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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23270B189 | 27 September 2023 | Evacuation Time Estimate Study | Pandemic Coronavirus COVID19 Siren |
| 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 | |
| 1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version | 20 June 2023 | Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version | |
| ML23180A108 | 20 June 2023 | ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report | Cyber Security Aging Management Turbine Missile |
| ML23088A217 | 31 December 2022 | Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022 | Boric Acid Nondestructive Examination Liquid penetrant |
| 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 |
| W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 | 30 November 2021 | Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 | |
| 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 | |
| W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt | 1 October 2021 | Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt | Safe Shutdown Tornado Missile Safe Shutdown Earthquake Internal Flooding Enforcement Discretion Probabilistic Risk Assessment Operating Basis Earthquake FLEX Tornado Generated Missile Fukushima Dai-Ichi Seismically rugged Tornado Missile Protection Large early release frequency TORMIS Earthquake Generic Issues Program |
| ML21272A303 | 30 September 2021 | Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report | Safe Shutdown Ultimate heat sink Anticipated operational occurrence Probabilistic Risk Assessment Tristructural Isotropic |
| ML21237A051 | 25 August 2021 | Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors | Non-Destructive Examination Safe Shutdown Earthquake Enforcement Discretion Probabilistic Risk Assessment Cyber Security Missed surveillance Significance Determination Process Surveillance Frequency Control Program Large early release frequency Time Critical Operator Action Low Safety Significance Issue Resolution Generic Issues Program Fire Protection Program |
| ML21081A192 | 30 June 2021 | Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment | Anticipated operational occurrence Nondestructive Examination Exemption Request Tristructural Isotropic |
| 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 |
| W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual | 5 April 2021 | License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual | Internal Flooding Probabilistic Risk Assessment Emergency Lighting Surveillance Frequency Control Program |
| ML21272A338 | 1 April 2021 | Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report | Ultimate heat sink Anticipated operational occurrence Internal Flooding Probabilistic Risk Assessment Design basis earthquake Maintenance Rule Program Turbine Missile Fatality |
| ML21090A033 | 31 March 2021 | Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) | Non-Destructive Examination |
| W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System | 29 January 2021 | Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System | Cyber Security |
| W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System | 23 July 2020 | License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System | Safe Shutdown Shutdown Margin Anticipated operational occurrence Commercial Grade Dedication Post Accident Monitoring Probabilistic Risk Assessment Coatings Cyber Security B.5.b Surveillance Frequency Control Program Process Control Program Fuel cladding Affidavit |
| W3F1-2019-0022, Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results | 14 March 2019 | Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results | |
| ML18215A178 | 30 June 2018 | WCAP-18169-NP, Rev 1, Arkansas Nuclear One Unit 2 Heatup and Cooldown Limit Curves for Normal Operation. | Hydrostatic |
| RBG-47873, License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List, Revised Commitment 5 | 13 June 2018 | License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List, Revised Commitment 5 | Aging Management |
| RBG-47870, License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List | 6 June 2018 | License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List | Aging Management |
| ML17236A179 | 22 August 2017 | Arkansas, Units 1 and 2, ANO Emergency Plan On-Shift Staffing Analysis Report, Revision 2 | Safe Shutdown High Radiation Area Severe Accident Management Guideline Minimum staff 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 |
| ML17163A185 | 30 June 2017 | Biological Evaluation of Impacts to Federally Listed Species for Waterford License Renewal | |
| RBG-47770, Focused Evaluation of External Flooding | 28 June 2017 | Focused Evaluation of External Flooding | Hydrostatic 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 |
| 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 |
| ML16365A027 | 31 October 2016 | ANP-3486NP, Revision 0, MRP-227-A Applicant/Licensee Action Item 6 Analysis for Arkansas Nuclear One Unit 1 (ANO-1). | Nondestructive Examination |
| ML16293A584 | 30 September 2016 | WCAP-18166-NP, Revision 0, Analysis of Capsule 284 from the Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 Reactor Vessel Radiation Surveillance Program. | |
| ML16202A167 | 5 July 2016 | Report 1500227.401, PWR Internals Aging Management Program Plan. | Nondestructive Examination Functionality Assessment Aging Management EVT-1 |
| ML16090A058 | 24 March 2016 | Submittal of Regulatory Conference Documents for April 4, 2016. Attachment 3: Engineering Report No. RBS-ME-16-00002, Main Control Room Heat-Up Analysis During Loss of HVAC Conditions for 24 Hours | |
| ML16090A059 | 24 March 2016 | Submittal of Regulatory Conference Documents for April 4, 2016. Attachment 6: Engineering Report No. RBS-ME-15-00036, Main Control Room (MCR) Operator Habitability Under Beyond Design Basis Loss of HVAC Conditions | Ultimate heat sink FLEX Preliminary White Finding |
| ML16090A057 | 24 March 2016 | Submittal of Regulatory Conference Documents for April 4, 2016. Attachment 2: Engineering Report No. RBS-ME-16-00003, Evaluation of Main Control Room Realistic Heat Load Based on Measured Data | |
| GNRO-2016/00015, Non-Proprietary Version of MP Machinery and Testing, LLC (Mpm) Proprietary Report 814779, Revs 1 & 2, Neutron Transport Analysis for Grand Gulf Nuclear Station, Previously Included in Letters GNRO-2014/0080 and GNRO-2015/00011 | 23 March 2016 | Non-Proprietary Version of MP Machinery and Testing, LLC (Mpm) Proprietary Report 814779, Revs 1 & 2, Neutron Transport Analysis for Grand Gulf Nuclear Station, Previously Included in Letters GNRO-2014/0080 and GNRO-2015/00011 | |
| ML16004A179 | 31 December 2015 | Attachment 2, ANP-3418NP, Revision 0, Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2) Licensing Report. (Non-Proprietary) | Safe Shutdown Aging Management |
| ML15278A024 | 28 September 2015 | Attachment 2, Areva Document ANP-3417NP, Revision 0, MRP-227-A Applicant / Licensee Action Item No. 7 Analysis for Arkansas Nuclear One, Unit 1 (Non-Proprietary), Attachment 3, Affidavit, and Attachment 4, List of Commitments | Safe Shutdown Earthquake Aging Management |
| ML15268A020 | 23 September 2015 | Attachment 3, Fuel Thermal Conductivity Degradation Evaluation (Non-Proprietary) | |
| ML15071A055 | 31 March 2015 | ANP-3300Q2NP, Revision 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1. | |
| ML15041A074 | 6 February 2015 | ANP-3300Q1NP, Rev. 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1, Attachment 2 to 1CAN0 | Hydrostatic Aging Management |
| ML14330A250 | 30 November 2014 | Attachment 4 to 1CAN111401, ANP-3300, Revision 1, Pressure-Temperature Limits at 54 Efpy. | Hydrostatic Exemption Request |
| ML14241A241 | 30 June 2014 | ANP-3300, Arkansas Nuclear One (ANO) Unit 1 Pressure-Temperature Limits at 54 EFPY, Attachment 4 | Hydrostatic Exemption Request |
| ML14139A380 | 14 May 2014 | CALC-ANO1-CS-12-00003, Revision 1, Flooding Walkdown Report for Resolution of Fukushima Near Term Task Force Recommendation 2.3, Attachment 1 to 0CAN051402 | High Radiation Area Locked High Radiation Area Fukushima Dai-Ichi Maintenance Rule Program |
| ML14139A381 | 14 May 2014 | CALC-ANO2-CS-12-00002, Revision 1, Flooding Walkdown Report for Resolution of Fukushima Near Term Task Force Recommendation 2.3, Attachment 2 to 0CAN051402 | High Radiation Area Fukushima Dai-Ichi Maintenance Rule Program Through-Wall Leak Scaffolding |
| 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 |
| ML14141A555 | 1 May 2014 | Attachment 1 to 1CAN051403 PWR Internals Aging Management Program Plan | Nondestructive Examination Functionality Assessment Aging Management EVT-1 |
| RBG-47447, Report 51-9207360-000, Entergy Fleet Fukushima Program Flood Hazard Reevaluation Report for River Bend Station. | 10 March 2014 | Report 51-9207360-000, Entergy Fleet Fukushima Program Flood Hazard Reevaluation Report for River Bend Station. | Safe Shutdown Ultimate heat sink Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Fukushima Dai-Ichi Frazil ice Earthquake |
| ML14056A167 | 25 February 2014 | Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for River Bend Station, Unit 1(PUBLIC) | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Seismically rugged Design basis earthquake Frazil ice Earthquake |
| ML13365A281 | 25 February 2014 | Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Seismically rugged Design basis earthquake Frazil ice Earthquake |
| ML14007A459 | 25 February 2014 | Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting FLEX Tornado Generated Missile Fukushima Dai-Ichi Job Performance Measure Seismically rugged Design basis earthquake Frazil ice Earthquake |