TS-3.3.4

TS-3.3.4

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
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
IR 05000424/2025002	9 July 2025	Vogtle	Integrated Inspection Report 05000424/2025002 and 05000425/2025002	Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Auxiliary Feedwater Remote shutdown
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
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
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
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
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
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	31 December 2024	Diablo Canyon	License Amendment Request 24-06, Revision to Technical Specification 1.1 and Addition of 5.5.21 to Use Online Monitoring Methodology	Steam Generator Reactor Coolant System Remote shutdown
ML24326A109	21 November 2024	05200050	Response to NuScale Technical Report Audit Question Number: A-16.3.3.1-7	Emergency Core Cooling System Decay Heat Removal
ML24326A111	21 November 2024	05200050	Response to NuScale Technical Report Audit Question Number: A-16.3.3.1-9	Control Rod
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)	4 November 2024	Watts Bar Sequoyah	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)	Steam Generator Reactor Coolant System Feedwater Primary containment Remote shutdown Emergency Core Cooling System
ML24059A425	14 August 2024	Harris	Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications	Steam Generator Feedwater Auxiliary Feedwater Primary containment Remote shutdown Control Rod
ML24215A193	2 August 2024	05200050	LLC, Response to SDAA Audit Question Number A-16.3.3.1-5	Steam Generator Reactor Coolant System Feedwater Reactor Pressure Vessel Emergency Core Cooling System Decay Heat Removal Main Steam
05000445/LER-2024-002, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions	3 June 2024	Comanche Peak	(Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions	Emergency Diesel Generator Remote shutdown 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
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
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	3 May 2024	Hatch Farley	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	Reactor Coolant System Feedwater Reactor Protection System Primary containment Main Turbine Remote shutdown Emergency Core Cooling System Control Rod
ML24031A622	28 February 2024	Vallecitos Nuclear Center	General Electric Nuclear Energy Americas, LLC - Issuance of Amendment No. 26 Possession-Only Authorization of the Reactor and Fuel for Renewed Facility Operating License No. R-33 for the Nuclear Test Reactor	Reactor Coolant System Control Rod
IR 05000483/2023002	21 February 2024	Callaway	Amended Integrated Inspection Report 05000483/2023002	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Auxiliary Feedwater Main Transformer Remote shutdown Safety Relief Valve Containment Spray
ML24026A196	26 January 2024	Vallecitos Nuclear Center	GEH - Response to NRC Request for Additional Information	Reactor Coolant System Control Rod
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
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
ML23332A105	7 December 2023	University of Texas at Austin	University of Texas at Austin - Regulatory Audit Re Renewal of Facility Operating License No. R-129 for Its Triga Mark II Nuclear Reactor	HVAC Control Rod
RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific	6 November 2023	Harris	Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific	Steam Generator Service water Auxiliary Feedwater Remote shutdown Decay Heat Removal
ML23304A387	31 October 2023	05200050	LLC Revision 1 to Standard Design Approval Application, Part 4, US460 Generic Technical Specifications, Vol. 1	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
ML23279A110	6 October 2023	Vallecitos Nuclear Center	GEH License Amendment Request - Permanent Cessation of the GE Nuclear Test Reactor (Ntr) and Possession Only Authorization	Reactor Coolant System Control Rod
ML23275A120	2 October 2023	Saint Lucie	Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10	Steam Generator Reactor Coolant System Feedwater Shutdown Cooling Emergency Core Cooling System Control Rod Containment Spray
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
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
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .	4 August 2023	Nine Mile Point	Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .	Reactor Coolant System Feedwater Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling HVAC Core Spray Residual Heat Removal Reactor Water Cleanup Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Residual Heat Removal Service Water Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Condenser Control Rod Main Steam Containment Spray Main Turbine Bypass System
ML23208A213	3 August 2023	Arkansas Nuclear	Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23158A206	19 July 2023	Vogtle	LAR-23-005 U/4 Amd 189 Timing of TS Effectiveness Prior to Initial Criticality Safety Evaluation	Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Residual Heat Removal Automatic Depressurization System Decay Heat Removal
ML23192A441	10 July 2023	Callaway	Integrated Inspection Report 05000483/2023002	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Auxiliary Feedwater Main Transformer Remote shutdown Safety Relief Valve Containment Spray
RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications	31 May 2023	Harris	License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications	Steam Generator Reactor Coolant System Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Primary containment Residual Heat Removal Control Room Emergency Filtration System Remote shutdown Emergency Core Cooling System Control Rod Containment Spray
IR 05000317/2023001	24 April 2023	Calvert Cliffs	Integrated Inspection Report 05000317/2023001 and 05000318/2023001	Steam Generator Reactor Coolant System Service water Emergency Diesel Generator Auxiliary Feedwater Shutdown Cooling Reactor Pressure Vessel Remote shutdown Emergency Core Cooling System Main Steam Line Containment Spray
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
L-23-036, Report of Facility Changes, Tests and Experiments	13 March 2023	Beaver Valley	Report of Facility Changes, Tests and Experiments
ML23052A129	21 February 2023	Beaver Valley	Report of Facility Changes, Tests and Experiments
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
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
NL-22-0764, – Units 1 & 2, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology	21 December 2022	Vogtle	– Units 1 & 2, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology	Steam Generator Reactor Coolant System Remote shutdown
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
1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation	31 October 2022	Arkansas Nuclear	Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Main Turbine Emergency Core Cooling System Decay Heat Removal Control Rod
ML22251A021	10 August 2022	Cook	Form 2.3-3 Operating Test Review Worksheet DC-Cook 2022	Steam Generator Feedwater Main Turbine Remote shutdown Stator Cooling Water Control Rod Auxiliary Feed Water Main Steam
ML22119A094	21 June 2022	Ginna	R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 150 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 Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Reactor Core Isolation Cooling Primary containment Main Turbine Residual Heat Removal Emergency Core Cooling System Control Rod Containment Spray
ML23019A253	8 June 2022	Technical Specifications Task Force	Draft of Revision 2 of Traveler TSTF-576, 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
ML22140A139	20 May 2022	Point Beach	Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Emergency Core Cooling System Containment Spray
ML21251A544	7 October 2021	LaSalle	Correction Letter - Issuance of Amendment Nos. 251 and 237 Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
ML21265A286	15 September 2021	Saint Lucie	Enclosure 2 - Volume 1 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion Application of Selection Criteria to the St. Lucie Plant Units 1 and 2 Technical Specifications, Revision 0	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
ML21265A299	15 September 2021	Saint Lucie	Enclosure 2 - Volume 14 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.9 Refueling Operations, Revision 0	Reactor Coolant System Secondary containment Reactor Protection System Shutdown Cooling Reactor Pressure Vessel Control Room Emergency Ventilation Emergency Core Cooling System Decay Heat Removal Control Rod
ML21162A069	7 September 2021	LaSalle	Issuance of Amendment Nos. Xxx and Yyy Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2	Feedwater Secondary containment Reactor Protection System Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling HVAC Reactor Pressure Vessel High Pressure Core Spray Core Spray Reactor Building Ventilation Residual Heat Removal Reactor Water Cleanup Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Residual Heat Removal Service Water Emergency Core Cooling System Main Steam Line Control Rod Main Steam
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1	23 June 2021	Technical Specifications Task Force	TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1	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 Intermediate Range Monitor Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Rod Main Steam Containment Spray
ML21194A271	22 June 2021	Callaway	Technical Specification Bases, 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
ML21194A275	22 June 2021	Callaway	Technical Specification, Chapter 3.3, Instrumentation	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Control Room Emergency Ventilation Remote shutdown Containment Spray
ML21152A110	1 June 2021	Palisades	Evaluation of the Proposed Changes	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Primary containment Shutdown Cooling HVAC Reactor Pressure Vessel Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Main Steam Line Control Room Envelope Control Rod Containment Spray
ML21074A000	22 April 2021	Indian Point	Issuance of Amendment No. 270 Permanently Defueled Technical Specifications	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Primary containment Residual Heat Removal Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Control Room Envelope Control Rod Main Steam Containment Spray
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes	19 April 2021	Prairie Island	Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes	Steam Generator Reactor Coolant System Primary containment Residual Heat Removal Shield Building Emergency Core Cooling System Control Room Envelope Control Rod
ML21053A117	8 April 2021	Wolf Creek	1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling Residual Heat Removal Control Room Emergency Ventilation Remote shutdown Emergency Core Cooling System Decay Heat Removal Control Room Envelope Control Rod Containment Spray
ML21049A006	16 March 2021	Nine Mile Point	Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve	Reactor Coolant System Reactor Protection System Primary containment Reactor Pressure Vessel
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