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 Issue dateTitleTopic
0CAN010503, Special Report19 January 2005Special Report
0CAN020305, Fitness-for-Duty Performance Data for Period July - December 200228 February 2003Fitness-for-Duty Performance Data for Period July - December 2002
0CAN020403, Transmittal of Fitness-for-Duty Performance Data for Period Ending December 31, 200318 February 2004Transmittal 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 200425 February 2005ANO, 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 200527 February 2006Fitness-for-Duty Performance Data for the Period July - December 2005Fitness for Duty
0CAN021204, Units 1 and 2, Third Five-Year Surveillance of the First Ventilated Storage Cask29 February 2012Units 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 Report11 February 2014Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary ReportSafe Shutdown
Boric Acid
Shutdown Margin
Time to boil
Hydrostatic
Operator Manual Action
Temporary Modification
Qualified Offsite Circuit
Large early release frequency
Fuel cladding
Offsite Circuit
GOTHIC
Overspeed trip
0CAN021501, Spent Fuel Storage Radioactive Effluent Release Report for 20143 February 2015Spent Fuel Storage Radioactive Effluent Release Report for 2014
0CAN030701, Drug Testing Laboratory Performance Report6 March 2007Drug Testing Laboratory Performance ReportFitness for Duty
0CAN031001, Units 1 & 2, Unsatisfactory Laboratory Testing Report18 March 2010Units 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 Fukushima28 March 2014ANO, 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 DaSafe Shutdown
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
Seismic Walkdown Report
0CAN040505, Units 1 and 2, Drug Testing Laboratory Performance Report12 April 2005Units 1 and 2, Drug Testing Laboratory Performance ReportFitness for Duty
0CAN050903, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes15 May 2009Annual 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 Changes10 May 2021Annual 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 200413 August 2004Fitness-for-Duty Performance Data for the Period January - June 2004
0CAN080601, Arkansas - Fitness-for-Duty Program Performance Data for the Period January - June 200622 August 2006Arkansas - Fitness-for-Duty Program Performance Data for the Period January - June 2006Fitness for Duty
0CAN100901, Units 1 & 2, Unsatisfactory Laboratory Testing Report13 October 2009Units 1 & 2, Unsatisfactory Laboratory Testing ReportFitness for Duty
0CAN101003, 10 CFR 50.59 Summary Report and Commitment Change Summary Report7 October 201010 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 330 December 2016Mitigating 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 3Ultimate heat sink
FLEX
Fukushima Dai-Ichi
Earthquake
0CAN121901, Summary of Lost Specimens Investigation Report3 December 2019Summary of Lost Specimens Investigation ReportFitness for Duty
1CAN010301, Arkansas, Unit 1, Once Through Steam Generator Inservice Inspection Report17 January 2003Arkansas, Unit 1, Once Through Steam Generator Inservice Inspection Report
1CAN031305, Cycle 24 COLR, Revision 613 March 2013Cycle 24 COLR, Revision 6Shutdown Margin
1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values19 March 2020Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable ValuesOvertravel
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-01620 April 2011Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016Non-Destructive Examination
Weld Overlay
Nondestructive Examination
Liquid penetrant
Through-Wall Leak
1CAN091001, 10 CFR 50.46 Report - Significant Change in Peak Cladding Temperature8 September 201010 CFR 50.46 Report - Significant Change in Peak Cladding Temperature
1CAN091601, Submittal of Initial Examination Completion of Post-Examination Analysis1 September 2016Submittal of Initial Examination Completion of Post-Examination AnalysisShutdown Margin
1CAN100203, Supplemental Response to NRC Bulletin 2002-02 for Arkansas Nuclear One, Unit 131 October 2002Supplemental Response to NRC Bulletin 2002-02 for Arkansas Nuclear One, Unit 1Boric Acid
Reactor Vessel Water Level
Non-Destructive Examination
VT-2
Pressure boundary leak
2CAN011003, Submittal of Us Dept. of Commerce, Bureau of Industry and Security. Additional Protocol Report28 January 2010Submittal of Us Dept. of Commerce, Bureau of Industry and Security. Additional Protocol Report
2CAN011202, Additional Protocol Report31 January 2012Additional Protocol Report
2CAN011703, Submittal of Additional Protocol Report26 January 2017Submittal of Additional Protocol Report
2CAN040806, 60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R1922 April 200860-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19Boric Acid
Nondestructive Examination
2CAN060504, Unit 2, Submittal of Report to Provide Information Re Replacement Valve Disc Manufactured by Crane-Aloyco16 June 2005Unit 2, Submittal of Report to Provide Information Re Replacement Valve Disc Manufactured by Crane-Aloyco
2CAN070804, Cycle 20 Startup Report3 July 2008Cycle 20 Startup ReportPower change
2CAN091103, CFR 50.59 Summary Report16 September 2011CFR 50.59 Summary ReportShutdown Margin
Stroke time
Temporary Modification
Fuel cladding
2CAN091302, Updated Seismic Walkdown Report30 September 2013Updated Seismic Walkdown ReportSafe Shutdown
Unanalyzed Condition
Boric Acid
Safe Shutdown Earthquake
Finite Element Analysis
Fukushima Dai-Ichi
Earthquake
Maintenance Rule Program
Scaffolding
2CAN100802, CFR 50.59 Summary Report for Period Ending October 6, 200813 October 2008CFR 50.59 Summary Report for Period Ending October 6, 2008Safe Shutdown
Boric Acid
Coatings
Missed surveillance
Fuel cladding
2CAN110502, CFR 50.59 Summary Report21 November 2005CFR 50.59 Summary ReportHot 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
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 LAR5 January 2012Response 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 LARCoatings
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 Re31 January 2013Attachment 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 ResShutdown Margin
Anticipated operational occurrence
Fuel cladding
Power Uprate
Manual Operator Action
3F0508-14, NRC Commitment Change Report - May 200828 May 2008NRC Commitment Change Report - May 2008
3F0511-02, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models6 May 2011Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA ModelsPower Uprate
3F0512-01, NRC Commitment Change Report - May 201214 May 2012NRC Commitment Change Report - May 2012Stress 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 Plugging5 June 2002Response to Request for Additional Information #263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube PluggingShutdown Margin
FLEX
Flow Induced Vibration
Unidentified leakage
Power Uprate
Exclusive Use
Affidavit
3F0616-02, Nrg Commitment Change Report - June 201614 June 2016Nrg Commitment Change Report - June 2016Safe Shutdown
Boric Acid
Offsite Dose Calculation Manual
Time to boil
B.5.b
Pressure Boundary Leakage
Backfit
Operability Assessment
3F0702-11, Reporting Required by Environmental Protection Plan16 July 2002Reporting Required by Environmental Protection Plan
3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 324 September 2002Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3Shutdown Margin
3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis8 September 2010CFR 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 Service19 November 2002Sea 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 43 December 2005Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4Fuel cladding
3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report12 December 200510 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report