TS-3.3.3

TS-3.3.3

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
NUREG-2194 Volume 2, Rev. 1, Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 2: Bases	31 January 2024		NUREG-2194, Vol. 2, Rev. 1, Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 2: Bases	Steam Generator Reactor Coolant System Feedwater Service water Main Steam Isolation Valve Primary containment Main Turbine Shutdown Cooling HVAC Reactor Pressure Vessel Residual Heat Removal Shield Building Fuel Pool Cooling and Cleanup Automatic Depressurization System Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam
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 Main Steam Line Main Steam Containment Spray
PMNS20231429, Meeting in Support of License Amendment Review Regarding Neutron Flux Channels	27 December 2023	Cook	Meeting in Support of License Amendment Review Regarding Neutron Flux Channels
ML23317A207	22 December 2023	Vogtle	Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448	Steam Generator Reactor Coolant System Emergency Diesel Generator Emergency Core Cooling System
ULNRC-06850, Special Report 2023-03 Pam Report Inoperability of a Post Accident Monitoring (Pam) Instrument	21 December 2023	Callaway	Special Report 2023-03 Pam Report Inoperability of a Post Accident Monitoring (Pam) Instrument	Reactor Coolant System
AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor	20 December 2023	Cook	Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor	Reactor Coolant System
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report	20 December 2023	Prairie Island	Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report	Steam Generator Reactor Coolant System
CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation	12 December 2023	Comanche Peak	(Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation
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
LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days	7 December 2023	Salem	Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days	Main Steam Line
L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles	15 November 2023	Turkey Point	License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles	Steam Generator Reactor Coolant System Feedwater High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Reactor Core Isolation Cooling Primary containment Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Control Room Emergency Ventilation Main Steam Safety Valve Emergency Core Cooling System Main Steam Line Main Condenser Control Rod Main Steam Containment Spray
WBL-23-052, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual	8 November 2023	Watts Bar	Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater HVAC Auxiliary Building Gas Treatment System Residual Heat Removal Control Room Emergency Ventilation Shield Building Main Steam Safety Valve Remote shutdown Emergency Gas Treatment System Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
WBL-23-045, 10 CFR 50.59 Summary Report	7 November 2023	Watts Bar	10 CFR 50.59 Summary Report	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Main Turbine HVAC Residual Heat Removal Shield Building Main Steam Safety Valve Emergency Core Cooling System Control Rod Main Steam
ML23310A051	6 November 2023	Callaway	EIP-ZZ.OO1O1, Addendum 2, Revision 22, Emergency Action Level Technical Bases Document	Steam Generator Reactor Coolant System Feedwater Secondary containment Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Primary containment Main Transformer Shutdown Cooling Safety Parameter Display System Reactor Pressure Vessel Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray
LR-N23-0072, Core Operating Limits Report Cycle 30	1 November 2023	Salem	Core Operating Limits Report Cycle 30	Reactor Coolant System Control Rod
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
ML23304A388	31 October 2023	05200050	LLC Revision 1 to Standard Design Approval Application, Part 4, US460 Generic Technical Specifications, Vol. 2	Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Shutdown Cooling Reactor Pressure Vessel Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam
ML23278A095	5 October 2023	Callaway	EIP-ZZ-00101 Addendum 2 - Emergency Action Level Technical Bases Document Administrative Correction Revision 021	Steam Generator Reactor Coolant System Feedwater Secondary containment Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Primary containment Main Transformer Shutdown Cooling Safety Parameter Display System Reactor Pressure Vessel Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray
ML23276B455	3 October 2023	Wolf Creek	Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report	Reactor Coolant System Reactor Protection System
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
ML23275A118	2 October 2023	Saint Lucie	Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Turbine Shutdown Cooling Control Room Emergency Ventilation Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Main Steam 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
ML23275A110	2 October 2023	Saint Lucie	License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Primary containment Shutdown Cooling Reactor Pressure Vessel Control Room Emergency Ventilation Shield Building Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Control Room Envelope Control Rod Containment Spray
ML23198A359	2 October 2023	Beaver Valley	Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary	Steam Generator Reactor Coolant System Feedwater Main Steam Safety Valve Emergency Core Cooling System Control Rod
ML23151A347	21 August 2023	Calvert Cliffs Nine Mile Point	Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration	Steam Generator Primary containment Safety Relief Valve
ML23188A129	26 July 2023	Braidwood	Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1	Steam Generator
ML23212A944	11 July 2023	North Anna	Post Accident Monitoring Report	Main Steam
ML23128A354	30 June 2023	Vallecitos Nuclear Center	GEH Ntr Appendix a, Technical Specifications	Reactor Coolant System Control Rod
ML23173A105	22 June 2023	Summer	Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel
RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications	19 June 2023	Catawba	License Amendment Application to Revise Control Room Cooling Technical Specifications	Control Room Emergency Filtration System Emergency Core Cooling System Control Room Envelope
ML23165A219	13 June 2023	Vogtle	Enclosure 9: Vogtle Electric Generating Plant, Units 3 and 4, Technical Specifications Bases, Revision 73	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Primary containment Main Turbine Shutdown Cooling HVAC Reactor Pressure Vessel Residual Heat Removal Shield Building Fuel Pool Cooling and Cleanup Automatic Depressurization System Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Condenser Control Rod Main Steam
ML23262B196	7 June 2023		Meeting Slides 20230607-final	Standby Gas Treatment System
ML23151A446	24 May 2023	Turkey Point	Enclosure 2, Volume 8: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 3	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Turbine Shutdown Cooling Residual Heat Removal Control Room Emergency Ventilation Control Room Emergency Filtration System Remote shutdown Qualified Safety Parameter Display System Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Rod Main Steam Containment Spray
ML23144A307	23 May 2023	Beaver Valley	Technical Specification Bases Update Status, Revision 47	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Transformer Main Turbine Shutdown Cooling Residual Heat Removal Control Room Emergency Ventilation Fuel Pool Cooling and Cleanup Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
ML23123A330	3 May 2023	Summer	Core Operating Limits Report, Cycle 28, Revision 0	Reactor Coolant System Feedwater Control Rod
DCL-23-025, 2022 Annual Radioactive Effluent Release Report	1 May 2023	Diablo Canyon	2022 Annual Radioactive Effluent Release Report	Steam Generator Main Condenser Control Rod
LR-N23-0033, Core Operating Limits Report Cycle 27	26 April 2023	Salem	Core Operating Limits Report Cycle 27	Reactor Coolant System Control Rod
RA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change	24 April 2023	Catawba	Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change	Steam Generator Reactor Coolant System Feedwater Secondary containment Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine HVAC Residual Heat Removal Circulating Water System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray
ML23103A228	12 April 2023	Millstone Surry North Anna	Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Core Cooling System Main Steam Line Control Rod Main Steam
NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483	11 April 2023	Vogtle	License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Safety Valve Emergency Core Cooling System
2CAN042301, 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 4	5 April 2023	Arkansas Nuclear	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 4	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Turbine Shutdown Cooling HVAC Control Room Emergency Ventilation Main Steam Safety Valve Emergency Core Cooling System Decay Heat Removal Main Steam Line Containment Spray
PNP 2023-002, 6 to Updated Final Safety Analysis Report	31 March 2023	Palisades	6 to Updated Final Safety Analysis Report	Steam Generator Feedwater Service water Auxiliary Feedwater Main Transformer Shutdown Cooling HVAC Core Spray Circulating Water System Main Steam Safety Valve Emergency Core Cooling System Main Steam Line Control Rod Main Steam Containment Spray
ML23166B146	31 March 2023	Vallecitos Nuclear Center	GEH Responses to OGC Comments on Ntr Appendix a Technical Specifications	Reactor Coolant System Control Rod
ML23086C026	31 March 2023	Vallecitos Nuclear Center	Enclosure 2: Nedo 32765, Revision 6, Technical Specifications for the Nuclear Test Reactor Facility R-33	Reactor Coolant System Control Rod
ML23086C025	24 March 2023	Vallecitos Nuclear Center	Enclosure 1: NRC Ntr License Renewal Audit Questions
ML23088A254	23 March 2023	Callaway	EIP-ZZ-00101, Addendum 2, Revision 020, Emergency Action Level Technical Bases Document	Steam Generator Reactor Coolant System Feedwater Secondary containment Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Primary containment Main Transformer Shutdown Cooling Safety Parameter Display System Reactor Pressure Vessel Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray
ML23089A028	10 March 2023	07201026	FOIA-2023-000071 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed
ML23060A245	9 March 2023		Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 21, 2023	Reactor Coolant System Secondary containment Primary containment Control Room Emergency Filtration System Main Steam Line
ML23054A324	28 February 2023	Vallecitos Nuclear Center	Nedo 32765, Revision 5, Technical Specifications for the Nuclear Test Reactor Facility License R-33	Reactor Coolant System Control Rod
ML23054A321	23 February 2023	Vallecitos Nuclear Center	GEH Supplemental Information for Ntr License Renewal Application	Reactor Coolant System Control Rod
ML23052A150	21 February 2023	Cook	NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request Regarding Neutron Flux Instrumentation
ML23052A023	17 February 2023	Limerick	License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation	Reactor Coolant System Feedwater 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 Intermediate Range Monitor Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Rod Main Steam Low Pressure Coolant Injection
IR 05000390/2022004	10 February 2023	Watts Bar	Integrated Inspection Report 05000390/2022004 and 05000391/2022004	Steam Generator Feedwater Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Emergency Gas Treatment System Emergency Core Cooling System Safety Relief Valve Control Rod Containment Spray
RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)	30 January 2023	Robinson	Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)
AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation	26 January 2023	Cook	Request for Approval of Change Regarding Neutron Flux Instrumentation	Steam Generator Reactor Coolant System Auxiliary Feedwater
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