CPSES-200600635, License Amendment Request (LAR) 06-004 Revision to Technical Specification 5.0, Administrative Controls. | 31 March 2006 | Comanche Peak | License Amendment Request (LAR) 06-004 Revision to Technical Specification 5.0, Administrative Controls. | 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 Rod Containment Spray |
CPSES-200601056, Response to Request for Additional Information Related to License Amendment Request (LAR) 2004-010 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | 7 June 2006 | Comanche Peak | Response to Request for Additional Information Related to License Amendment Request (LAR) 2004-010 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | Steam Generator Reactor Coolant System Feedwater Service water Main Steam Isolation Valve Auxiliary Feedwater Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System Main Steam Line Main Condenser Containment Spray |
DCL-02-079, Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report | 31 July 2002 | Diablo Canyon | Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report | Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Reactor Pressure Vessel Residual Heat Removal Main Steam Safety Valve Emergency Core Cooling System |
DCL-03-049, 2002 Annual Radioactive Effluent Release Report | 30 April 2003 | Diablo Canyon | 2002 Annual Radioactive Effluent Release Report | Steam Generator Main Condenser |
DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation | 11 June 2003 | Diablo Canyon | License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation | Reactor Coolant System Reactor Protection System Control Rod |
DCL-03-101, Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report | 15 August 2003 | Diablo Canyon | Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report | Reactor Coolant System |
DCL-03-118, License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | 26 September 2003 | Diablo Canyon | License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | Steam Generator Reactor Coolant System Auxiliary Feedwater Residual Heat Removal Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Steam |
DCL-03-173, License Amendment Request 03-19 for Revision to Technical Specifications 3.3.3, Post-Accident Monitoring (PAM) Instrumentation and 3.6.8, Hydrogen Recombiners | 30 December 2003 | Diablo Canyon | License Amendment Request 03-19 for Revision to Technical Specifications 3.3.3, Post-Accident Monitoring (PAM) Instrumentation and 3.6.8, Hydrogen Recombiners | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Primary containment Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Main Steam Line Containment Spray |
DCL-04-046, CFR 50.59 Report of Changes. Tests, and Experiments for the Period January 1, 2002, Through December 31, 2003 | 23 April 2004 | Diablo Canyon | CFR 50.59 Report of Changes. Tests, and Experiments for the Period January 1, 2002, Through December 31, 2003 | Steam Generator Reactor Coolant System Reactor Protection System Emergency Response Data System Safety Parameter Display System Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Rod |
DCL-04-141, Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. 'Steam Generator (SG) Tube Surveillance Program.' & 5.6.10 | 28 December 2004 | Diablo Canyon | Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. 'Steam Generator (SG) Tube Surveillance Program.' & 5.6.10 | Steam Generator Reactor Coolant System Main Steam Isolation Valve Main Steam Line Main Steam |
DCL-06-048, 2005 Annual Radioactive Effluent Release Report. | 31 December 2005 | Diablo Canyon | 2005 Annual Radioactive Effluent Release Report. | Steam Generator |
DCL-07-047, Annual Radioactive Effluent Release Report | 27 April 2007 | Diablo Canyon | Annual Radioactive Effluent Release Report | Steam Generator Main Condenser |
DCL-08-034, Transmittal of 2007 Annual Radioactive Effluent Release Report | 30 April 2008 | Diablo Canyon | Transmittal of 2007 Annual Radioactive Effluent Release Report | Steam Generator Main Condenser |
DCL-09-025, 2008 Annual Radioactive Effluent Release Report | 24 April 2009 | Diablo Canyon | 2008 Annual Radioactive Effluent Release Report | Steam Generator HVAC Main Condenser |
DCL-10-026, Technical Specification 5.6.8 PAM Instrumentation Report | 23 March 2010 | Diablo Canyon | Technical Specification 5.6.8 PAM Instrumentation Report | Reactor Coolant System |
DCL-10-042, Annual Radioactive Effluent Release Report | 28 April 2010 | Diablo Canyon | Annual Radioactive Effluent Release Report | Steam Generator Reactor Protection System HVAC Emergency Core Cooling System Main Condenser |
DCL-11-049, 2010 Annual Radioactive Effluent Release Report, in Accordance with 10 CFR 50.36a(a)(2) and Section 5.6.3 | 28 April 2011 | Diablo Canyon | 2010 Annual Radioactive Effluent Release Report, in Accordance with 10 CFR 50.36a(a)(2) and Section 5.6.3 | Steam Generator Main Condenser |
DCL-11-104, Attachment 1: List of Regulatory Commitments | 26 October 2011 | Diablo Canyon | Attachment 1: List of Regulatory Commitments | Reactor Coolant System |
DCL-12-040, 2011 Annual Radioactive Effluent Release Report | 30 April 2012 | Diablo Canyon | 2011 Annual Radioactive Effluent Release Report | Steam Generator Main Condenser Control Rod |
DCL-13-042, Submittal of 2012 Annual Radioactive Effluent Release Report | 30 April 2013 | Diablo Canyon | Submittal of 2012 Annual Radioactive Effluent Release Report | Steam Generator Main Condenser Control Rod |
DCL-13-043, Supplement to License Amendment Request 11-07. Process Protection System Replacement. | 30 April 2013 | Diablo Canyon | Supplement to License Amendment Request 11-07. Process Protection System Replacement. | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Turbine Residual Heat Removal Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray |
DCL-13-092, Technical Specification Bases, Revision 8 | 16 September 2013 | Diablo Canyon | Technical Specification Bases, Revision 8 | 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 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 |
DCL-14-036, Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement | 30 April 2014 | Diablo Canyon | Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement | Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Main Turbine Containment Spray |
DCL-14-039, Annual Radioactive Effluent Release Report | 30 April 2014 | Diablo Canyon | Annual Radioactive Effluent Release Report | Steam Generator Main Condenser |
DCL-15-053, 2014 Annual Radioactive Effluent Release Report | 29 April 2015 | Diablo Canyon | 2014 Annual Radioactive Effluent Release Report | Steam Generator Main Steam Isolation Valve Main Condenser |
DCL-15-059, Technical Specification Bases, Revision 9 | 5 May 2015 | Diablo Canyon | Technical Specification Bases, Revision 9 | 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 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 |
DCL-16-054, Annual Radioactive Effluent Release Report for 2015 | 27 April 2016 | Diablo Canyon | Annual Radioactive Effluent Release Report for 2015 | Steam Generator Main Condenser |
DCL-16-126, Revision 10 to Technical Specification Bases | 30 December 2016 | Diablo Canyon | Revision 10 to Technical Specification Bases | 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 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 |
DCL-17-031, Transmittal of 2016 Annual Radioactive Effluent Release Report | 26 April 2017 | Diablo Canyon | Transmittal of 2016 Annual Radioactive Effluent Release Report | Steam Generator Main Condenser Control Rod |
DCL-18-028, Submittal of 2017 Annual Radioactive Effluent Release Report | 24 April 2018 | Diablo Canyon | Submittal of 2017 Annual Radioactive Effluent Release Report | Steam Generator Main Condenser |
DCL-18-070, Technical Specification Bases, Revision 11 | 11 September 2018 | Diablo Canyon | Technical Specification Bases, Revision 11 | 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 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 |
DCL-18-112, Technical Specification 5.6.8 PAM Instrumentation Report | 20 December 2018 | Diablo Canyon | Technical Specification 5.6.8 PAM Instrumentation Report | |
DCL-19-026, Annual Radioactive Effluent Release Report | 23 April 2019 | Diablo Canyon | Annual Radioactive Effluent Release Report | Steam Generator Main Condenser Control Rod |
DCL-20-068, Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System | 16 August 2020 | Diablo Canyon | Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System | Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Remote shutdown |
DCL-20-076, Technical Specification Bases | 10 September 2020 | Diablo Canyon | Technical Specification Bases | 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 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 |
DCL-20-092, License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition | 3 December 2020 | Diablo Canyon | License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Safety Parameter Display System Residual Heat Removal Fuel Pool Cooling and Cleanup 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 |
DCL-22-017, Submittal of 2021 Annual Radioactive Effluent Release Report | 21 April 2022 | Diablo Canyon | Submittal of 2021 Annual Radioactive Effluent Release Report | Steam Generator Main Condenser |
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 |
ENS 40842 | 25 June 2004 14:50:00 | Seabrook | Plant Exceeded Lco Action Statement Limits | |
ENS 48590 | 13 December 2012 21:30:00 | Nine Mile Point | Technical Specification Required Shutdown Due to Primary Containment System Declared Inoperable | Feedwater High Pressure Coolant Injection Primary containment Shutdown Cooling Reactor Pressure Vessel Emergency Core Cooling System |
ENS 50396 | 24 August 2014 05:00:00 | Point Beach | Technical Specification Required Shutdown Due to Post Accident Monitoring Instrumentation Out of Service | |
ENS 50492 | 24 September 2014 20:33:00 | Prairie Island | Unit 1 Train B Rvlis and Iccm Inoperable Due to Data Errors | |
ENS 52218 | 2 September 2016 13:08:00 | Wolf Creek | Technical Specification Required Shutdown | Reactor Coolant System |
ET 08-0009, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program for Interim Alternate Repair Criteria | 8 February 2008 | Wolf Creek | Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program for Interim Alternate Repair Criteria | Steam Generator Reactor Coolant System Control Rod |
ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr). | 10 July 2008 | Wolf Creek | Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr). | Steam Generator Reactor Coolant System Reactor Pressure Vessel |
ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. | 14 August 2008 | Wolf Creek | Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Auxiliary Feedwater Control Room Emergency Ventilation Remote shutdown Emergency Core Cooling System Containment Spray |
ET 09-0016, Revision to Technical Specifications 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criterion | 2 June 2009 | Wolf Creek | Revision to Technical Specifications 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criterion | Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Control Room Emergency Ventilation Control Rod |
ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) | 27 April 2020 | Wolf Creek | Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Main Turbine Shutdown Cooling Residual Heat Removal Control Room Emergency Ventilation Shield Building Remote shutdown Emergency Core Cooling System Decay Heat Removal Control Room Envelope Control Rod Containment Spray |
HL-4561, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt | 7 June 1994 | Hatch | Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Allow Testing Planned at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt | Feedwater Service water High Pressure Coolant Injection Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Shutdown Cooling HVAC Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Standby Gas Treatment System Circulating Water System Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Main Condenser Control Rod Main Steam Containment Spray Low Pressure Coolant Injection |
IA-86-827, Final Response to FOIA Request for Documents.App a Documents Consisting of La Crosse & Big Rock Point Semiannual Effluent Repts & App B Documents Consisting of Encl Turkey Point & St Lucie SALP Repts Available in Pdr.W/O Stated Encls | 16 December 1986 | Saint Lucie Turkey Point La Crosse Big Rock Point 05000000 | Final Response to FOIA Request for Documents.App a Documents Consisting of La Crosse & Big Rock Point Semiannual Effluent Repts & App B Documents Consisting of Encl Turkey Point & St Lucie SALP Repts Available in Pdr.W/O Stated Encls | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Transformer Main Turbine Shutdown Cooling Safety Parameter Display System Residual Heat Removal Decay Heat Removal Main Steam Line Control Rod Auxiliary Feed Water Main Steam Containment Spray |