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Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2011
| Documents added in 2011 | |||
|---|---|---|---|
| V = Volume | N = Number | R =Revision | P = Part | S = Supplement | Ch = Chapter | Add = Addendum | Sec = Section | DFC = Draft For Comment | |||
| PUBLICATION NUMBER | TITLE | DATE OF PUBLICATION | ADAMS ACCESSION NUMBER |
| NUREG/CR-7028 V1 | Engineered Covers for Waste Containment: Changes in Engineering Properties and Implications for Long-Term Performance Assessment (Main Report) | Dec 2011 | ML12005A110 |
| NUREG/CR-7028 V2 | Engineered Covers for Waste Containment: Changes in Engineering Properties and Implications for Long-Term Performance Assessment: Appendices | Dec 2011 | ML12005A111 (Package) |
| NUREG/BR-0476 V1 | 2011 New Reactor Program | Dec 2011 | ML12004A009 |
| NUREG-1650 Add 4 | Answers to Questions from the Peer Review by Contracting Parties on the United States of America Fifth National Report for the Convention on Nuclear Safety | Dec 2011 | ML12003A114 |
| NUREG-2113 DFC | Environmental Impact Statement for the Proposed Fluorine Extraction Process and Depleted Uranium Deconversion Plant in Lea County, New Mexico (Draft for Comment) | Dec 2011 | ML12001A000 (Package) |
| NUREG/IA-0403 | Full Scale Loop Seal Experiments with TRACE V5 Patch 1 | Dec 2011 | ML11355A126 |
| NUREG/IA-0406 | Post-Test Calculations on Steam Cool-Down Test QUENCH-04 with RELAP5, SCDAP/RELAP5, and TRACE | Dec 2011 | ML11355A127 |
| NUREG/BR-0164 R8 | NRC: Independent Regulator of Nuclear Safety | Dec 2011 | ML11356A051 |
| NUREG-2104 DFC | Knowledge and Abilities Catalog for Nuclear Power Plant Operators Advanced Boiling Water Reactors (Draft for Comment) | Dec 2011 | ML11354A280 |
| NUREG-0933 S34 | Resolution of Generic Safety Issues | Dec 2011 | ML11353A382 |
| NUREG/CR-7114 DFC | Methodology for Low Power/Shutdown Fire PRA (Draft for Comment) | Dec 2011 | ML11353A377 |
| NUREG-2111 V1 DFC | Draft Environmental Impact Statement for Combined Licenses (COLs) for William States Lee III Nuclear Station Units 1 and 2 (Draft for Comment) | Dec 2011 | ML11343A010 |
| NUREG-2111 V2 DFC | Draft Environmental Impact Statement for Combined Licenses (COLs) for William States Lee III Nuclear Station Units 1 and 2 (Draft for Comment) | Dec 2011 | ML11343A011 |
| NUREG/CR-7102 | Kerite Analysis in Thermal Environment of FIRE (KATE-Fire): Test Results | Dec 2011 | ML11333A033 |
| NUREG-0654 R1 S3 | Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants | Nov 2012 | ML113010596 |
| NUREG-0847 S25 | Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 | Nov 2011 | ML12011A024 |
| NUREG/CR-7004 | Technical Basis for Regulatory Guidance on Design-Basis Hurricane-Borne Missile Speeds for Nuclear Power Plants | Nov 2011 | ML11341A102 |
| NUREG/CR-7005 | Technical Basis for Regulatory Guidance on Design-Basis Hurricane Wind Speeds for Nuclear Power Plants | Nov 2011 | ML11335A031 |
| NUREG/BR-0356 | New Reactors: Striving for Enhanced Safety | Nov 2011 | ML11343A026 |
| NUREG/CR-7113 | An Assessment of Ultrasonic Techniques for Far-Side Examinations of Austenitic Stainless Steel Piping Welds | Nov 2011 | ML12011A126 (Package) |
| NUREG/CR-7002 | Criteria for Development of Evacuation Time Estimate Studies | Nov 2011 | ML11329A053 |
| NUREG/CR-7046 | Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America | Nov 2011 | ML11321A195 |
| NUREG/CR-7038 | Verification of RESRAD-OFFSITE | Nov 2011 | ML11321A185 |
| NUREG/CR-7116 | Materials Aging Issues and Aging Management for Extended Storage and Transportation of Spent Nuclear Fuel | Nov 2011 | ML11321A182 |
| NUREG/CR-7002 | Criteria for Development of Evacuation Time Estimate Studies | Nov 2011 | ML11329A053 |
| NUREG-1556 V2 R1 DFC | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Industrial Radiography Licenses (Draft for Comment) | Nov 2011 | ML11312A123 |
| NUREG-2103 DFC | Knowledge and Abilities Catalog for Nuclear Plant Operators: Pressurized Water Reactors, Westinghouse AP100 (Draft for Comment) | Oct 2011 | ML11307A367 |
| NUREG/CR-7105 | Radionuclide Release from Slag and Concrete Waste Materials, Part 2: Relationship Between Laboratory Tests and Field Leaching | Oct 2011 | ML11307A347 |
| NUREG-2112 | Public Comment Analysis and Adjudication: Supplement 3 to NUREG-0654/FEMA-REP-1, “Guidance for Protective Action Strategies | Oct 2011 | ML11292A153 |
| NUREG-2105 V1 DFC | Draft Environmental Impact Statement for Combined License (COL) for Enrico Fermi Unit 3 (Draft for Comment) | Oct 2011 | ML11287A108 |
| NUREG-2105 V2 DFC | Draft Environmental Impact Statement for Combined License (COL) for Enrico Fermi Unit 3 (Draft for Comment) | Oct 2011 | ML11287A109 |
| NUREG/IA-0405 | Coupling the RELAP Code with External Calculation Programs (Shared Memory Version) | Oct 2011 | ML11308A038 |
| NUREG/IA-0256 | Simulation of PKL Loss of RHRS Experiment E3.1 with RELAP5 and TRACE Codes – Application to a PWR NPP Model | Sept 2011 | ML11306A053 |
| NUREG/IA-0257 | Simulation of PKL Loss of RHRS Experiment F2.2 Run 2 with RELAP5 and TRACE Codes – Application to a PWR NPP Model | Sept 2011 | ML11306A056 |
| NUREG/CR-7045 | Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data | Sept 2011 | ML11294A199 |
| NUREG-1793 V1 S1 | Final Safety Evaluation Report Related to Certification of the AP1000 Standard Plant Design (Beginning through Chapter 8) | Sept 2011 | ML11293A087 (Package) |
| NUREG-1793 V2 S1 | Final Safety Evaluation Report Related to Certification of the AP1000 Standard Plant Design (Chapters 9 through 24) | Sept 2011 | ML11292A141 (Package) |
| NUREG-1793 V3 S1 | Final Safety Evaluation Report Related to Certification of the AP1000 Standard Plant Design (Appendix A to End) | Sept 2011 | ML11292A113 |
| NUREG/BR-0240 R4 | Reporting Safety Concerns to the NRC | Sept 2011 | ML11277A149 |
| NUREG/BR-0240 R4 (Spanish Version) | Reportar Las Preocupaciones De Seguridad A La NRC (Reporting Safety Concerns to the NRC) | Sept 2011 | ML11277A157 |
| NUREG-1022 Rev 3 DFC | NUREG-1022 Rev 3 DFC "Event Report Guidelines 10 CFR 50.72 and 50.73" (Draft for Comment) | Sept 2011 | ML11273A065 |
| NUREG-0847 S24 | Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2 | Sept 2011 | ML11277A148 |
| NUREG/CR-7103 V1 | Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys | Sept 2011 | ML11277A221 (Package) |
| NUREG-1953 | Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models – Surry and Peach Bottom | Sept 2011 | ML11256A023 |
| NUREG-2109 | Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Repository License Application – Administrative and Programmatic Volume | Sept 2011 | ML11255A002 |
| NUREG-2108 | Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Repository License Application - Preclosure Volume | Sept 2011 | ML11250A093 |
| NUREG/IA-0216 V2 | International HRA Empirical Study – Phase 2 Report: Results from Comparing HRA Method Predictions to Simulator Data from SGTR Scenarios | Aug 2011 | ML11250A010 |
| NUREG-1350 V23 | Information Digest 2011-2012 | Aug 2011 | ML11241A096 |
| NUREG/CP-0195 | Proceedings of the Workshop on Engineered Barrier Performance Related to Low-Level Radioactive Waste, Decommissioning, and Uranium Mill Tailings Facilities | Aug 2011 | ML11238A056 |
| NUREG-1482 R2 DFC | Guidelines for Inservice Testing at Nuclear Power Plants, Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants´(Draft for Comment) | Aug 2011 | ML11224A036 |
| NUREG-1960 | Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plants Unit 1 and 2 | Aug 2011 | ML11235A622 |
| NUREG-1960 S1 | Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plants Unit 1 and 2 | Aug 2011 | ML11236A175 |
| NUREG-IA-0255 | Coupled RELAP/PARCS Full Plant Model - Assessment of a Cooling Transient in Trillo Nuclear Power Plant | Aug 2011 | ML11222A125 |
| NUREG-1437 S47 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Columbia Generating Station | Aug 2011 | ML11227A007 |
| NUREG-2107 | Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Repository License Application | Aug 2011 | ML11223A273 |
| NUREG/CP-0152 V8 | Proceedings of the Eleventh NRC/ASME Symposium on Valves, Pumps, and Inservice Testing | Aug 2011 | ML11223A005 |
| NUREG/CR-7042 | A Large Scale Validation of a Methodology for Assessing Software Reliability | July 2011 | ML11214A110 |
| NUREG-1437 S46 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Seabrook Station (Draft For Comment) | July 2011 | ML11213A080 (Package) |
| NUREG-0847 S23 | Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2 | July 2011 | ML11206A499 |
| NUREG/BR-0478 R1 | The Generic Issues Program | July 2011 | ML11207A014 |
| NUREG-1934 2nd DFC | Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG) (Draft for Comment) | July 2011 | ML11200A097 |
| NUREG/CR-7044 DFC | Development of Quantitative Software Reliability Models for Digital Protection Systems of Nuclear Power Plants (Draft for Comment) | July 2011 | ML11200A069 |
| NUREG/IA-0254 | Suitability of Fault Modes and Effects Analysis for Regulatory Assurance of Complex Logic in Digital Instrumentation and Control Systems | July 2011 | ML11201A179 |
| NUREG/BR-0478 | The Generic Issues Program | June 2011 | ML11196A096 |
| NUREG/CR-7039 V1 | Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8: Overview and Summary | July 2011 | ML11195A298 |
| NUREG/CR-7039 V2 | Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8: Technical Reference | July 2011 | ML11195A299 |
| NUREG/CR-7039 V3 | Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8: User’s Guide | July 2011 | ML11195A300 |
| NUREG/CR-7039 V4 | Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8: Tutorial | July 2011 | ML11195A128 |
| NUREG/CR-7039 V5 | Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8: Workspaces | July 2011 | ML11195A129 |
| NUREG/CR-7039 V6 | Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8: Quality Assurance | July 2011 | ML11195A130 |
| NUREG/CR-7039 V7 | Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8: Data Loading | July 2011 | ML11195A131 |
| NUREG/BR-0474 R1 | A Journey to Your Future: Make Discovering Your Career an Adventure | June 2011 | ML13010A446 |
| NUREG/BR-0314 R2 | Protecting Our Nation: A Report of the U.S. Nuclear Regulatory Commission | June 2011 | ML11193A004 |
| NUREG/CR-7101 | Structural Materials Analyses of the Newhall Pass Tunnel Fire, 2007 | June 2011 | ML11182A260 |
| NUREG-1948 | Final Safety Evaluation Report Related to the Aircraft Impact Amendment to the U.S. Advanced Boiling Water Reactor (ABWR) Design Certification | June 2011 | ML11182A163 |
| NUREG-1885 R4 | Report to Congress on the Security Inspection Program for Commercial Power Reactors and Category I Fuel Cycle Facilities: Results and Status Update | June 2011 | ML11181A024 |
| NUREG/IA-0254 | Suitability of Fault Modes and Effects Analysis for Regulatory Assurance of Complex Logic in Digital Instrumentation and Control Systems | June 2011 | ML11201A179 |
| NUREG-2102 | Safety Evaluation Report Related to the License Renewal of Hope Creek Generating Station | July 2011 | ML11200A221 |
| NUREG/BR-0500 Spanish Version | Cultura De Seguridad: Declaracion de la politica (Safety Culture Policy Statement) | June 2011 | ML11291A041 |
| NUREG/BR-0500 Printer Friendly | Safety Culture Policy Statement | June 2011 | ML11173A052 |
| NUREG/BR-0500 | Safety Culture Policy Statement | June 2011 | ML11165A021 |
| NUREG-0090 V33 | Report to Congress on Abnormal Occurrences: Fiscal Year 2010 | June 2011 | ML11172A088 |
| NUREG/CR-6918 R1 | VARSKIN 4: A Computer Code for Assessing Skin Dose From Skin Contamination | June 2011 | ML11172A090 |
| NUREG-2101 | Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station | June 2011 | ML11166A135 |
| NUREG-1910 S3 | Environmental Impact Statement for the Lost Creek ISR Project in Sweetwater County: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Final Report) | June 2011 | ML11125A006 |
| NUREG-1437 S44 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Crystal River Unit 3 Nuclear Generating Plant (Draft For Comment) | May 2011 | ML11139A153 |
| NUREG-1943 V1 | Environmental Impact Statement for Combined Licenses (COLs) for Comanche Peak Nuclear Power Plant Units 3 and 4 (Final Report) | May 2011 | ML11131A001 |
| NUREG-1943 V2 | Environmental Impact Statement for Combined Licenses (COLs) for Comanche Peak Nuclear Power Plant Units 3 and 4 (Final Report) | May 2011 | ML11131A002 |
| NUREG-1936 V1 | Environmental Impact Statement for Combined License (COL) for Calvert Cliffs Nuclear Power Plant Unit 3 (Final Report) | May 2011 | ML11129A167 |
| NUREG-1936 V2 | Environmental Impact Statement for Combined License (COL) for Calvert Cliffs Nuclear Power Plant Unit 3 (Final Report) | May 2011 | ML11129A179 |
| NUREG/CR-7040 | Evaluation of JNES Equipment Fragility Tests for Use in Seismic Probabilistic Risk Assessments for U.S. Nuclear Power Plants | April 2011 | ML11129A103 |
| NUREG/IA-0245 | Assessment of TRACE 5.0 against ROSA Test 6-1, Vessel Upper Head SBLOCA | April 2011 | ML11115A045 |
| NUREG-1950 | Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800 | April 2011 | ML11116A062 |
| NUREG/IA-0253 | Development of a Computer Tool for In-Depth Analysis and Post Processing of the RELAP5 Thermal Hydraulic Code | April 2011 | ML11118A088 |
| NUREG/CR-7029 | Lessons Learned in Detecting, Monitoring, Modeling, and Remediating Radioactive Ground-Water Contamination | April 2011 | ML11118A087 |
| NUREG-1964 | Access Control Systems | April 2011 | ML11115A078 |
| NUREG/IA-0242 | Qualification of the Three-Dimensional Thermal Hydraulic Model of TRACE Using Plant Data | April 2011 | ML11108A046 |
| NUREG-1961 | Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Units 1, 2 and 3 | April 2011 | ML11095A011 |
| NUREG-1939 V1 | Final Environmental Impact Statement for Combined Licenses (COLs) for Virgil C. Summer Nuclear Station Units 2 and 3 (Final) | April 2011 | ML11098A044 |
| NUREG-1939 V2 | Final Environmental Impact Statement for Combined Licenses (COLs) for Virgil C. Summer Nuclear Station Units 2 and 3 (Final) | April 2011 | ML11098A057 |
| NUREG-0936 V29 N2 | NRC Regulatory Semiannual Agenda: July –December 2010 | March 2011 | ML11126A133 |
| NUREG-1959 | Intrusion Detection Systems and Subsystems: Technical Information for NRC Licensees | March 2011 | ML11112A009 |
| NUREG/CR-7026 | Application of Model Abstraction Techniques to Simulate Transport in Soils | March 2011 | ML111090360 (Package) |
| NUREG-1475 R1 | Applying Statistics | March 2011 | ML11102A076 |
| NUREG-1927 | Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance (Final Report) | March 2011 | ML111020115 |
| NUREG/CR-7022 V1 | FRAPCON-3.4: A Computer Code for the Calculation of Steady-State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup | March 2011 | ML11101A005 |
| NUREG/CR-7022 V2 | FRAPCON-3.4: Integral Assessment | March 2011 | ML11101A006 |
| NUREG/CR-7023 V1 | FRAPTRAN 1.4: A Computer Code for Transient Analysis of Oxide Fuel Rods | March 2011 | ML11101A008 |
| NUREG/CR-7023 V2 | FRAPTRAN 1.4: Integral Assessment | March 2011 | ML11101A009 |
| NUREG/CR-7024 | Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO | March 2011 | ML11101A012 |
| NUREG-1947 | Final Supplemental Environmental Impact Statement for Combined Licenses (COLs) for Vogtle Electric Generating Plant, Units 3 and 4 | March 2011 | ML11076A010 |
| NUREG-1437 S45 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1 and 2 Final Report) | March 2011 | ML11089A021 |
| NUREG-1830 V7 | USNRC Office of Investigations Annual Report Fiscal Year 2010 | Feb 2011 | ML11054A015 |
| NUREG/BR-0451 | Church Street Building Parking And Transportation Services | Feb 2011 | ML11153A123 |
| NUREG-0980 V1 N9 | Nuclear Regulatory Legislation, 111th Congress; 2nd Session | Feb 2011 | ML110880560 |
| NUREG-0890 V2 N9 | Nuclear Regulatory Legislation, 111th Congress; 2nd Session | Feb 2011 | ML110880600 |
| NUREG-0980 V3 N9 | Nuclear Regulatory Legislation, 111th Congress; 2nd Session | Feb 2011 | ML110880746 |
| NUREG/IA-0252 | The Development and Verification of TRACE Model for IIST Experiments | Feb 2011 | ML110660139 |
| NUREG/IA-0251 | Improvement of RELAPS5/MOD3.3 Reflood Model Based on the Assessments Against FLECHT-SEASET Test | Feb 2011 | ML110740241 |
| NUREG/IA-0250 | Simulation of the F2.1 Experiment at PKL Facility using RELAP5/MOD3 | Feb 2011 | ML110740242 |
| NUREG-IA-0248 | Post-Test Analysis of Hot Leg 2x25% Break at PSB-VVER Facility Using TRACE V5.0 Code | Feb 2011 | ML110740240 |
| NUREG/IA-0243 | Development of Vandellos II NPP Model Using the TRACE Code: Application to an Actual Transient of Main Coolant Pumps Trip and Start-Up | Feb 2011 | ML110660129 |
| NUREG-1937 V1 | Environmental Impact Statement for Combined Licenses (COLs) for South Texas Project Electric Generating Station Units 3 and 4 | Feb 2011 | ML11049A000 |
| NUREG-1937 V2 | Environmental Impact Statement for Combined Licenses (COLs) for South Texas Project Electric Generating Station Units 3 and 4 | Feb 2011 | ML11049A001 |
| NUREG/CR-7035 | Analysis of Severe Roadway Accidents Involving Long Duration Fires | Feb 2011 | ML110620106 |
| NUREG/CR-7034 | Analysis of Severe Railway Accidents Involving Long Duration Fires | Feb 2011 | ML110620107 |
| NUREG/CR-7033 | Guidance on Developing Effective Radiological Risk Communication Messages: Effective Message Mapping and Risk Communication with the Public in Nuclear Plant Emergency Planning Zones | Feb 2011 | ML110490120 |
| NUREG/CR-7032 | Developing an Emergency Risk Communication (ERC)/Joint Information Center (JIC) Plan for A Radiological Emergency | Feb 2011 | ML110490119 |
| NUREG/IA-0247 | RELAP5 Simulation of Darlington Nuclear Generating Station Loss of Flow Event | Feb 2011 | ML110410202 |
| NUREG-1945 V1 | Environmental Impact Statement for the Proposed Eagle Rock Enrichment Facility in Bonneville County, Idaho" Final Report | Feb 2011 | ML11014A005 |
| NUREG-1945 V2 | Environmental Impact Statement for the Proposed Eagle Rock Enrichment Facility in Bonneville County, Idaho" Final Report | Feb 2011 | ML11014A006 |
| NUREG/BR-0342 R2 | Emergency Preparedness and Incident Response | Jan 2011 | ML11229A018 |
| NUREG-0847 S22 | Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant Unit 2 | Jan 2011 | ML110390197 |
| NUREG-1958 | Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station | Jan 2011 | ML110340147 (Package) |
| NUREG/CR-7013 | Analysis of Experimental Data for High-Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor | Jan 2011 | ML110140201 |
| NUREG/CR-7012 | Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel | Jan 2011 | ML110140213 |
| NUREG-1910 S2 | Environmental Impact Statement (EIS) for the Nichols Ranch ISR Project in Campbell and Johnson Counties, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Final Report) | Jan 2011 | ML103440120 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026