| Start date | Site | Title | System |
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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 |