| 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 |
ML20296A391
|
| 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 |