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	Start date	Site	Title	System
AEP-NRC-2012-54, Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.	12 September 2012	Cook	Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.	Steam Generator Reactor Coolant System Reactor Pressure Vessel Emergency Core Cooling System Main Steam Line
AEP-NRC-2015-05, Correction of Technical Specification Typographical Error	2 February 2015	Cook	Correction of Technical Specification Typographical Error	Steam Generator Emergency Core Cooling System
AEP-NRC-2020-47, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Containment Area Radiation (High Range)	25 June 2020	Cook	Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Containment Area Radiation (High Range)
AEP-NRC-2020-59, for Donald C. Cook Nuclear Plant (CNP) Unit 2 - Report Per Technical Specification 5.6.6, Lnoperability of Unit 2, Post Accident Monitoring, Containment Water Level	27 August 2020	Cook	for Donald C. Cook Nuclear Plant (CNP) Unit 2 - Report Per Technical Specification 5.6.6, Lnoperability of Unit 2, Post Accident Monitoring, Containment Water Level
AEP-NRC-2020-76, Report Per Technical Specification 5.6.6, Inoperability of Unit 1, Post Accident Monitoring, Containment Water Level	24 November 2020	Cook	Report Per Technical Specification 5.6.6, Inoperability of Unit 1, Post Accident Monitoring, Containment Water Level
AEP-NRC-2021-07, Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level	28 January 2021	Cook	Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level
AEP-NRC-2021-24, Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation	23 March 2021	Cook	Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation	Reactor Coolant System Emergency Core Cooling System Containment Spray
AEP-NRC-2021-47, Unit 2 - Application to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections	8 November 2021	Cook	Unit 2 - Application to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections	Steam Generator Emergency Core Cooling System
AEP-NRC-2021-68, Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation	16 December 2021	Cook	Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation	Steam Generator Reactor Coolant System Auxiliary Feedwater Emergency Core Cooling System
AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring	15 December 2022	Cook	Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring	Intermediate Range Monitor
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
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
B15236, Application for Amend to License NPF-49,relocating TS Requirements for Containment Purge Exhaust & Supply Valves from Radiation Monitoring Instrumentation TS Table to ESF Actuation Sys TS Table	27 June 1995	Millstone	Application for Amend to License NPF-49,relocating TS Requirements for Containment Purge Exhaust & Supply Valves from Radiation Monitoring Instrumentation TS Table to ESF Actuation Sys TS Table
B16297, Annual Rept,Jan-Dec 1996	31 December 1996	Millstone	Annual Rept,Jan-Dec 1996	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Auxiliary Feedwater HVAC Residual Heat Removal Decay Heat Removal Control Rod Main Steam
B17350, Responds to NRC Re Violations Noted in Insp Repts 50-245/98-207,50-336/98-207 & 50-423/98-207,respectively. Corrective Actions:Issues Were Discussed W/Personnel Directly Involved in Preparation of Licensing Submittal	20 July 1998	Millstone	Responds to NRC Re Violations Noted in Insp Repts 50-245/98-207,50-336/98-207 & 50-423/98-207,respectively. Corrective Actions:Issues Were Discussed W/Personnel Directly Involved in Preparation of Licensing Submittal	Reactor Coolant System Service water Emergency Diesel Generator Emergency Core Cooling System
BSEP-92-0024, Forwards Request for Temporary Waiver of Compliance from TS 3.3.3, ECCS Actuation Instrumentation When in Operational Condition 4, to Permit One Channel from Each of Two Trip Sys to Be Inoperable Simultaneously for Up to 12 H	7 October 1992	Brunswick	Forwards Request for Temporary Waiver of Compliance from TS 3.3.3, ECCS Actuation Instrumentation When in Operational Condition 4, to Permit One Channel from Each of Two Trip Sys to Be Inoperable Simultaneously for Up to 12 H
BSEP-94-0413, Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times	28 October 1994	Brunswick	Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times	Secondary containment Reactor Protection System Primary containment Shutdown Cooling Core Spray Reactor Water Cleanup Control Room Emergency Ventilation Automatic Depressurization System Core Standby Cooling System Emergency Core Cooling System Main Steam Line Control Rod Main Steam Low Pressure Coolant Injection
BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7	16 July 1999	Braidwood	Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7	Reactor Coolant System Safety Parameter Display System
CNL-15-060, Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F	15 December 2015	Watts Bar	Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F	Steam Generator Reactor Coolant System Feedwater Reactor Pressure Vessel Main Steam Line Main Condenser
CNL-16-047, Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria	4 May 2016	Watts Bar	Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria	Steam Generator Reactor Coolant System Feedwater Main Steam
CNL-17-020, Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 11	16 February 2017	Watts Bar	Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 11	Steam Generator Reactor Coolant System Feedwater Residual Heat Removal Remote shutdown
CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)	30 September 2019	Watts Bar	Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Reactor Pressure Vessel Main Steam Safety Valve Main Steam Line Main Condenser Main Steam
CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)	22 June 2020	Watts Bar	Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)	Steam Generator Reactor Coolant System Auxiliary Feedwater Decay Heat Removal Containment Spray
CNL-20-053, Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-39	17 July 2020	Watts Bar	Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-390-	Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Auxiliary Feedwater Reactor Pressure Vessel Main Steam Line Main Condenser
CNL-21-013, Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06)	11 March 2021	Watts Bar	Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06)	Steam Generator Reactor Coolant System Reactor Pressure Vessel Main Steam Line Main Condenser
CNL-21-021, Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, .	30 March 2021	Watts Bar	Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, .	Steam Generator Reactor Coolant System Emergency Diesel Generator
CNL-22-001, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)	4 April 2022	Watts Bar Sequoyah	Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)	Steam Generator Emergency Diesel Generator
CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)	13 July 2022	Watts Bar Sequoyah	Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)	Steam Generator Emergency Diesel Generator
CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.	17 February 2014	Catawba	Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.	Steam Generator Reactor Coolant System Auxiliary Feedwater Remote shutdown Decay Heat Removal Containment Spray
CNS-14-035, Submittal of Post Accident Monitoring (PAM) Report	17 March 2014	Catawba	Submittal of Post Accident Monitoring (PAM) Report	Reactor Coolant System Remote shutdown
CNS-14-055, Technical Specification Bases Changes	5 May 2014	Catawba	Technical Specification Bases Changes	Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Auxiliary Feedwater Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Main Steam Line Containment Spray
CP-200800411, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses	13 March 2008	Comanche Peak	Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses	Steam Generator Reactor Coolant System Feedwater Residual Heat Removal Control Room Emergency Filtration System Remote shutdown Emergency Core Cooling System Main Steam Line Control Rod
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2	1 August 2008	Comanche Peak	Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Control Room Emergency Filtration 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 Containment Spray
CP-200900262, License Amendment Request (LAR) 09-001, Administrative Revision to Operating Licenses and Technical Specifications	11 February 2009	Comanche Peak	License Amendment Request (LAR) 09-001, Administrative Revision to Operating Licenses and Technical Specifications	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Shutdown Cooling HVAC Residual Heat Removal Control Room Emergency Filtration System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Control Rod Containment Spray
CP-200900748, Comanche Peak - License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria	8 June 2009	Comanche Peak	Comanche Peak - License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Control Rod
CP-200901042, Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria	20 August 2009	Comanche Peak	Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria	Steam Generator Reactor Coolant System Feedwater Main Steam Line Control Rod
CP-200901307, Revision to License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria	28 September 2009	Comanche Peak	Revision to License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria	Steam Generator
CP-200901308, Revision to License Amendment Request 09-007 Model D5 Steam Generator Alternate Repair Criteria	14 September 2009	Comanche Peak	Revision to License Amendment Request 09-007 Model D5 Steam Generator Alternate Repair Criteria	Steam Generator
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2	15 February 2010	Comanche Peak	Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Control Room Emergency Filtration System 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
CP-201101038, License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled	1 August 2011	Comanche Peak	License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled	Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Shutdown Cooling HVAC Residual Heat Removal Shield Building Control Room Emergency Filtration System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Room Envelope Control Rod Main Steam Containment Spray
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases	1 August 2011	Comanche Peak	Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Turbine HVAC Residual Heat Removal Control Room Emergency Filtration System Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray
CP-201200012, (Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent ....	28 March 2012	Comanche Peak	(Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent ....	Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Control Rod
CP-201201129, License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation	2 October 2012	Comanche Peak	License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Auxiliary Feedwater Main Turbine Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Steam Containment Spray
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67	4 February 2013	Comanche Peak	Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Main Turbine Shutdown Cooling HVAC Residual Heat Removal Control Room Emergency Filtration System 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
CP-201300738, License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item..	10 July 2013	Comanche Peak	License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item..	Steam Generator Reactor Coolant System Control Room Emergency Filtration System Main Steam Line Main Condenser
CP-201301065, Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process	29 August 2013	Comanche Peak	Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process	Steam Generator Reactor Coolant System Control Room Emergency Filtration System Main Steam Line Main Condenser
CP-201400231, Supplement to License Amendment Request 13-002 Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line.	19 February 2014	Comanche Peak	Supplement to License Amendment Request 13-002 Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line.	Steam Generator Reactor Coolant System
CP-201600048, Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels	27 January 2016	Comanche Peak	Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels	Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Primary containment Main Turbine Shutdown Cooling Safety Parameter Display System Reactor Pressure Vessel Residual Heat Removal Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Rod Main Steam Containment Spray
CP-201701010, Special Report 1-SR-17-001-00 for Comanche Peak Nuclear Power Plant, Unit 1 Regarding Inoperable Post Accident Monitoring Instrument Report	19 December 2017	Comanche Peak	Special Report 1-SR-17-001-00 for Comanche Peak Nuclear Power Plant, Unit 1 Regarding Inoperable Post Accident Monitoring Instrument Report
CP-201800652, Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report	12 September 2018	Comanche Peak	Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report	Steam Generator Auxiliary Feedwater Remote shutdown

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