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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
0CAN030504, Justification for ANO Exemption Request for Loading of Damaged Fuel21 March 2005Justification for ANO Exemption Request for Loading of Damaged FuelExemption Request
Earthquake
Fuel cladding
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
0CAN051704, Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One.13 March 2017Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One.Safe Shutdown
FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
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
0CAN061701, Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis7 June 2017Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards AnalysisFire Barrier
Fire Protection Program
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
0CAN081703, Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report16 August 2017Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation ReportHot Short
Safe Shutdown
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Earthquake
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
0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis6 October 2021Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis
0CAN120202, CFR 50.59 Summary Report4 December 2002CFR 50.59 Summary ReportEarthquake
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
1CAN040302, License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.32 April 2003License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.3High Radiation Area
Operating Basis Earthquake
Nondestructive Examination
Finite Element Analysis
Design basis earthquake
Earthquake
Control of Heavy Loads
Fuel cladding
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
1CAN051401, Time-Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years Arkansas Nuclear One Unit 16 May 2014Time-Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years Arkansas Nuclear One Unit 1Aging Management
1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version20 June 2023Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version
1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation29 June 2023Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
1CAN091001, 10 CFR 50.46 Report - Significant Change in Peak Cladding Temperature8 September 201010 CFR 50.46 Report - Significant Change in Peak Cladding Temperature
1CAN091301, Updated Seismic Walkdown Report30 September 2013Updated Seismic Walkdown ReportSafe Shutdown
Unanalyzed Condition
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Finite Element Analysis
Fukushima Dai-Ichi
Earthquake
Maintenance Rule Program
Scaffolding
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
1CAN110203, Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01 for ANO-1 Incore Instrument Nozzles21 November 2002Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01 for ANO-1 Incore Instrument NozzlesBoric Acid
VT-2
1CAN111201, Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 33116 November 2012Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 331Safe Shutdown
Unanalyzed Condition
Safe Shutdown Earthquake
Finite Element Analysis
Fukushima Dai-Ichi
Earthquake
Maintenance Rule Program
1CAN111201, Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 332 Through 56016 November 2012Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 332 Through 560Safe Shutdown
Scaffolding
2CAN010304, Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions29 January 2003Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading RestrictionsBoric Acid
High Radiation Area
Safe Shutdown Earthquake
Operating Basis Earthquake
Nondestructive Examination
Finite Element Analysis
Design basis earthquake
Earthquake
Control of Heavy Loads
Fuel cladding
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
2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods24 February 2022Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third PeriodsVT-2
Large early release frequency
Liquid penetrant
2CAN040801, Summary of Design and Analyses of Weld Overlays for Hot Leg Nozzle Dissimilar Metal Welds for Alloy 600 Mitigation at ANO-22 April 2008Summary of Design and Analyses of Weld Overlays for Hot Leg Nozzle Dissimilar Metal Welds for Alloy 600 Mitigation at ANO-2Weld Overlay
Nondestructive Examination
Dissimilar Metal Weld
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
2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval29 June 2021Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth IntervalVT-2