TS-3.1.6

TS-3.1.6

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
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
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
CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)	13 December 2023	Watts Bar	Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Auxiliary Feedwater Residual Heat Removal Intermediate Range Monitor Decay Heat Removal Main Steam Line Control Rod Main Steam
ML23198A012	12 December 2023	05000128	Examination Report Letter No. 50-128/Ol-23-03, Texas A&M University	Control Rod
ML23276B459	12 December 2023	University of California - Irvine	University of California - Irvine, Examination Report Letter No. 50-326/OL-24-01,	Control Rod
WBL-23-055, of the Unit 2 Cycle 6 Core Operating Limits Report	22 November 2023	Watts Bar	of the Unit 2 Cycle 6 Core Operating Limits Report	Control Rod
ML23311A357	7 November 2023	Prairie Island	Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0	Reactor Coolant System Control Rod
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
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
ML23303A136	27 October 2023	Perry	Enclosure C - Pnpp Technical Specification Bases, Revision 18	Reactor Coolant System Feedwater Secondary containment Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Recirculation Pump HVAC Reactor Pressure Vessel High Pressure Core Spray Core Spray Residual Heat Removal Reactor Water Cleanup Shield Building Fuel Pool Cooling and Cleanup Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Remote shutdown Steam Jet Air Ejector Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Room Envelope Main Condenser Control Rod Main Steam Containment Spray Low Pressure Coolant Injection
ML23275A126	2 October 2023	Saint Lucie	Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16	Steam Generator Reactor Coolant System Secondary containment Reactor Protection System Shutdown Cooling Control Room Emergency Ventilation Shield Building Emergency Core Cooling System Decay Heat Removal Safety Relief Valve Control Room Envelope 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
ML23275A117	2 October 2023	Saint Lucie	Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7	Reactor Coolant System Reactor Protection System Control Rod
ML23275A116	2 October 2023	Saint Lucie	Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6	Steam Generator Reactor Coolant System Reactor Protection System Shutdown Cooling Reactor Pressure Vessel Emergency Core Cooling System Main Steam Line Control Rod Main Steam
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
ML23264A041	27 September 2023	Watts Bar	NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides
ML23263A260	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 6 - Appendix a & B
ML23255A253	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Initial Certificate - Appendix a
ML23255A252	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 8 - Appendix a & B
ML23255A251	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 7 - Appendix a & B
ML23255A250	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 6 - Appendix a & B
ML23255A249	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 5 - Appendix a & B
ML23255A248	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 4 - Appendix a & B
ML23255A247	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 3 - Appendix a & B
ML23255A246	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 2 - Appendix a & B
ML23255A245	12 September 2023	07201025	Conditions for Cask Use and Technical Specifications, Renewed Amendment 1 - Appendix a
ML23249A259	6 September 2023	North Anna	Core Operating Limits Report Cycle 30, Pattern Ukr, Revision 0	Reactor Coolant System Emergency Core Cooling System Control Rod
NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483	11 August 2023	Vogtle	Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483	Reactor Coolant System
ML23199A294	9 August 2023	Palo Verde	Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable	Control Rod
IR 05000156/2023201	1 August 2023	University of Wisconsin	University of Wisconsin - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000156/2023201 - Cover Letter and Enclosure
ML23206A050	25 July 2023	Hatch	2A, Exam Final Items (Hatch 2021-301)	Reactor Coolant System Feedwater Secondary containment Service water Emergency Diesel Generator Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Recirculation Pump HVAC Reactor Pressure Vessel Core Spray Reactor Building Ventilation Residual Heat Removal Standby Gas Treatment System Stator Water Cooling Automatic Depressurization System Remote shutdown Emergency Core Cooling System Main Steam Line Rod Worth Minimizer Main Condenser Control Rod Main Steam
NL-23-0611, Core Operating Limits Report, Cycle 11 Version 1	19 July 2023	Vogtle	Core Operating Limits Report, Cycle 11 Version 1
ML22297A281	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Initial Certificate
ML22297A282	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 1
ML22297A283	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 2
ML22297A284	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 3
ML22297A285	14 July 2023	07201025	Preliminary Appendix A- Conditions for Cask Use and Technical Specifications, Renewed Amendment 4
ML22297A286	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 5
ML22297A287	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 6
ML22297A288	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 7
ML22297A289	14 July 2023	07201025	Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 8
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
IR 05000027/2023201	13 June 2023	Washington State University	Washington State University U.S. Nuclear Regulatory Commission Routine Inspection Report 05000027-2023201
PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence	8 June 2023	Susquehanna	Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence	Reactor Protection System Reactor Pressure Vessel Rod Worth Minimizer Control Rod
ML23151A444	24 May 2023	Turkey Point	Enclosure 2, Volume 6: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Core Cooling System Main Steam Line Control Rod Main Steam
ML23151A447	24 May 2023	Turkey Point	Enclosure 2, Volume 9: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 3	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Auxiliary Feedwater Shutdown Cooling Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Condenser Control Rod
ML23144A306	23 May 2023	Beaver Valley	Licensing Requirements Manual, Revision 114	Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Shutdown Cooling Reactor Pressure Vessel Main Steam Safety Valve Emergency Core Cooling System Main Steam Line Main Condenser 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
L-23-125, Cycle 24 Core Operating Limits Report	17 May 2023	Beaver Valley	Cycle 24 Core Operating Limits Report	Reactor Coolant System Control Rod
BW230027, Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 24, Rev. 16	10 May 2023	Braidwood	Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 24, Rev. 16	Reactor Coolant System Control Rod
CP-202300201, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)	4 May 2023	Comanche Peak	(CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)	Reactor Coolant System Control Rod
RA-23-0105, Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core	4 May 2023	Catawba	Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core	Steam Generator Reactor Coolant System
RA-23-0118, Cycle 29, Revision 1, Core Operating Limits Report (COLR)	3 May 2023	McGuire	Cycle 29, Revision 1, Core Operating Limits Report (COLR)	Steam Generator Reactor Coolant System
ML23121A048	1 May 2023	Ginna	R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0	Reactor Coolant System Control Rod
WBL-23-023, of Cycle 19 Core Operating Limit Report	27 April 2023	Watts Bar	of Cycle 19 Core Operating Limit Report	Control Rod
ML23103A195	13 April 2023	Sequoyah	Cycle 26 Core Operating Limits Report Revision 0	Reactor Coolant System Control Rod
... further results

Navigation menu

Search