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	Issue date	Title	Topic
0CAN030504, Justification for ANO Exemption Request for Loading of Damaged Fuel	21 March 2005	Justification for ANO Exemption Request for Loading of Damaged Fuel	Exemption Request Earthquake Fuel cladding
0CAN051704, Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One.	13 March 2017	Engineering 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
0CAN061701, Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis	7 June 2017	Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis	Fire Barrier Fire Protection Program
0CAN081703, Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report	16 August 2017	Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report	Hot Short Safe Shutdown Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Earthquake
0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis	6 October 2021	Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis
0CAN120202, CFR 50.59 Summary Report	4 December 2002	CFR 50.59 Summary Report	Earthquake
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 4.3	2 April 2003	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 4.3	High Radiation Area Operating Basis Earthquake Nondestructive Examination Finite Element Analysis Design basis earthquake Earthquake Control of Heavy Loads Fuel cladding
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 1	6 May 2014	Time-Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years Arkansas Nuclear One Unit 1	Aging Management
1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version	20 June 2023	Enclosure 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 Operation	29 June 2023	Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
1CAN091301, Updated Seismic Walkdown Report	30 September 2013	Updated Seismic Walkdown Report	Safe Shutdown Unanalyzed Condition Safe Shutdown Earthquake Probabilistic Risk Assessment Finite Element Analysis Fukushima Dai-Ichi Earthquake Maintenance Rule Program Scaffolding
1CAN110203, Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01 for ANO-1 Incore Instrument Nozzles	21 November 2002	Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01 for ANO-1 Incore Instrument Nozzles	Boric 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 331	16 November 2012	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 331	Safe 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 560	16 November 2012	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 560	Safe Shutdown Scaffolding
2CAN010304, Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions	29 January 2003	Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions	Boric 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
2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods	24 February 2022	Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods	VT-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-2	2 April 2008	Summary of Design and Analyses of Weld Overlays for Hot Leg Nozzle Dissimilar Metal Welds for Alloy 600 Mitigation at ANO-2	Weld Overlay Nondestructive Examination Dissimilar Metal Weld
2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval	29 June 2021	Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval	VT-2
2CAN111201, Arkansas, Unit 2, Attachment 1 - Engineering Report CALC-ANO2-CS-12-00001, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page 364 of 533 Through End	16 November 2012	Arkansas, Unit 2, Attachment 1 - Engineering Report CALC-ANO2-CS-12-00001, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page 364 of 533 Through End	Scaffolding
3F0103-03, Response to Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Degradation & Reactor Coolant Pressure Boundary Integrity	28 January 2003	Response to Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Degradation & Reactor Coolant Pressure Boundary Integrity	Boric Acid Non-Destructive Examination VT-2 Aging Management Stress corrosion cracking Pressure Boundary Leakage Unidentified leakage Operational leakage
3F0119-01, Reference 5 - EPA-600-R-07-020, Performance of Statistical Tests for Site Versus Background Soil Comparisons When Distributional Assumptions Are Not Met.	31 March 2007	Reference 5 - EPA-600-R-07-020, Performance of Statistical Tests for Site Versus Background Soil Comparisons When Distributional Assumptions Are Not Met.
3F0320-01, NRC Commitment Change Report - March 2020	17 March 2020	NRC Commitment Change Report - March 2020	Safe Shutdown Nondestructive Examination B.5.b Control of Heavy Loads Liquid penetrant
3F0518-03, Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2018	24 May 2018	Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2018	Internal Flooding Temporary Modification Control of Heavy Loads
3F0520-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020	18 May 2020	Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020	Fitness for Duty High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Process Control Program Exemption Request Commercial Grade Fatigue Rule Fire Protection Program Overexposure
3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022	17 May 2022	Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022	High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Process Control Program Commercial Grade Fire Protection Program Grace period Overexposure
3F0623-02, Maintenance Support Building	9 June 2023	Maintenance Support Building
3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.	30 June 2012	Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.
3F0912-01, ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C	30 September 2012	ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C	Boric Acid Loop seal Ultimate heat sink Fuel cladding Power Uprate Manual Operator Action
3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip	25 October 2011	ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip	Stroke time Power Uprate
3F1107-06, CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report	21 November 2007	CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report
3F1112-01, Alion Technical Report ALION-PLN-ENER-8706-02, Rev. 0, Crystal River 3: Bypass Fiber Quantity Test Plan	7 November 2012	Alion Technical Report ALION-PLN-ENER-8706-02, Rev. 0, Crystal River 3: Bypass Fiber Quantity Test Plan
3F1112-02, 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250	31 October 2012	17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250
CNRO-2002-00052, Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations	28 October 2002	Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations	Nondestructive Examination Incorporated by reference Finite Element Analysis Liquid penetrant Dissimilar Metal Weld
CNRO-2003-00020, Arkansas, Unit 2 and Waterford, Unit 3, Relaxation Requests to NRC Order EA-03-009	11 June 2003	Arkansas, Unit 2 and Waterford, Unit 3, Relaxation Requests to NRC Order EA-03-009	Finite Element Analysis Liquid penetrant
CNRO-2003-00030, Arkansas, Unit 2 and Waterford, Unit 3, Letter CNRO-2003-00027 to NRC, Relaxation Requests to NRC Order EA-03-009, Dated July 1, 2003	24 July 2003	Arkansas, Unit 2 and Waterford, Unit 3, Letter CNRO-2003-00027 to NRC, Relaxation Requests to NRC Order EA-03-009, Dated July 1, 2003	Nondestructive Examination
CNRO-2003-00033, Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachment 47 Thr	26 August 2003	Rev. 1 to Engineering Report M-EP-2003-002, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element..., Appendix C, Attachment 47 Through En
CNRO-2004-00008, Rev. 0 to M-EP-2004-001, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth in the Un-Inspected Regions of the Control Rod Drive Mechanism Nozzles at ANO, Unit 1, App. C Th	2 February 2004	Rev. 0 to M-EP-2004-001, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth in the Un-Inspected Regions of the Control Rod Drive Mechanism Nozzles at ANO, Unit 1, App. C Through P
ML021230304	11 April 2002	Technical Requirements Manual, Revision No. 10, Change No. AP-10, for Arkansas Nuclear One Unit 2	Boric Acid
ML021630316	11 June 2002	ILRT Type a Test Interval Optimization Methodology Problem Statement, Nei/Epri, Draft	Probabilistic Risk Assessment Coatings Large early release frequency
ML021990405	18 July 2002	Supplemental Fire Modeling for Fire Zone 98-J, Emergency Diesel Generator Corridor & Fire Zone 99-M, North Electrical Switchgear Room, Arkansas Nuclear One, Unit 1	Safe Shutdown Fire Barrier Significance Determination Process

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