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
NL-25-0378, Core Operating Limits Report, Cycle 2	14 October 2025	Vogtle	Core Operating Limits Report, Cycle 2
ML25281A193	8 October 2025	North Anna	Core Operating Limits Report, Cycle 32, Pattern GOP, Revision 0	Reactor Coolant System Emergency Core Cooling System Control Rod
GO2-25-117, Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia TS 3.3.2.1, Control Rod Block Instrumentation	29 September 2025	Columbia	Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia TS 3.3.2.1, Control Rod Block Instrumentation	Reactor Pressure Vessel Rod Worth Minimizer Control Rod
IR 05000243/2025201	24 September 2025	Oregon State University	Oregon State University - U.S. Nuclear Regulatory Commission Safety Inspection Report 05000243/2025201	Control Rod
BW250041, Core Operating Limits Report, Cycle 25, Revision 21	24 September 2025	Braidwood	Core Operating Limits Report, Cycle 25, Revision 21	Reactor Coolant System Control Rod
ML25260A487	17 September 2025	Technical Specifications Task Force 99902042	Correction to TSTF-585, Revision 5, Revise LCO 3.0.3 to Require Managing Risk	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater High Pressure Core Spray Residual Heat Removal Circulating Water System Emergency Core Cooling System Decay Heat Removal Main Steam Line
TSTF-25-06, TSTF Response to NRC Request for Additional Information on TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk and Transmittal of Revision 5	10 September 2025	Technical Specifications Task Force 99902042	TSTF Response to NRC Request for Additional Information on TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk and Transmittal of Revision 5	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater High Pressure Core Spray Residual Heat Removal Circulating Water System Emergency Core Cooling System Decay Heat Removal Main Steam Line
RA-25-0217, Core Operating Limits Report (COLR) for Unit 2 Cycle 28 Reload Core	4 September 2025	Catawba	Core Operating Limits Report (COLR) for Unit 2 Cycle 28 Reload Core	Steam Generator Reactor Coolant System
NLS2025035, Application to Revise Technical Specifications to Adopt TSTF-576, Revise Safety/Relief Valve Requirements	23 August 2025	Cooper	Application to Revise Technical Specifications to Adopt TSTF-576, Revise Safety/Relief Valve Requirements	Reactor Coolant System Secondary containment Service water Reactor Protection System Main Steam Isolation Valve Primary containment Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Automatic Depressurization System Residual Heat Removal Service Water Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Rod Main Steam Containment Spray Main Turbine Bypass System
ML25153A008	21 August 2025	Byron Braidwood	Units, 1 and 2 - Issuance of Amendments to Revise Technical Specifications to Use Framatome Gaia Fuel (EPID L-2024-LLA-0072) (NON-PROPRIETARY)	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Primary containment Reactor Pressure Vessel Residual Heat Removal Control Room Emergency Ventilation Emergency Core Cooling System Main Steam Line Control Rod Containment Spray
DCL-25-055, Core Operating Limits Report for Unit 1 Cycle 26	9 July 2025	Diablo Canyon	Core Operating Limits Report for Unit 1 Cycle 26	Reactor Coolant System Control Rod
ML25142A334	22 May 2025	07201052	Enclosure 3, Responses, Letter Dated 5/22/25 from Fkrattner and Dbussmann (Gns) to Dfm, Director (Nrc), Castor geo69 Dry Storage System-Submission of Response to Supplemental RAIs and Revised SAR
ML25094A152	22 May 2025	05200050	SDAA - FSER Chapter 4 - Reactor	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Reactor Pressure Vessel Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Rod Main Steam
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
ML25140A128	20 May 2025	Ginna	License Amendment Request to Extend the Completion Time for Sodium Hydroxide System	Steam Generator Reactor Coolant System Residual Heat Removal Emergency Core Cooling System Containment Spray
WBL-25-030, Of the Unit 2 Cycle 7 Core Operating Limits Report (COLR)	13 May 2025	Watts Bar	Of the Unit 2 Cycle 7 Core Operating Limits Report (COLR)	Reactor Coolant System Control Rod
CP-202500130, (CPNPP) - Core Operating Limits Report (Colr), Unit 1 Cycle 25, (ERX-25-001, Revision O & 1)	7 May 2025	Comanche Peak	(CPNPP) - Core Operating Limits Report (Colr), Unit 1 Cycle 25, (ERX-25-001, Revision O & 1)	Reactor Coolant System Control Rod
WBL-25-027, Of the Unit 1 Cycle 20 Core Operating Limits Report (COLR) and Revision 0 of the Unit 2 Cycle 7 COLR	6 May 2025	Watts Bar	Of the Unit 1 Cycle 20 Core Operating Limits Report (COLR) and Revision 0 of the Unit 2 Cycle 7 COLR	Reactor Coolant System Control Rod
NL-25-0125, Core Operating Limits Report, Cycle 1, Version 2	25 April 2025	Vogtle	Core Operating Limits Report, Cycle 1, Version 2
BYRON 2025-0027, Cycle 26 Core Operating Limits Report	24 April 2025	Byron	Cycle 26 Core Operating Limits Report	Reactor Coolant System Control Rod
RA-25-0114, (Mns), Unit 1 - Cycle 31, Revision 0, Core Operating Limits Report (COLR)	23 April 2025	McGuire	(Mns), Unit 1 - Cycle 31, Revision 0, Core Operating Limits Report (COLR)	Steam Generator Reactor Coolant System
ML25113A120	22 April 2025	North Anna	Cycle 31, Pattern Dsy, Revision 0	Reactor Coolant System Emergency Core Cooling System Control Rod
L-2025-069, Cycle 35 Core Operating Limits Report	9 April 2025	Turkey Point	Cycle 35 Core Operating Limits Report	Reactor Coolant System Control Rod
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
ML25083A285	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 6, Revision 1, Appendices a and B
ML25083A291	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 9, Appendices a and B
ML25083A287	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 7, Revision 1, Appendices a and B
ML25083A289	7 April 2025	07201025	Renewed CoC No. 1025, Amendment No. 8, Revision 1, Appendices a and B
L-2025-051, Core Operating Limits Report (COLR) Unit 1 Cycle 43 (U 1 C43)	4 April 2025	Point Beach	Core Operating Limits Report (COLR) Unit 1 Cycle 43 (U 1 C43)	Reactor Coolant System Feedwater
RA-25-0086, Cycle 30, Revision 1, Core Operating Limits Report (COLR)	27 March 2025	McGuire	Cycle 30, Revision 1, Core Operating Limits Report (COLR)	Steam Generator Reactor Coolant System
ML24338A158	26 March 2025	05200050	US460 SDAA Chapter 4 SER	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Reactor Pressure Vessel Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Rod Main Steam
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
L-PI-25-011, Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 1, Cycle 34, Revision 1	20 March 2025	Prairie Island	Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 1, Cycle 34, Revision 1	Reactor Coolant System Control Rod
ML24352A075	19 March 2025	Byron Braidwood	Issuance of Amendments Nos. 239, 239, 238, and 238 Regarding Removal of Power Distribution Monitoring System (Pdms) Details from Technical Specifications	Reactor Protection System Control Rod
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
CNL-25-039, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-576	10 March 2025	Browns Ferry	Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-576	Reactor Coolant System Main Steam Isolation Valve Main Turbine Reactor Pressure Vessel Residual Heat Removal Automatic Depressurization System Emergency Core Cooling System Main Steam Line Control Rod
ML25066A098	7 March 2025	Technical Specifications Task Force 99902042	Transmittal of TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater High Pressure Core Spray Residual Heat Removal Circulating Water System Emergency Core Cooling System Decay Heat Removal Main Steam Line
ML25042A102	12 February 2025	Vogtle	Integrated Inspection Report 05200025/2024004 and 05200026/2024004	Steam Generator Reactor Coolant System Feedwater Reactor Protection System Residual Heat Removal Control Room Emergency Ventilation Automatic Depressurization System Main Steam Safety Valve Decay Heat Removal
PNP 2025-003, License Amendment Request to Revise Selected Permanently Defueled Technical Specifications to Support Repairing of Steam Generator Tubes by Sleeving	11 February 2025	Palisades	License Amendment Request to Revise Selected Permanently Defueled Technical Specifications to Support Repairing of Steam Generator Tubes by Sleeving	Steam Generator Reactor Coolant System Feedwater HVAC Reactor Pressure Vessel Main Steam Safety Valve Emergency Core Cooling System Main Steam Line Main Steam Containment Spray
ML24242A049	10 February 2025	07201025	3. Proposed Renewed CoC No. 1025 Amendment No. 6 Revision 1, Appendices a and B
ML24242A055	10 February 2025	07201025	9. Proposed Renewed CoC No. 1025 Amendment No. 9, Appendices a and B
ML24242A053	10 February 2025	07201025	7. Proposed Renewed CoC No. 1025 Amendment No. 8 Revision 1, Appendices a and B
ML25027A018	26 January 2025	Columbia	Pre-Application Teleconference Slides for RWM -	Rod Worth Minimizer Control Rod
ML25023A057	23 January 2025	Sequoyah	Cycle 27 Core Operating Limits Report Revision 2	Reactor Coolant System Control Rod
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
ML24285A207	17 December 2024	Watts Bar	Amendment Nos. 170 and 76 Regarding the Revision of Technical Specifications 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, and 5.9.5 by Adopting Various Technical Specifications Task Force Travelers	Steam Generator Reactor Coolant System Feedwater Safety Parameter Display System Emergency Core Cooling System Control Rod
CNL-24-049, Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements	9 December 2024	Browns Ferry	Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements	Reactor Coolant System Main Steam Isolation Valve Main Turbine Reactor Pressure Vessel Residual Heat Removal Automatic Depressurization System Emergency Core Cooling System Main Steam Line Control Rod
ML24337A013	2 December 2024	Wolf Creek	Cycle 27 Core Operating Limits Report, Revision 1	Reactor Coolant System
NL-24-0408, Unit 3, Core Operating Limits Report, Cycle 2, Version 1	21 November 2024	Vogtle	Unit 3, Core Operating Limits Report, Cycle 2, Version 1
WBL-24-050, Of Cycle 20 Core Operating Limits Report (COLR)	19 November 2024	Watts Bar	Of Cycle 20 Core Operating Limits Report (COLR)	Control Rod
ML24255A044	15 November 2024	05000128	Examination Report Letter No. 50-128/OL-25-01, Texas A&M University	Control Rod
L-24-254, Cycle 25 Core Operating Limits Report	15 November 2024	Beaver Valley	Cycle 25 Core Operating Limits Report	Reactor Coolant System Control Rod
ML24318B831	13 November 2024	Technical Specifications Task Force	TSTF Slides from 11/13/24 Implementation Workshop TSTF-585, Revise LCO 3.0.3 to Require Managing Risk	Service water High Pressure Coolant Injection Reactor Protection System Main Steam Isolation Valve Primary Containment Isolation System Auxiliary Feedwater Core Spray Decay Heat Removal Control Rod
ML24310A168	5 November 2024	Prairie Island	Core Operating Limits Report (COLR) for Cycle 34, Revision 0	Reactor Coolant System Control Rod
CP-202400424, (Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0)	4 November 2024	Comanche Peak	(Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0)	Reactor Coolant System Control Rod
L-2024-175, Cycle 34 Core Operating Report	24 October 2024	Turkey Point	Cycle 34 Core Operating Report	Reactor Coolant System Control Rod
L-2024-160, Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)	21 October 2024	Point Beach	Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)	Reactor Coolant System Feedwater
BW240061, Core Operating Limits Report, Cycle 25, Revision 17	17 October 2024	Braidwood	Core Operating Limits Report, Cycle 25, Revision 17	Reactor Coolant System Control Rod
... further results

Navigation menu

Search