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Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2020
| Documents added in 2020 | |||
|---|---|---|---|
| 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/KM-0001, S2 | Three Mile Island Accident of 1979 Knowledge Management Digest: The Cleanup Experience - A Literature Review |
December 2020 | ML20364A243 |
| NUREG/CR-7274 | Validation of a Computational Fluid Dynamics Method Using Horizontal Dry Cask Simulator Data | December 2020 | ML20357A056 |
| NUREG/KM-0015, DFC | Considerations for Estimating Site-Specific Probable Maximum Precipitation at Nuclear Power Plants in the United States of America: Draft Report for Comment | December 2020 | ML20356A293 |
| NUREG-2242, DFC | Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030: Draft for Comment | December 2020 | ML20342A132 |
| NUREG-1757, V2, R2, DFC | Consolidated Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria: Draft Report for Comment | November 2020 | ML20273A010 |
| NUREG-1021, R12, DFC | Operator Licensing Examination Standards for Power Reactors: Draft Report for Comment | November 2020 | ML20329A326 |
| NUREG/CR-2907, V24 | Radioactive Effluents from Nuclear Power Plants: Annual Report 2018 | November 2020 | ML20325A229 |
| NUREG-1415, V34, N2 | Office of the Inspector General Semiannual Report to Congress: April 1, 2020 – September 30, 2020 | October 2020 | ML20335A211 |
| NUREG-2224 | Dry Storage and Transportation of High Burnup Spent Nuclear Fuel – Final Report | November 2020 | ML20191A321 |
| NUREG-1556, V20, R1 | Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures – Final Report | November 2020 | ML20318A384 |
| NUREG-2220, V4 | Fiscal Year 2020 – Agency Financial Report | November 2020 | ML20321A325 |
| NUREG/IA-0521 | Analysis with TRACE Code of PKL III Tests G1.2. Study on Heat Transfer Mechanisms in the SG in Presence of Nitrogen, Steam and Water as a Function of the Primary Coolant Inventory in Double Loop Operation | November 2020 | ML20315A453 |
| NUREG-1307, R18, DFC | Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities, Draft Report for Comment | October 2020 | |
| NUREG-2243, DFC | Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in McKinley County, New Mexico – Draft for Comment | October 2020 | ML20289A621 |
| NUREG/BR-0359, R3 | Modeling Potential Reactor Accident Consequences, State-of-the-Art Reactor Consequence Analyses: Using decades of research and experience to model accident progression, mitigation, emergency response, and health effects | October 2020 | ML20304A339 |
| NUREG-2236, V3 | Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Plant Analysis Risk Models–Duane Arnold: Appendices F – H | October 2020 | ML20300A240 |
| NUREG-2236, V2 | Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Plant Analysis Risk Models–Duane Arnold: Appendices D – E | October 2020 | ML20300A236 |
| NUREG-2236, V1 | Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Plant Analysis Risk Models–Duane Arnold: Chapters 1 – 8, Appendices A – C | October 2020 | ML20300A225 |
| NUREG-1503, S2 | Final Safety Evaluation Report: Related to the Certification of the Advanced Boiling Water Reactor Design | October 2020 | ML20301A886 |
| NUREG-1885, R13 | Report to Congress on the Security Inspection Program for Operating Commercial Power Reactors and Category I Fuel Cycle Facilities: Results and Status Update – Annual Report for Calendar Year 2019 | October 2020 | ML20290B044 |
| NUREG-2233 | Methodology for Modeling Transient Fires in Nuclear Power Plant Fire Probabilistic Risk Assessment | October 2020 | ML20289A568 |
| NUREG/CR-7265, V2 | Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types. Appendices A – K | October 2020 | ML20281A604 |
| NUREG/CR-7265, V1 | Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types. Chapters 1 – 7 | October 2020 | ML20281A565 |
| NUREG/CR-7272 | NRC ATWS-I Stability Tests with Downskew Axial Power Profile: KATHY Test Series STS123 | September 2020 | ML20275A101 |
| NUREG/CR-7210 | Development and Validation of Models for Predicting Leakage from Degraded Tube-to-Tubesheet Joints During Severe Accidents | July 2020 | ML20204A871 |
| NUREG/1123, R3 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors – Final Report | September 2020 | ML20260H086 |
| NUREG/1122, R3 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors – Final Report | September 2020 | ML20260H083 |
| NUREG/IA-0519, R1 | Survey of Member Countries' Nuclear Power Plant Fire Protection Regulations by the OECD Nuclear Energy Agency (NEA) Fire Incidents Records Exchange (FIRE) Database Project – Topical Report No. 2 | September 2020 | ML20258A177 |
| NUREG/BR-0007, R8 | Instructions for the Preparation and Distribution of Material Status Reports (DOE/NRC Forms 742 and 742C) – Final | August 2020 | ML20240A181 |
| NUREG/KM-0014 | History and Activities of the NRC Committee to Review Generic Requirements | August 2020 | ML20241A232 |
| NUREG/BR-0006, R9 | Instructions for Completing Nuclear Material Transaction Reports: (DOE/NRC Forms 741 and 740M) | August 2020 | ML20240A155 |
| NUREG/IA-0519 | Survey of Member Countries' Nuclear Power Plant Fire Protection Regulations by the OECD Nuclear Energy Agency (NEA) Fire Incidents Records Exchange (FIRE) Database Project – Topical Report No. 2 | August 2020 | ML20239A807 |
| NUREG-2216 | Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material: Final Report | August 2020 | ML20234A651 |
| NUREG-1507, R1 | Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions | August 2020 | ML20233A507 |
| NUREG-0016, R1 | Calculation of Releases of Radioactive Materials in Gaseous Liquid Effluents from Boiling Water Reactors (BWR-Gale Code) | January 1979 | ML091910213 |
| NUREG-0017, R2 | Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors: GALE-BWR 3.2 Code | July 2020 | ML20213C729 |
| NUREG-0016, R2 | Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors: GALE-BWR 3.2 Code | July 2020 | ML20213C728 |
| NUREG-2228 | Weld Residual Stress Finite Element Analysis Validation: Part II—Proposed Validation Procedure – Final Report | July 2020 | ML20212L592 |
| NUREG-0700, R3 | Human-System Interface Design Review Guidelines | July 2020 | ML20162A214 |
| NUREG-1480 | Loss of an Iridium-192 Source and Therapy Misadministration at Indiana Regional Cancer Center Indiana, Pennsylvania, on November 16, 1992 | February 1993 | ML20198M497 |
| NUREG-1482, R3 | 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 | July 2020 | ML20202A473 |
| NUREG/CR-6210 | Computer Codes for Evaluation of Control Room Habitability (HABIT) | June 1996 | ML063480558 |
| NUREG-2238 | Validation of a Computational Fluid Dynamics Method Using Vertical Dry Cask Simulator Data | June 2020 | ML20182A706 |
| NUREG/BR-0204, R3 | Instructions for Completing the U.S. Nuclear Regulatory Commission's Uniform Low-Level Radioactive Waste Manifest – Final Report. | June 2020 | ML20178A433 |
| NUREG-2178, V2 | Fire Modeling Guidance for Electrical Cabinets, Electric motors, Indoor Dry Transformers, and the Main Control Board | June 2020 | ML20168A655 |
| NUREG-2230 | Methodology for Modeling Fire Growth and Suppression Response for Electrical Cabinet Fires in Nuclear Power Plants | June 2020 | ML20157A148 |
| NUREG-0090, V42 | Report to Congress on Abnormal Occurrences, Fiscal Year 2019 | June 2020 | ML20162A165 |
| NUREG/IA-0520 | Simulation with RELAP5/MOD3.3 of an Integral-Effect Test on Loop-Seal Clearing in the Upper Plenum Test Facility During Test A5 | June 2020 | ML20156A331 |
| NUREG/IA-0468, R1 | Validation of RELAP5 Model of Ringhals 4 against a Load Step Test at Uprated Power | June 2020 | ML20156A309 |
| NUREG-2229 | Safety Evaluation Report: Northwest Medical Isotopes, LLC Construction Permit Application for a Radioisotope Production Facility | May 2020 | ML20153A468 |
| NUREG-1415, V34, N1 | Office of the Inspector General Semiannual Report to Congress: October 1, 2019 – March 31, 2020 | April 2020 | ML20147A661 |
| NUREG/CR-7256, V2 | Effects of Environmental Conditions on Manual Actions for Flood Protection and Mitigation: Review of the Research Literature | May 2020 | ML20147A665 |
| NUREG/CR-7256, V1 | Effects of Environmental Conditions on Manual Actions for Flood Protection and Mitigation: Identifying Conditions, Characterizing Actions and Assessing Impacts | May 2020 | ML20147A640 |
| NUREG-2239, DFC | Environmental Impact Statement for Interim Storage Partners LLC's License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas | May 2020 | ML20122A220 |
| NUREG-2215 | Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities - Final Report | April 2020 | ML20121A190 |
| NUREG-1437, Supplement 6, Second Renewal | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 6, Second Renewal Regarding Subsequent License Renewal for Surry Power Station Units 1 and 2 - Final Report | April 2020 | ML20071D538 |
| NUREG-2232 | Heat Release Rate and Fire Characteristics of Fuels Representative of Typical Transient Fire Events in Nuclear Power Plants | March 2020 | ML20091L481 |
| NUREG-0713, V40 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2018: Fifty-First Annual Report | March 2020 | ML20087J424 |
| NUREG/CR-7269 | Enhancing Guidance for Evacuation Time Estimate Studies | March 2020 | ML20070M158 |
| NUREG-1409, R1, DFC | Backfitting Guidelines - Draft Report for Comment | March 2020 | ML18109A498 |
| NUREG-2237, DFC | Environmental Impact Statement for the Holtec International's License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel and High Level Waste | March 2020 | ML20069G420 |
| NUREG-1830, V16 | Office of Investigations – Annual Report 2019 | February 2020 | ML20054A170 |
| NUREG/CR-7131 | Review of Probable Maximum Precipitation Procedures and Databases Used to Develop Hydrometeorological Reports | February 2020 | ML20043E110 |
| NUREG-1921, S1 | EPRI/NRC-RES Fire Human Reliability Analysis Guidelines—Qualitative Analysis for Main Control Room Abandonment Scenarios, Supplement 1 | February 2020 | ML20035E043 |
| NUREG-1100, V36 | Congressional Budget Justification: Fiscal Year 2021 Summary | February 2020 | ML20024D764 |
| NUREG/CR-7266 | MELCOR Modeling of Accident Scenarios at a Facility for Aqueous Reprocessing of Spent Nuclear Fuel | January 2020 | ML20030B798 |
| NUREG/IA-0518 | PWR PACTEL Small Break LOCA Experiment SBL-50 Calculation with TRACE Code | January 2020 | ML20029D760 |
| NUREG/IA-0516 | LOCAs With Loss of One Active Emergency Cooling System Simulated by RELAP5 | January 2020 | ML20028D808 |
| NUREG/IA-0517 | Analysis of Maanshan Station Blackout Accident and Rescue Procedures under Different Tube Plugging Situations with TRACE | January 2020 | ML20028D511 |
| NUREG-1437, S10, Second Renewal | Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 10, Second Renewal, Regarding Subsequent License Renewal for Peach Bottom Atomic Power Station, Units 2 and 3: Final Report | January 2020 | ML20023A937 |
| NUREG-0570 | Toxic Vapor Concentrations in the Control Room Following a Postulated Accidental Release | June 1979 | ML063480551 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026