025	Hope Creek	Enclosure 2, Volume 14: Hope Creek Generating Station - Improved Technical Specifications Conversion ITS Section 3.9 Refueling Operations, Revision 1	Reactor Coolant System Secondary containment Service water Reactor Protection System Reactor Core Isolation Cooling Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Reactor Water Cleanup Intermediate Range Monitor Emergency Core Cooling System Decay Heat Removal Control Rod Containment Spray Low Pressure Coolant Injection
ML25134A178	14 May 2025	Hope Creek	Enclosure 2, Volume 17: Hope Creek Generating Station - Improved Technical Specifications Conversion ITS Chapter 5.0 Administrative Controls, Revision 1	Steam Generator Reactor Coolant System Feedwater Secondary containment High Pressure Coolant Injection Reactor Protection System Reactor Core Isolation Cooling Primary containment Main Turbine Reactor Pressure Vessel Core Spray Reactor Building Ventilation Residual Heat Removal Standby Gas Treatment System Control Room Emergency Filtration System Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Room Envelope Main Condenser 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
GO2-25-081, Cycle 28 Core Operating Limits Report	7 May 2025	Columbia	Cycle 28 Core Operating Limits Report	Feedwater Control Rod
ML25128A220	6 May 2025	Monticello	Core Operating Limits Report for Cycle 33	Feedwater Main Steam Isolation Valve Control Rod
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
L-25-076, Core Operating Limits Report for Operating Cycle 21	15 April 2025	Perry	Core Operating Limits Report for Operating Cycle 21	Feedwater Reactor Protection System Control Rod
LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2	4 April 2025	Hope Creek	License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2	Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Reactor Core Isolation Cooling Primary containment Shutdown Cooling Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Control Room Emergency Filtration System Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Low Pressure Coolant Injection
ML25101A036	3 April 2025	Susquehanna	Technical Specification 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 Safety Relief Valve Main Condenser Control Rod Main Steam Main Turbine Bypass System
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
PLA-8169, Submittal of Susquehanna Steam Electric Station Unit 2 Cycle 23 Core Operating Limits Report	2 April 2025	Susquehanna	Submittal of Susquehanna Steam Electric Station Unit 2 Cycle 23 Core Operating Limits Report	Feedwater Main Turbine Control Rod
ML25091A046	27 March 2025		FOIA-2025-000406 Released Set 1	Steam Generator Feedwater Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Reactor Core Isolation Cooling Primary containment Main Turbine Reactor Pressure Vessel Core Spray Control Room Emergency Ventilation Standby Liquid Control Emergency Core Cooling System Main Steam Line Safety Relief Valve Control rod blade Main Condenser Control Rod Low Pressure Coolant Injection
RBG-48350, State Core Operating Limits Report (COLR) - Cycle 24, Revision 0	26 March 2025	River Bend	State Core Operating Limits Report (COLR) - Cycle 24, Revision 0	Feedwater Control Rod
ML25078A166	19 March 2025	Peach Bottom	Re-Issuance of the Core Operating Limits Report for Reload 25, Cycle 26	Feedwater Main Steam Isolation Valve Emergency Core Cooling System Safety Relief Valve Control Rod
RA-25-0071, Cycle 27 Core Operating Limits Report (COLR)	17 March 2025	Brunswick	Cycle 27 Core Operating Limits Report (COLR)	Feedwater Reactor Protection System Main Steam Isolation Valve Main Turbine Emergency Core Cooling System Safety Relief Valve Control Rod Main Turbine Bypass System
ML25044A299	13 February 2025	Peach Bottom	Core Operating Limits Report for Reload 24, Cycle 25	Feedwater Main Steam Isolation Valve Emergency Core Cooling System Safety Relief Valve Control Rod
NL-24-0421, Submittal of the Inservice Testing Program Alternative Requests and Relief Requests for Pumps and Valves - Sixth Ten-Year Interval	30 January 2025	Hatch	Submittal of the Inservice Testing Program Alternative Requests and Relief Requests for Pumps and Valves - Sixth Ten-Year Interval	Secondary containment Service water Reactor Protection System Shutdown Cooling Core Spray Residual Heat Removal Standby Gas Treatment System Control Rod
PLA-8144, Proposed Amendment to Licenses NPF-14 and NPF-22: Revised Reactor Vessel Water Level 3 and Level 8 Allowable Value PLA-8144	29 January 2025	Susquehanna	Proposed Amendment to Licenses NPF-14 and NPF-22: Revised Reactor Vessel Water Level 3 and Level 8 Allowable Value PLA-8144	Feedwater High Pressure Coolant Injection Reactor Protection System Primary Containment Isolation System Reactor Core Isolation Cooling Primary containment Shutdown Cooling Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Automatic Depressurization System Emergency Core Cooling System Main Steam Line Main Steam Low Pressure Coolant Injection
RA-25-0023, Cycle 25 Core Operating Limits Report (Colr), Revision 1	28 January 2025	Brunswick	Cycle 25 Core Operating Limits Report (Colr), Revision 1	Feedwater Reactor Protection System Main Steam Isolation Valve Main Turbine Emergency Core Cooling System Safety Relief Valve Control Rod Main Turbine Bypass System
ML25027A421	27 January 2025	Grand Gulf Arkansas Nuclear River Bend Waterford	Entergy Operations, Inc. - Application to Revise Technical Specifications to Adopt TSTF-591, Revised Risk Informed Completion Time (RICT) Program	Steam Generator Reactor Coolant System Reactor Pressure Vessel Emergency Core Cooling System Control Room Envelope
ML24339B729	18 December 2024	Calvert Cliffs Peach Bottom Nine Mile Point Byron Braidwood Limerick Ginna Clinton FitzPatrick LaSalle	Amd - Constellation - Adoption of TSTF-591	Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Reactor Pressure Vessel Emergency Core Cooling System Main Turbine Bypass System
ML24310A284	4 November 2024	Peach Bottom	Core Operating Limits Report for Reload 25, Cycle 26	Feedwater Main Steam Isolation Valve Emergency Core Cooling System Safety Relief Valve Control Rod
ML24151A384	31 October 2024	Limerick	– Issuance of Amendment Nos. 264 and 226 Support to Digital Modernization Project Installation (EPID L-2023-LLA-0025) and Exemption from the Requirements of 10 CFR 50.62	Secondary containment High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Primary containment Reactor Recirculation Pump Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Standby Gas Treatment System Standby Liquid Control Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Rod Main Steam Low Pressure Coolant Injection
JAFP-24-0044, Core Operating Limits Report Cycle 27	16 September 2024	FitzPatrick	Core Operating Limits Report Cycle 27	Feedwater Main Steam Isolation Valve Control Rod
ML24255A886	10 September 2024	Browns Ferry	Core Operating Limits Report for Cycle 16 Operation, Revision 0	Feedwater Reactor Protection System Safety Relief Valve Control Rod
IR 05000373/2024002	13 August 2024	LaSalle	County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002	Service water Reactor Protection System Emergency Diesel Generator Reactor Core Isolation Cooling Main Turbine Core Spray Standby Gas Treatment System Standby Liquid Control Emergency Core Cooling System Main Steam Line 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
ML24213A322	30 July 2024	Fermi	NRR E-mail Capture - Fermi 2 Audit Questions from the Audit Team Supporting Review of the LAR to Adopt TSTF-505	Reactor Protection System Emergency Diesel Generator Reactor Core Isolation Cooling Primary containment Automatic Depressurization System Steam Jet Air Ejector Emergency Core Cooling System Low Pressure Coolant Injection
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
IR 05000298/2024002	25 July 2024	Cooper	Integrated Inspection Report 05000298/2024002	Reactor Coolant System Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Reactor Core Isolation Cooling Main Turbine Core Spray Residual Heat Removal Automatic Depressurization System Residual Heat Removal Service Water Control Rod Main Steam
ML24101A179	25 June 2024	Arkansas Nuclear	Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Shutdown Cooling Emergency Core Cooling System Containment Spray
ML24177A151	24 June 2024	Peach Bottom	Post Accident Monitoring Instrumentation Report	Main Steam Isolation Valve Primary containment Main Steam Line
ML24124A016	28 May 2024	Perry	Issuance of Amendment No. 204 to Adopt Technical Specifications Task Force Traveler TSTF-264, Revision 0	Reactor Protection System Intermediate Range Monitor Control Rod
ML24079A076	23 May 2024	Calvert Cliffs Dresden Peach Bottom Nine Mile Point Byron Braidwood Limerick Ginna Clinton Quad Cities FitzPatrick LaSalle	Issuance of Amendments to Adopt TSTF 264	Feedwater Reactor Protection System Intermediate Range Monitor Control Rod
ML24142A432	20 May 2024	Hope Creek	Enclosure 2: Hope Creek Generating Station Improved Technical Specifications Conversion - Volume 4	Reactor Coolant System Reactor Protection System Reactor Pressure Vessel Intermediate Range Monitor Main Steam Line Control Rod
ML24142A442	20 May 2024	Hope Creek	Enclosure 2: Hope Creek Generating Station Improved Technical Specifications Conversion - Volume 14	Reactor Coolant System Secondary containment Service water Reactor Protection System Reactor Core Isolation Cooling Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Reactor Water Cleanup Intermediate Range Monitor Emergency Core Cooling System Decay Heat Removal Control Rod Containment Spray Low Pressure Coolant Injection
ML24142A435	20 May 2024	Hope Creek	Enclosure 2: Hope Creek Generating Station Improved Technical Specifications Conversion - Volume 7	Reactor Protection System Intermediate Range Monitor Main Steam Line Control Rod
ML24142A445	20 May 2024	Hope Creek	Enclosure 2: Hope Creek Generating Station Improved Technical Specifications Conversion - Volume 17	Steam Generator Reactor Coolant System Feedwater Secondary containment High Pressure Coolant Injection Reactor Protection System Reactor Core Isolation Cooling Primary containment Main Turbine Reactor Pressure Vessel Core Spray Reactor Building Ventilation Residual Heat Removal Standby Gas Treatment System Control Room Emergency Filtration System Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Room Envelope Main Condenser 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
05000265/LER-2024-001, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing	10 May 2024	Quad Cities	Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing	Reactor Protection System Emergency Diesel Generator Reactor Water Cleanup Control Rod
05000298/LER-2024-004, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications	9 May 2024	Cooper	Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications	Reactor Protection System Main Turbine
ML24114A310	3 May 2024	Hatch Mcguire Palo Verde Fermi Watts Bar Cooper Sequoyah Susquehanna Surry North Anna Diablo Canyon Vogtle Farley Cook Comanche Peak FitzPatrick McGuire Vallecitos Nuclear Center	Monthly (28-Day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 14, 2024	Reactor Coolant System Reactor Protection System Emergency Diesel Generator Primary containment Reactor Pressure Vessel Containment Spray
IR 05000298/2024001	3 May 2024	Cooper	Integrated Inspection Report 05000298/2024001	Feedwater Secondary containment Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Primary containment Main Turbine HVAC Residual Heat Removal Standby Liquid Control Residual Heat Removal Service Water Rod Worth Minimizer Control Rod
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TS-3.3.1.1

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