TS-3.3.6

TS-3.3.6

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
ML25230A081	2 September 2025	Vogtle	Units 3 and 4 — Issuance of Amendment to Revise Technical Specification 3.3.15 and 3.3.16	Steam Generator Reactor Coolant System Feedwater Residual Heat Removal Automatic Depressurization System
ML25213A183	27 August 2025	Comanche Peak	– Issuance of Amendment Nos. 193 and 193, Respectively, to Change Technical Specifications Consistent with TSTF-51, TSTF-471-A and TSTF-571	Reactor Coolant System Residual Heat Removal Control Room Emergency Filtration System Control Room Envelope Control Rod
ML25181A799	3 July 2025	Sequoyah	Summary of Public Teleconference with Tennessee Valley Authority to Discuss a Proposed License Amendment Request Regarding Revision to TS LCO 3.3.6 for Containment Vent Isolation Instrumentation
ML25112A334	23 June 2025	Sequoyah	Issuance of Amendment Nos. 372 and 366 Regarding Revision of the Fuel Handling Accident Analysis, Deletion of Technical Specification 3.9.4, and Revision of Technical Specification 3.3.6	Primary containment Shield Building Emergency Gas Treatment System
ML25160A088	11 June 2025	Sequoyah	License Amendment Request to Revise LCO 3.3.6 Pre-Submittal Meeting Slides
PMNS20250669, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request	2 June 2025	Sequoyah	Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request
LG-25-083, Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 18, Cycle 19	28 May 2025	Limerick	Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 18, Cycle 19	Reactor Coolant System Feedwater Main Steam Isolation Valve Emergency Core Cooling System Safety Relief Valve Control Rod
ML25091A289	9 April 2025	Saint Lucie	Regulatory Audit Plan in Support of License Amendment Request for Licensing Basis Changes in Support of St. Lucie Unit 2 Transition to 24-Month Fuel Cycles	Feedwater Main Steam Isolation Valve Auxiliary Feedwater Control Room Emergency Ventilation Shield Building Remote shutdown Emergency Core Cooling System Containment Spray
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
CNL-25-019, Response to Request for Additional Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetration, and to Modify Technical Specification	17 March 2025	Sequoyah	Response to Request for Additional Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetration, and to Modify Technical Specification	Primary containment Shield Building
ML25037A329	11 February 2025	Vogtle	Summary of February 6, 2025, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a Proposed Alternate Source Term LAR to Adopt Regulatory Guide 1.1.183, Rev. 1, for Vogtle, Units 1 & 2	Steam Generator Control Room Emergency Filtration System Main Steam Line Control Rod Containment Spray
LG-25-001, Core Operating Limits Report for Limerick Generating Station, Unit 1, Reload 20, Cycle 21	31 January 2025	Limerick	Core Operating Limits Report for Limerick Generating Station, Unit 1, Reload 20, Cycle 21	Reactor Coolant System Feedwater Main Steam Isolation Valve Emergency Core Cooling System Safety Relief Valve Control Rod
NL-24-0325, License Amendment Request: Move Surveillance Requirements from Technical Specifications (TS) 3.3.15 and 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic	24 January 2025	Vogtle	License Amendment Request: Move Surveillance Requirements from Technical Specifications (TS) 3.3.15 and 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic	Steam Generator Reactor Coolant System Feedwater Residual Heat Removal Automatic Depressurization System Main Steam Safety Valve Decay Heat Removal Main Steam Line Control Rod
ML25022A059	21 January 2025	Sequoyah	Request for Additional Information Exhb - FHA Analysis, TS 3.9.4, TS 3.3.6, L-2024-LLA-0117	Shield Building
CNL-24-084, Response to Request for Confirmatory Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3	13 January 2025	Sequoyah	Response to Request for Confirmatory Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3
ML24347A029	12 December 2024	Sequoyah	NRR E-mail Capture - Request for Confirmatory Information License Amendment Request to Modify the FHA Analysis, Tech Spec TS 3.9.4 and Tech Spec 3.3.6 (L-2024-LLA-0117)
ML24284A294	22 October 2024		Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: October 29, 2024	Control Rod
ML24281A007	2 October 2024	Sequoyah	NRR E-mail Capture - Acceptance Review Results for the Sequoyah License Amendment Request to Modify the FHA Analysis, Tech Spec TS 3.9.4 and Tech Spec 3.3.6 (L-2024-LLA-0117)
CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel	12 September 2024	Comanche Peak	License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel	Reactor Coolant System Residual Heat Removal Control Room Emergency Filtration System Control Room Envelope Control Rod Containment Spray
ML24249A050	3 September 2024	Hatch	Revision to Technical Requirements Manual, Part 2 of 2	Feedwater Secondary containment Service water Reactor Protection System Main Steam Isolation Valve Primary containment Core Spray Main Steam Line Rod Worth Minimizer Main Condenser Control Rod Main Steam
ML24247A180	28 August 2024	Sequoyah	Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea
ML24247A175	28 August 2024	Sequoyah	Enclosure 1: Description and Assessment of the Proposed Changes	Secondary containment Primary containment Shield Building Emergency Gas Treatment System
PMNS20241102, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specs 3.3.6 and 3.9.4 Related to Containment Isolation/Penetrations and the Fuel Handling a	21 August 2024	Sequoyah	Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specs 3.3.6 and 3.9.4 Related to Containment Isolation/Penetrations and the Fuel Handling a
ML24218A218	15 August 2024	Sequoyah	Summary of July 16, 2024, Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future Sequoyah Nuclear Plant LAR Related to Containment Penetrations and Fuel Handling
ML24215A344	6 August 2024		2024 NEI RP Forum - NRC Presentation (ML24215A344)	Secondary containment Primary containment HVAC
ML24191A064	16 July 2024	Sequoyah	TVA Pre-Submittal Conference Presentation for Proposed LAR Regarding a Revision to Sequoyah Fuel Handling Accident Analysis, Deletion of TS 3.9.4 and Modification of TS 3.3.6 - July 16, 2024
05000440/LER-2024-002, Reactor Water Clean Up Leak Detection Loss of Safety Function	27 June 2024	Perry	Reactor Water Clean Up Leak Detection Loss of Safety Function	Feedwater Primary containment Reactor Pressure Vessel Reactor Water Cleanup Control Rod
PMNS20240795, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specs 3.3.6 and 3.9.4 Related to Containment Isolation/Penetrations and the Fuel Handling Accident Analys	26 June 2024	Sequoyah	Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specs 3.3.6 and 3.9.4 Related to Containment Isolation/Penetrations and the Fuel Handling Accident Analysis
LG-24-040, Unit - Issuance of the Core Operating Limits Report (COLR) for Unit 1 Reload 20, Cycle 21	9 May 2024	Limerick	Unit - Issuance of the Core Operating Limits Report (COLR) for Unit 1 Reload 20, Cycle 21	Reactor Coolant System Feedwater Control Rod
ML24191A338	6 May 2024	Callaway	Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter B 3.9, Refueling Operations	Reactor Coolant System Service water Reactor Pressure Vessel Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Rod
ML24191A311	6 May 2024	Callaway	Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter 3.3, Instrumentation	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Control Room Emergency Ventilation Remote shutdown 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
ULNRC-06868, Annual Radioactive Effluent Release Report	30 April 2024	Callaway	Annual Radioactive Effluent Release Report	Steam Generator Reactor Coolant System
ML23326A039	24 January 2024	Arkansas Nuclear	Issuance of Amendment No. 281 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 Emergency Core Cooling System Emergency Feedwater Initiation and Control Decay Heat Removal Main Steam Line Control Rod Emergency Feedwater System
2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4	11 January 2024	Arkansas Nuclear	Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Control Room Emergency Ventilation Emergency Core Cooling System Main Steam Line Main Steam Containment Spray
ML23198A012	12 December 2023	05000128	Examination Report Letter No. 50-128/Ol-23-03, Texas A&M University	Control Rod
ML23228A143	22 November 2023	Farley	Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals	Steam Generator
ML23275A111	2 October 2023	Saint Lucie	Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16	Steam Generator Reactor Coolant System Feedwater Secondary containment Reactor Protection System Auxiliary Feedwater Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Shield Building Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Containment Spray
1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4	21 September 2023	Arkansas Nuclear	Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Turbine Emergency Core Cooling System Emergency Feedwater Initiation and Control Decay Heat Removal Main Steam Line Control Rod Main Steam
TSTF-23-06, TSTF Response to NRC Request for Additional Information on TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements	13 September 2023	Technical Specifications Task Force 99902042	TSTF Response to NRC Request for Additional Information on TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements	Reactor Coolant System Feedwater Secondary containment Reactor Protection System Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Pressure Vessel High Pressure Core Spray Residual Heat Removal Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Emergency Core Cooling System Main Steam Line Control Rod Main Steam Containment Spray
ML23241B040	11 September 2023	Technical Specifications Task Force	Final Traveler SE of TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown	Emergency Diesel Generator
ML23241B039	11 September 2023	Technical Specifications Task Force	Final Model SE of TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown	Emergency Diesel Generator
ML23228A111	23 August 2023		Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 5, 2023	Steam Generator Reactor Coolant System Primary containment Remote shutdown Emergency Core Cooling System Control Rod Low Pressure Coolant Injection
ML23158A018	31 July 2023	Vogtle	Issuance of Amendments Nos. 219 and 202, Regarding Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490	Steam Generator Reactor Coolant System Feedwater Secondary containment Main Steam Isolation Valve Primary containment Shutdown Cooling HVAC Residual Heat Removal Control Room Emergency Filtration System Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
ML23124A222	30 June 2023	Technical Specifications Task Force	Draft Traveler SE of TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown	Emergency Diesel Generator
ML23124A220	30 June 2023	Technical Specifications Task Force	Draft Model SE of TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown	Emergency Diesel Generator
LG-23-040, Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 17, Cycle 18	31 May 2023	Limerick	Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 17, Cycle 18	Reactor Coolant System Feedwater Main Steam Isolation Valve Emergency Core Cooling System Safety Relief Valve Control Rod
ML23151A452	24 May 2023	Turkey Point	Enclosure 2, Volume 14: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2	Reactor Coolant System Secondary containment Reactor Pressure Vessel Residual Heat Removal Control Room Emergency Ventilation Emergency Core Cooling System Decay Heat Removal Control Rod
ML23151A454	24 May 2023	Turkey Point	Enclosure 2, Volume 16: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Chapter 5, Administrative Controls, Revision 2	Steam Generator Reactor Coolant System Control Room Emergency Ventilation Control Room Emergency Filtration System Emergency Core Cooling System Safety Relief Valve Control Room Envelope Control Rod Containment Spray
ML23102A147	22 May 2023	Beaver Valley	Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time	Emergency Diesel Generator Residual Heat Removal Control Room Emergency Ventilation Control Room Envelope
ML23081A038	25 April 2023	Dresden Nine Mile Point Clinton Quad Cities LaSalle	County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration	Feedwater Primary containment Reactor Building Ventilation Main Steam Line
TSTF-23-04, Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements	6 April 2023	Technical Specifications Task Force 99902042	Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements	Reactor Coolant System Feedwater Secondary containment Reactor Protection System Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Pressure Vessel High Pressure Core Spray Residual Heat Removal Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Emergency Core Cooling System Main Steam Line Control Rod Main Steam Containment Spray
ML23095A021	4 April 2023	Turkey Point	Enclosure 2 - ITS Section 3.9 Refueling Operations, Revision 2, Volume 14	Reactor Coolant System Secondary containment Reactor Pressure Vessel Residual Heat Removal Control Room Emergency Ventilation Emergency Core Cooling System Decay Heat Removal Control Rod
ML23095A022	4 April 2023	Turkey Point	Enclosure 2 - ITS Chapter 5.0 Administrative Controls, Revision 2, Volume 16	Steam Generator Reactor Coolant System Control Room Emergency Ventilation Control Room Emergency Filtration System Emergency Core Cooling System Safety Relief Valve Control Room Envelope Control Rod Containment Spray
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes	29 March 2023	Hope Creek	Submittal of Hope Creek Generating Station Technical Specification Bases Changes	Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Primary Containment Isolation System Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling HVAC 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 Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Room Envelope Rod Worth Minimizer Control rod blade Main Condenser Control Rod Main Steam Containment Spray Low Pressure Coolant Injection Main Turbine Bypass System
ML23067A185	29 December 2022	Callaway	Rev. 18 to Technical Specification, Bases Change, Chapter B 3.9, Refueling Operations	Reactor Coolant System Service water Reactor Pressure Vessel Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Rod
ML23067A152	29 December 2022	Callaway	67, 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
ML23067A157	29 December 2022	Callaway	Technical Specifications, Chapter 3.3, Instrumentation	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Control Room Emergency Ventilation Remote shutdown Containment Spray
ML21242A216	21 December 2022	Diablo Canyon	Issuance of Amendment Nos. 243 and 244 Technical Specifications and Revised License Conditions for the Permanently Defueled Condition (EPID: L-2020-LLA-0261	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Residual Heat Removal Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Control Rod Containment Spray Control Room Emergency Air Temperature Control System
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