TS-3.5.2

TS-3.5.2

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
ENS 57952	25 September 2025 17:29:00	South Texas	Two Trains of ECCS Inoperable	Emergency Core Cooling System
ML25265A043	25 September 2025	Vogtle	Summary of September 17, 2025, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc., Proposed LAR for (1) Risk-Informed Completion Time Program, (2) 10 Cfr 50.69, and (3) Surveillance Frequency Control Progra
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
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
L-2025-149, Response to Requests for Additional Information Regarding Seabrook License Amendment Requests to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Time - RITSTF Initiative 4b, and 10 CFR 50.69.	5 September 2025	Seabrook	Response to Requests for Additional Information Regarding Seabrook License Amendment Requests to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Time - RITSTF Initiative 4b, and 10 CFR 50.69.	Steam Generator Feedwater Emergency Diesel Generator Primary containment Main Steam Line Containment Spray
ML25241A086	4 September 2025	Harris	Duke Energy Pre-submittal Meeting September 4, 2025	Reactor Coolant System Service water Emergency Diesel Generator Auxiliary Feedwater HVAC Emergency Core Cooling System Containment Spray
2CAN092501, Request to Revise Typographical Errors in Technical Specifications	4 September 2025	Arkansas Nuclear	Request to Revise Typographical Errors in Technical Specifications	Reactor Coolant System Shutdown Cooling Containment Spray
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
GO2-25-091, License Amendment Request to Revise Technical Specification to Adopt TSTF-599, Eliminate Periodic Surveillance Test of Simultaneous Start of Redundant Diesel Generators	2 September 2025	Columbia	License Amendment Request to Revise Technical Specification to Adopt TSTF-599, Eliminate Periodic Surveillance Test of Simultaneous Start of Redundant Diesel Generators
ML25240B502	28 August 2025	Washington State University	Transmittal of 2025 Annual Report for the Wsu Nuclear Science Center	Control Rod
ML25224A234	15 August 2025	Vogtle	Summary of August 11, 2025, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc., a Proposed Emergency License Amendment Request to Change Technical Specification 3.5.2	Steam Generator Reactor Coolant System Feedwater
ML25225A229	15 August 2025	Vogtle	Issuance of Emergency Amendment No. 202 to Revise Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating (Emergency Circumstances)	Steam Generator Reactor Coolant System Residual Heat Removal Automatic Depressurization System Emergency Core Cooling System Control Rod
ML25224A250	12 August 2025	Vogtle	NRR E-mail Capture - for Your Action - RAIs - Vogtle 4 - Emergency License Amendment Request (LAR) Regarding Core Makeup Tanks (L-2025-LLA-0127)	Reactor Coolant System
NL-25-0318, Response to NRC Requests Regarding Emergency License Amendment Request One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating	12 August 2025	Vogtle	Response to NRC Requests Regarding Emergency License Amendment Request One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating	Reactor Coolant System
IR 05000298/2025002	11 August 2025	Cooper	Integrated Inspection Report 050002982025002	Reactor Coolant System Feedwater Secondary containment Service water Reactor Protection System Emergency Diesel Generator Reactor Core Isolation Cooling Primary containment Reactor Pressure Vessel Residual Heat Removal Residual Heat Removal Service Water Emergency Core Cooling System Main Condenser Control Rod Containment Spray
ML25223A299	11 August 2025	Vogtle	SNC Slides - SNC Presentation - Public Meeting on August 11, 2025 - Proposed Emergency Vogtle 4 SR 3.5.2.4 LAR	Steam Generator Feedwater Emergency Core Cooling System
NL-25-0317, Emergency License Amendment Request: One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating	11 August 2025	Vogtle	Emergency License Amendment Request: One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating	Steam Generator Reactor Coolant System Feedwater Residual Heat Removal Automatic Depressurization System Emergency Core Cooling System
ML25224A170	11 August 2025	05000026	SNC Slides - SNC Presentation - Public Meeting on August 11, 2025 - Proposed Emergency Vogtle 4 SR 3.5.2.4 LAR -	Steam Generator Reactor Coolant System Feedwater Residual Heat Removal Emergency Core Cooling System
IR 05000440/2025002	7 August 2025	Perry	Integrated Inspection Report 05000440/2025002	Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Main Transformer Shutdown Cooling Reactor Recirculation Pump Reactor Pressure Vessel High Pressure Core Spray Core Spray Residual Heat Removal Reactor Water Cleanup Fuel Pool Cooling and Cleanup Circulating Water System Stator Cooling Water Emergency Core Cooling System Main Steam Line Control Rod Main Steam
RS-25-110, Constellation Energy Generation, Llc., Application to Revise Technical Specifications to Adopt TSTF-599, Revision 1, Eliminate Periodic Surveillance Test of Simultaneous Start of Redundant Diesel Generators	5 August 2025	Dresden Peach Bottom Nine Mile Point Byron Braidwood Limerick Clinton Quad Cities LaSalle	Constellation Energy Generation, Llc., Application to Revise Technical Specifications to Adopt TSTF-599, Revision 1, Eliminate Periodic Surveillance Test of Simultaneous Start of Redundant Diesel Generators	Secondary containment Emergency Diesel Generator Reactor Pressure Vessel Emergency Core Cooling System Containment Spray
ML25195A314	30 July 2025		EAI-RIII-2025-0085 - J. Meyers Notice of Violation and NRC Inspection Report No. 05000254/2024403	Reactor Pressure Vessel Control Rod
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program	10 July 2025	Beaver Valley Davis Besse Perry Comanche Peak	Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program	Steam Generator Reactor Coolant System Feedwater Secondary containment Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Reactor Core Isolation Cooling Primary containment Residual Heat Removal Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Condenser Control Rod Main Steam Containment Spray
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
ML25171A122	20 June 2025	Seabrook	Risk-Informed Completion Time TSTF-505 and 10 CFR 50.69 Audit Questions (EPIDs L-2025-LLA-0025, L-2025-LLA-0058)	Reactor Protection System Containment Spray
05000254/LER-2025-004, Loss of Suppression Chamber Vacuum Breaker Safety Function Due to Configuration Control Error	4 June 2025	Quad Cities	Loss of Suppression Chamber Vacuum Breaker Safety Function Due to Configuration Control Error	Secondary containment Primary containment Reactor Pressure Vessel
ML25147A134	4 June 2025	Beaver Valley	– Correction to Issuance of Amendments 325 and 215, to Revise Technical Specifications to Delete Note 4 for LCO 3.5.2 and Correct Typographical Errors in the Titles of Topical Reports
ML25126A076	30 May 2025	Palo Verde	Issuance of Amendment Nos. 225, 225 and 225, Regarding Revision Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands and Use Gothic Code	Reactor Coolant System Shutdown Cooling Emergency Core Cooling System Decay Heat Removal Containment Spray
ML25094A166	22 May 2025	05200050	SDAA - FSER Chapter 15 - Transient and Accident Analyses	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Main Steam Isolation Valve Residual Heat Removal Emergency Core Cooling System Decay Heat Removal 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
05000440/LER-2025-001, Automatic Actuation of Division 3 Diesel Generator Resulting from Startup Transformer Testing	21 May 2025	Perry	Automatic Actuation of Division 3 Diesel Generator Resulting from Startup Transformer Testing	Service water Emergency Diesel Generator High Pressure Core Spray Residual Heat Removal Emergency Core Cooling System Decay Heat Removal
ML25119A052	15 May 2025	Palo Verde	Regulatory Audit Summary Report in Support of License Amendment Request to Revise TSs 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands and to Use Gothic Code
LR-N24-0029, Enclosure 1: Contents of the Hope Creek Improved Technical Specifications (ITS) Submittal	14 May 2025	Hope Creek	Enclosure 1: Contents of the Hope Creek Improved Technical Specifications (ITS) Submittal	Reactor Coolant System Secondary containment Reactor Core Isolation Cooling Shutdown Cooling Reactor Pressure Vessel Reactor Water Cleanup Automatic Depressurization System Standby Liquid Control Emergency Core Cooling System Control Rod
ML25134A164	14 May 2025	Hope Creek	Enclosure 2, Volume 10: Hope Creek Generating Station - Improved Technical Specifications Conversion ITS Section 3.5 Emergency Core Cooling Systems (Eccs), RPV Water Inventory Control, and Reactor Core Isolation Cooling (RCIC) System	Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Pressure Vessel Core Spray Residual Heat Removal Automatic Depressurization System Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control rod blade Control Rod Containment Spray Low Pressure Coolant Injection
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
IR 05000348/2025001	13 May 2025	Farley 07200042	Joseph M Farley Nuclear Plant - Integrated Inspection Report 05000348/2025001, 05000364/2025001 and 07200042/2025001	Steam Generator Feedwater Service water Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System Containment Spray
ML25114A211	6 May 2025	Quad Cities	NRC Inspection Report No. 05000254/2024403 and Investigation Reports 3-2023-013 and 3-2023-0015	Feedwater Reactor Pressure Vessel Control Rod
CNL-25-057, Response to Request for Confirmation of Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2, TS LCO 3.5.2, Note 1	22 April 2025	Watts Bar Sequoyah	Response to Request for Confirmation of Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2, TS LCO 3.5.2, Note 1	Residual Heat Removal Emergency Core Cooling System
ML25078A036	11 April 2025	Beaver Valley	Issuance of Amendment to Revise Technical Specifications to Delete Note 4 for Limiting Condition for Operation (LCO) 3.5.2 and Correct Typographical Errors in the Titles of Topical Reports (Trs)	Emergency Core Cooling System
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
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
05000498/LER-2025-001, Two Inoperable Emergency Core Cooling System Trains Resulting in Potential Loss of Safety Function	7 April 2025	South Texas	Two Inoperable Emergency Core Cooling System Trains Resulting in Potential Loss of Safety Function	HVAC Emergency Core Cooling System Control Room Envelope
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
ML25090A018	28 March 2025	Palo Verde	Supplement to License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code	Emergency Core Cooling System
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
ML25029A125	26 March 2025	05200050	US460 SDAA Chapter 15 SER	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Main Steam Isolation Valve HVAC Reactor Pressure Vessel Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Room Envelope Control Rod Main Steam
ML25085A273	25 March 2025	Watts Bar Sequoyah	Request for Confirmation of Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, TS LCO 3.5.2, Note 1	Residual Heat Removal Emergency Core Cooling System
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T	14 March 2025	Byron Braidwood	License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T	Steam Generator Reactor Coolant System Residual Heat Removal Decay Heat Removal Control Rod
05000254/LER-2025-001, Technical Specification 3.6.4.2 Action Not Performed Due to Tagout Boundary Placement Error	7 March 2025	Quad Cities	Technical Specification 3.6.4.2 Action Not Performed Due to Tagout Boundary Placement Error	Secondary containment Primary containment Reactor Building Ventilation
ML24347A075	6 March 2025	University of California - Irvine	Examination Report Letter No. 50-326/OL-25-01, University of California - Irvine	Emergency Diesel Generator Control Rod
L-2025-020, License Amendment Request 279, Extend Surveillance Test Intervals in Support of Transition to 24 Month Fuel Cycles	3 March 2025	Turkey Point	License Amendment Request 279, Extend Surveillance Test Intervals in Support of Transition to 24 Month Fuel Cycles	Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Auxiliary Feedwater Main Turbine Residual Heat Removal Control Room Emergency Ventilation Emergency Core Cooling System Main Steam Line Control Room Envelope Containment Spray
ENS 57561	19 February 2025 09:24:00	South Texas	Two of Three ECCS Trains Declared Inoperable	Emergency Core Cooling System Containment Spray
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