0CAN010503, Special Report | 19 January 2005 | Special Report | |
0CAN020305, Fitness-for-Duty Performance Data for Period July - December 2002 | 28 February 2003 | Fitness-for-Duty Performance Data for Period July - December 2002 | |
0CAN020403, Transmittal of Fitness-for-Duty Performance Data for Period Ending December 31, 2003 | 18 February 2004 | Transmittal of Fitness-for-Duty Performance Data for Period Ending December 31, 2003 | |
0CAN020505, ANO, Units 1 and 2 - Transmittal of Fitness-for-Duty Performance Data for Period July - December 2004 | 25 February 2005 | ANO, Units 1 and 2 - Transmittal of Fitness-for-Duty Performance Data for Period July - December 2004 | |
0CAN020602, Fitness-for-Duty Performance Data for the Period July - December 2005 | 27 February 2006 | Fitness-for-Duty Performance Data for the Period July - December 2005 | Fitness for Duty |
0CAN021204, Units 1 and 2, Third Five-Year Surveillance of the First Ventilated Storage Cask | 29 February 2012 | Units 1 and 2, Third Five-Year Surveillance of the First Ventilated Storage Cask | |
0CAN021403, Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary Report | 11 February 2014 | Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary Report | Safe Shutdown Boric Acid Shutdown Margin Time to boil Hydrostatic Operator Manual Action Temporary Modification Qualified Offsite Circuit Feedwater Heater Large early release frequency Eddy Current Testing Fuel cladding Offsite Circuit GOTHIC Overspeed trip Thermography Water hammer |
0CAN021501, Spent Fuel Storage Radioactive Effluent Release Report for 2014 | 3 February 2015 | Spent Fuel Storage Radioactive Effluent Release Report for 2014 | |
0CAN030701, Drug Testing Laboratory Performance Report | 6 March 2007 | Drug Testing Laboratory Performance Report | Fitness for Duty |
0CAN031001, Units 1 & 2, Unsatisfactory Laboratory Testing Report | 18 March 2010 | Units 1 & 2, Unsatisfactory Laboratory Testing Report | |
0CAN031404, ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima | 28 March 2014 | ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima Da | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake Seismic Walkdown Report |
0CAN040505, Units 1 and 2, Drug Testing Laboratory Performance Report | 12 April 2005 | Units 1 and 2, Drug Testing Laboratory Performance Report | Fitness for Duty |
0CAN050903, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes | 15 May 2009 | Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes | |
0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes | 10 May 2021 | Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes | |
0CAN080401, Fitness-for-Duty Performance Data for the Period January - June 2004 | 13 August 2004 | Fitness-for-Duty Performance Data for the Period January - June 2004 | |
0CAN080601, Arkansas - Fitness-for-Duty Program Performance Data for the Period January - June 2006 | 22 August 2006 | Arkansas - Fitness-for-Duty Program Performance Data for the Period January - June 2006 | Fitness for Duty |
0CAN100901, Units 1 & 2, Unsatisfactory Laboratory Testing Report | 13 October 2009 | Units 1 & 2, Unsatisfactory Laboratory Testing Report | Fitness for Duty |
0CAN101003, 10 CFR 50.59 Summary Report and Commitment Change Summary Report | 7 October 2010 | 10 CFR 50.59 Summary Report and Commitment Change Summary Report | |
0CAN121602, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 3 | 30 December 2016 | Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 3 | Ultimate heat sink FLEX Fukushima Dai-Ichi Earthquake |
0CAN121901, Summary of Lost Specimens Investigation Report | 3 December 2019 | Summary of Lost Specimens Investigation Report | Fitness for Duty |
1CAN010301, Arkansas, Unit 1, Once Through Steam Generator Inservice Inspection Report | 17 January 2003 | Arkansas, Unit 1, Once Through Steam Generator Inservice Inspection Report | Stress corrosion cracking Eddy Current Testing Eddy Current Test |
1CAN031305, Cycle 24 COLR, Revision 6 | 13 March 2013 | Cycle 24 COLR, Revision 6 | Shutdown Margin |
1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values | 19 March 2020 | Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values | Overtravel |
1CAN041105, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016 | 20 April 2011 | Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016 | Weld Overlay Nondestructive Examination Stress corrosion cracking Liquid penetrant Through-Wall Leak |
1CAN091001, 10 CFR 50.46 Report - Significant Change in Peak Cladding Temperature | 8 September 2010 | 10 CFR 50.46 Report - Significant Change in Peak Cladding Temperature | |
1CAN091601, Submittal of Initial Examination Completion of Post-Examination Analysis | 1 September 2016 | Submittal of Initial Examination Completion of Post-Examination Analysis | Shutdown Margin Core Exit Thermocouple |
1CAN100203, Supplemental Response to NRC Bulletin 2002-02 for Arkansas Nuclear One, Unit 1 | 31 October 2002 | Supplemental Response to NRC Bulletin 2002-02 for Arkansas Nuclear One, Unit 1 | Boric Acid Reactor Vessel Water Level Nondestructive Examination VT-2 Stress corrosion cracking Pressure boundary leak |
2CAN011003, Submittal of Us Dept. of Commerce, Bureau of Industry and Security. Additional Protocol Report | 28 January 2010 | Submittal of Us Dept. of Commerce, Bureau of Industry and Security. Additional Protocol Report | |
2CAN011202, Additional Protocol Report | 31 January 2012 | Additional Protocol Report | |
2CAN011703, Submittal of Additional Protocol Report | 26 January 2017 | Submittal of Additional Protocol Report | |
2CAN040806, 60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19 | 22 April 2008 | 60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19 | Boric Acid Nondestructive Examination Stress corrosion cracking Eddy Current Testing |
2CAN060504, Unit 2, Submittal of Report to Provide Information Re Replacement Valve Disc Manufactured by Crane-Aloyco | 16 June 2005 | Unit 2, Submittal of Report to Provide Information Re Replacement Valve Disc Manufactured by Crane-Aloyco | |
2CAN070804, Cycle 20 Startup Report | 3 July 2008 | Cycle 20 Startup Report | Power change Core Exit Thermocouple |
2CAN091103, CFR 50.59 Summary Report | 16 September 2011 | CFR 50.59 Summary Report | Shutdown Margin Stroke time Temporary Modification Stress corrosion cracking Fuel cladding |
2CAN091302, Updated Seismic Walkdown Report | 30 September 2013 | Updated Seismic Walkdown Report | Safe Shutdown Unanalyzed Condition Boric Acid Safe Shutdown Earthquake Finite Element Analysis Fukushima Dai-Ichi Earthquake Maintenance Rule Program Scaffolding Power Uprate Seismic Walkdown Report |
2CAN100802, CFR 50.59 Summary Report for Period Ending October 6, 2008 | 13 October 2008 | CFR 50.59 Summary Report for Period Ending October 6, 2008 | Safe Shutdown Boric Acid Coatings High Energy Line Break Missed surveillance Operability Determination Fuel cladding Manual Operator Action |
2CAN110502, CFR 50.59 Summary Report | 21 November 2005 | CFR 50.59 Summary Report | Hot Short Safe Shutdown Unanalyzed Condition Shutdown Margin Packing leak Ultimate heat sink Offsite Dose Calculation Manual Slow transfer Anticipated operational occurrence Tornado Missile Coatings Incorporated by reference High Energy Line Break Tornado Generated Missile Tornado Missile Protection Fuel cladding Fire Protection Program Fire Watch Flow Induced Vibration |
3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR | 5 January 2012 | Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR | Coatings Flow Accelerated Corrosion License Renewal Power Uprate |
3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re | 31 January 2013 | Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Res | Shutdown Margin Anticipated operational occurrence Operator Manual Action Feedwater Heater Fuel cladding Power Uprate Loss of condenser vacuum |
3F0508-14, NRC Commitment Change Report - May 2008 | 28 May 2008 | NRC Commitment Change Report - May 2008 | |
3F0511-02, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models | 6 May 2011 | Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models | Power Uprate |
3F0512-01, NRC Commitment Change Report - May 2012 | 14 May 2012 | NRC Commitment Change Report - May 2012 | Stress corrosion cracking |
3F0602-05, Response to Request for Additional Information 263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging | 5 June 2002 | Response to Request for Additional Information #263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging | Shutdown Margin FLEX Flow Induced Vibration Unidentified leakage Power Uprate Exclusive Use Affidavit |
3F0616-02, Nrg Commitment Change Report - June 2016 | 14 June 2016 | Nrg Commitment Change Report - June 2016 | Safe Shutdown Boric Acid Offsite Dose Calculation Manual Time to boil B.5.b Mitigating Strategies Pressure Boundary Leakage Backfit Operability Assessment |
3F0702-11, Reporting Required by Environmental Protection Plan | 16 July 2002 | Reporting Required by Environmental Protection Plan | |
3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3 | 24 September 2002 | Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3 | Shutdown Margin |
3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis | 8 September 2010 | CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis | |
3F1102-08, Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service | 19 November 2002 | Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service | |
3F1205-03, Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4 | 3 December 2005 | Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4 | Fuel cladding |
3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report | 12 December 2005 | 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report | |