| Documents added in 2016 |
| 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/BR-0526 | U.S. Nuclear Regulatory Commission's Role in the Five-Year Plan to Address Uranium Contamination in the Navajo Nation | December 2016 | ML16341A800 |
| NUREG-1556, V13, R2, DFC | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Commercial Radiopharmacy Licenses, Draft Report for Comment | December 2016 | ML16356A040 |
| NUREG/CR-7223 | Tsunami Hazard Assessment: Best Modeling Practices and State-of-the-Art Technology | December 2016 | ML16357A270 |
| NUREG-2210 | Safety Evaluation Report: Related to the License Renewal of Fermi 2, Docket Number 50-341, DTE Electric Company | December 2016 | ML16356A234 |
| NUREG-2180 | Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities (DELORES-VEWFIRE) – Final Report | December 2016 | ML16343A058 |
| NUREG-1910, S6 | Environmental Impact Statement for the Reno Creek In Situ Recovery Project in Campbell County, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities, Final Report | December 2016 | ML16342A973 |
| NUREG-2176, S1 | Environmental Impact Statement for Combined Licenses (COLs) for Turkey Point Nuclear Plant Units 6 and 7 | December 2016 | ML16337A147 |
| NUREG-1556 V21, R1 | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Possession Licenses for Production of Radioactive Material Using an Accelerator | November 2016 | ML16336A536 |
| NUREG/IA-0476 | Main Steam Line Break Analysis for Lungmen ABWR | November 2016 | ML16333A332 |
| NUREG-1556, V9, R3 | Consolidated Guidance About Materials Licenses, Program-Specific Guidance About Medical Use Licenses – Draft Report for Comment | November 2016 | ML16328A214 |
| NUREG/BR-0525 | Office of Investigations | November 2016 | ML16328A004 |
| NUREG/IA-0477 | Thermal Hydraulic and Fuel Rod Mechanical Combination Analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP Interface | November 2016 | ML16327A466 |
| NUREG-1307, R16, DFC | Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities | November 2016 | ML16315A300 |
| NUREG-2211 | Safety Evaluation Report: Related to the License Renewal of Grand Gulf Nuclear Station, Unit 1, Docket Number 50-416, Entergy Operations, Inc. | November 2016 | ML16320A015 |
| NUREG-1542, V22 | Performance and Accountability Report Fiscal Year 2016 | November 2016 | ML16320A585 |
| NUREG/BR-0117, N16-04 | NMSS News Link Fall 2016 | November 2016 | ML16319A012 |
| NUREG/IA-0475 | TRACE/RELAP5 Comparative Calculations For Double-Ended LBLOCA and SBO | November 2016 | ML16309A080 |
| NUREG/IA-0473 | Feedwater Line Break Analysis Using RELAP5/MOD3.3 for Steam Generator Blowdown Load Assessment | November 2016 | ML16309A068 |
| NUREG-1824, S1 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications | November 2016 | ML16309A011 |
| NUREG-2209, DFC | Environmental Impact Statement for Construction Permit for the Northwest Medical Isotopes Radioisotope Production Facility | October 2016 | ML16305A029 |
| NUREG-2176, V4 | Environmental Impact Statement for Combine Licenses (COLs) for Turkey Point Nuclear Plant Units 6 and 7 – Final report – Exhibit E | October 2016 | ML16300A312 |
| NUREG-2176, V3 | Environmental Impact Statement for Combine Licenses (COLs) for Turkey Point Nuclear Plant Units 6 and 7 – Final report – Appendices A to K | October 2016 | ML16301A018 |
| NUREG-2176, V2 | Environmental Impact Statement for Combine Licenses (COLs) for Turkey Point Nuclear Plant Units 6 and 7 – Final report – Chapters 7 to 12 | October 2016 | ML16300A137 |
| NUREG-2176, V1 | Environmental Impact Statement for Combine Licenses (COLs) for Turkey Point Nuclear Plant Units 6 and 7 – Final report – Chapters 1 to 6 | October 2016 | ML16300A104 |
| NUREG-1650, R6 | The United States of America Seventh National Report for the Convention on Nuclear Safety | October 2016 | ML16293A104 |
| NUREG/CR-7207, PNNL-23708 | Spent Fuel Transportation Package Response to the Newhall Pass Tunnel Fire Scenario, Final Report | October 2016 | ML16291A052 |
| NUREG/CR-7206, PNNL-23701 | Spent Fuel Transportation Package Response to the MacArthur Maze Fire Scenario, Final Report | October 2016 | ML16291A041 |
| NUREG-2202 | Safety Evaluation Report – Related to the Early Site Permit Application in the Matter of PSEG Power, LLC and PSEG Nuclear, LLC for the PSEG Early Site Permit Site – Docket No. 52-043 – PSEG Power, LLC and PSEG Nuclear, LLC | October 2016 | ML16280A024 |
| NUREG/CR-7218, V1 | Rod Bundle Heat Transfer Facility Two-Phase Mixture Level Swell and Uncovery Test Experiments Data Report | October 2016 | ML16277A168 |
| NUREG/CR-7218, V2 | Rod Bundle Heat Transfer Facility Two-Phase Mixture Level Swell and Uncovery Test Experiments Data Report | October 2016 | ML16277A245 |
| NUREG/CR-7217, ANL-11/60 | Application of Automated Analysis Software to Eddy Current Inspection Data from Steam Generator Tube Bundle Mock-up | September 2016 | ML16271A090 |
| NUREG-2205 | Safety Evaluation Report, Related to the License Renewal of LaSalle County Station, Units 1 and 2, Docket Nos. 50-373 and 50-374, Exelon Generation Company, LLC | September 2016 | ML16271A039 |
| NUREG/CP-0304 | Proceedings of the International Workshop on the Use of Robotic Technologies at Nuclear Facilities | September 2016 | ML16270A357 |
| NUREG/CR-7227, ORNL/TM-2015/619 | US Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013 | September 2016 | ML16267A351 |
| NUREG/KM-0010, Errata | Errata to WASH-1400 The Reactor Safety Study The Introduction of Risk Assessment in the Regulation of Nuclear Reactors | September 2016 | ML16264A431 |
| NUREG-1437, S56, V2 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Fermi 2 Nuclear Power Plant – Final Report, Appendices | September 2016 | ML16259A109 |
| NUREG-1437, S56, V1 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Fermi 2 Nuclear Power Plant – Final Report, Chapters 1 to 8 | September 2016 | ML16259A103 |
| NUREG/BR-0500, R2 | Safety Culture Policy Statement – Spanish | September 2016 | ML16252A437 |
| NUREG/IA-0468 | Validation of RELAP5 Model of Ringhals 4 Against a Load Step Test at Uprated Power | September 2016 | ML16251A085 |
| NUREG-2201 | Probabilistic Risk Assessment and Regulatory Decisionmaking: Some Frequently Asked Questions | September 2016 | ML16245A032 |
| NUREG-1350, V28 | Information Digest, 2016–2017 | September 2016 | ML16243A018 |
| NUREG-0172 | Age-Specific Radiation Dose Commitment Factors for a one-year Chronic Year | September 2016 | ML14083A242 |
| NUREG/IA-0466 | International Agreement Report – Analysis of the OSU-MASLWR 001 and 002 Tests by Using the TRACE Code | August 2016 | ML16244A541 |
| NUREG/CR-7211 | Application of a Hydrological Uncertainty Methodology to Nuclear Reactor Site Evaluations | August 2016 | ML16242A042 |
| NUREG/BR-0292, R1 | Safety of Spent Fuel Transportation | August 2016 | ML16237A133 |
| NUREG-1437, S57 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding LaSalle County Station, Units 1 and 2, Final Report | August 2016 | ML16238A029 |
| NUREG/CR-7224 | Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit | August 2016 | ML16237A100 |
| NUREG/IA-0470, V1 | International Agreement Report – Nuclear Regulatory Authority Experimental Program to Characterize and Understand High Energy Arcing Fault (HEAF) Phenomena | August 2016 | ML16235A163 |
| NUREG/IA-0471 | International Agreement Report – Fuel Rod Behavior and Uncertainty Analysis by FRAPTRAN/TRACE/DAKOTA Code in Maanshan LBLOCA | August 2016 | ML16229A182 |
| NUREG-2189 | Safety Evaluation Report – Related to SHINE Medical Technologies, Inc. Construction Permit Application for a Medical Radioisotope Production Facility Docket Number 50-608 | August 2016 | ML16229A140 |
| NUREG/KM-0010 | WASH-1400 – The Reactor Safety Study – The Introduction of Risk Assessment to the Regulation of Nuclear Reactors | August 2016 | ML16225A002 |
| NUREG-1885, R9 | Report to Congress on the Security Inspection Program for Commercial Power Reactors and Category I Fuel Cycle Facilities: Results and Status Update – Annual Report for Calendar Year 2015 | August 2016 | ML16211A029 |
| NUREG-1649, R6 | Reactor Oversight Process | August 2016 | ML16214A274 |
| NUREG/CR-7219, ANL-16/09 | Cladding Behavior during Postulated Loss-of-Coolant Accidents | July 2016 | ML16211A004 |
| NUREG/BR-0117, N16-03 | NMSS News Link Summer 2016 | July 2016 | ML16200A019 |
| NUREG/CR-7103, V3, PNNL-24647 | Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys: Stress Corrosion Cracking of Cold Worked Alloy 690 | July 2016 | ML16190A072 |
| NUREG/CR-7222 | Tsunami Hazard Assessment Based on Wave Generation, Propagation, and Inundation Modeling for the U.S. East Coast | July 2016 | ML16193A021 |
| NUREG-1556, V4, R1 | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Master Materials Licenses, Final Report | July 2016 | ML16188A048 |
| NUREG-1556, V12, R1, DFC | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Possession Licenses for Manufacturing and Distribution – Draft Report for Comment | June 2016 | ML16182A163 |
| NUREG-1556, V1, R2 | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Portable Gauge Licenses, Final Report | June 2016 | ML16175A375 |
| NUREG-1556, V10, R1 | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Master Materials Licenses, Final Report | June 2016 | ML16181A111 |
| NUREG-1556, V15, R1 | Consolidated Guidance About Materials Licenses: Guidance About Changes of Control and About Bankruptcy Involving Byproduct, Source, or Special Nuclear Materials Licenses, Final Report | June 2016 | ML16181A003 |
| NUREG-1910, S6, DFC | Environmental Impact Statement for the Reno Creek In Situ Recovery Project in Campbell County, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities, Draft Report for Comment | June 2016 | ML16181A082 |
| NUREG-1556, V19, R1 | Guidance for Agreement State Licensees About NRC Form 241 "Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore Waters" and Guidance for NRC Licensees Proposing to Work in Agreement State Jurisdiction (Reciprocity), Final Report | June 2016 | ML16175A107 |
| NUREG-1927, R1 | Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel Final Report | June 2016 | ML16179A148 |
| NUREG-2156 | The U.S. HRA Empirical Study Assessment of HRA Method Predictions against Operating Crew Performance on a U.S. Nuclear Power Plant Simulator | June 2016 | ML16179A124 |
| NUREG-1556, V16, R1, DFC | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Licenses Authorizing Distribution to General Licensees – Draft Report for Comment | June 2016 | ML16167A386 |
| NUREG/KM-0001, S1 | Three Mile Island Accident of 1979 Knowledge Management Digest – Recovery and Cleanup | June 2016 | ML16166A358 |
| NUREG/KM-0001, R1 | Three Mile Island Accident of 1979 Knowledge Management Digest – Overview | June 2016 | ML16166A337 |
| NUREG/BR-0099, R14 | U.S. Nuclear Regulatory Commission Overview | June 2016 | ML16165A342 |
| NUREG-1437, S48, FINAL ERRATA Sheet | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 48 Regarding South Texas Project, Units 1 and 2 Final Report ERRATA Sheet | June 2016 | ML16165A182 |
| NUREG/CR-7220 | SNAP/RADTRAD 4.0: Description of Models and Methods | June 2016 | ML16160A019 |
| NUREG-2195, DFC | Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treated Alloy 600 and 690 Steam Generator Tubes – Draft Report for Comment | May 2016 | ML16134A029 |
| NUREG/CR-4513, R2 | Estimation of Fracture Toughness of Cast Stainless Steels during Thermal Aging in LWR Systems | May 2016 | ML16145A082 |
| NUREG-0090, V38 | Report to Congress on Abnormal Occurrences Fiscal Year 2015 | May 2016 | ML16145A026 |
| NUREG-2182, V3 | Final Safety Evaluation Report for the Combined License for Enrico Fermi 3, Docket Number 52-033, DTE Electric Company, Appendices B to F | May 2016 | ML16141A038 |
| NUREG-2182, V2 | Final Safety Evaluation Report for the Combined License for Enrico Fermi 3, Docket Number 52-033, DTE Electric Company, Chapters 10 to 20, Appendix A | May 2016 | ML16140A095 |
| NUREG-2182, V1 | Final Safety Evaluation Report for the Combined License for Enrico Fermi 3, Docket Number 52-033, DTE Electric Company, Chapters 1 to 9 | May 2016 | ML16140A058 |
| NUREG-2196 | BWR ECCS Pump Suction Concerns following a LOCA | May 2016 | ML16141A097 |
| NUREG/IA-0467 | RELAP5 Analysis of Mitigation Strategy for Extended Blackout Power Condition in PWR | May 2016 | ML16138A055 |
| NUREG/CR-7155, SAND2012-10702P | State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station | May 2016 | ML16133A461 |
| NUREG/CR-7214 | Toward a More Risk-Informed and Performance-Based Framework for the Regulation of the Seismic Safety of Nuclear Power Plants | May 2016 | ML16126A008 |
| NUREG/CR-7200 | Influence of Coupling Erosion and Hydrology on the Long-Term Performance of Engineered Surface Barriers | May 2016 | ML16125A124 |
| NUREG-2184 | Supplement to the U.S. Department of Energy's Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada, Final Report | May 2016 | ML16125A032 |
| NUREG-1415, V29, N2 | Office of the Inspector General Semiannual Report to Congress October 1, 2015 – March 31, 2016 | April 2016 | ML16160A037 |
| NUREG/BR-0508, R1 | Reactor Oversight Process | April 2016 | ML16119A045 |
| NUREG/CP-0303, V5, EPRI 3002005205 | Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES) - 2012, Volume 5, Module 5: Advanced Fire Modeling | April 2016 | ML16117A511 |
| NUREG/CP-0303, V4, EPRI 3002005205 | Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES) - 2012, Volume 4, Module 4: Human Reliability Analysis (HRA) | April 2016 | ML16117A468 |
| NUREG/CP-0303, V3, EPRI 3002005205 | Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES) - 2012, Volume 3, Module 3: Fire Analysis | April 2016 | ML16117A280 |
| NUREG/CP-0303, V2, EPRI 3002005205 | Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES) - 2012, Volume 2, Module 2: Electrical Circuits | April 2016 | ML16117A161 |
| NUREG/CP-0303, V1, EPRI 3002005205 | Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES) - 2012, Volume 1, Module 1: Probabilistic Risk Analysis (PRA) | April 2016 | ML16117A096 |
| NUREG-2194, V2 | Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 1: Bases | April 2016 | ML16110A369 |
| NUREG-2194, V1 | Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 1: Specifications | April 2016 | ML16110A277 |
| NUREG-0713, V36 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2014: Forty-Seventh Annual Report | April 2016 | ML16112A230 |
| NUREG/CR-7216 | Spent Fuel Pool Project Phase II: Pre-Ignition and Ignition Testing of a 1x4 Commercial 17x17 Pressurized Water Reactor Spent Fuel Assemblies under Complete Loss of Coolant Accident Conditions | April 2016 | ML16112A084 |
| NUREG/CR-7215 | Spent Fuel Pool Project Phase 1: Pre-Ignition and Ignition Testing of a Single Commercial 17x17 Pressurized Water Reactor Spent Fuel Assembly under Complete Loss of Coolant Accident Conditions | April 2016 | ML16112A022 |
| NUREG-2178, V1, EPRI 3002005578 | Refining And Characterizing Heat Release Rates From Electrical Enclosures During Fire (RACHELLE-FIRE) Volume 1: Peak Heat Release Rates and Effect of Obstructed Plume | April 2016 | ML16110A140 |
| NUREG/CR-7197 | Heat Release Rates of Electrical Enclosure Fires (Helen-Fire), Final Report | April 2016 | ML16110A037 |
| NUREG-2179, V2 | Environmental Impact Statement for Combined License (COL) for Bell Bend Nuclear Power Plant, Final Report, Chapters 9 to 12, Appendices A to N | April 2016 | ML16111B193 |
| NUREG-2179, V1 | Environmental Impact Statement for Combined License (COL) for Bell Bend Nuclear Power Plant, Final Report, Chapters 1 to 8 | April 2016 | ML16111B169 |
| NUREG/CR-7213, ANL/EVS-15/10 | MILDOS-AREA Computation Verification Version 4 | April 2016 | ML16105A217 |
| NUREG/KM-0009 | Historical Review and Observations of Defense-in-Depth | April 2016 | ML16104A071 |
NUREG-2193,
S1 | Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station Docket Number 50-346 FirstEnergy Nuclear Operating Company, Supplement 1 | April 2016 | ML16104A350 |
NUREG-2193,
V2 | Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station Docket Number 50-346 FirstEnergy Nuclear Operating Company, Sections 4 to 6 Appendices | April 2016 | ML16104A301 |
NUREG-2193,
V1 | Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station Docket Number 50-346 FirstEnergy Nuclear Operating Company, Sections 1 to 3 | April 2016 | ML16104A207 |
| NUREG/CR-7212, ANL/EVS-15/9 | Technical Manual and User's Guide for MILDOS-AREA Version 4 | April 2016 | ML16103A316 |
| NUREG/BR-0117 N16-02 | NMSS New Link Spring 2016 | March 2016 | ML16091A236 |
| NUREG-2174 | Impact of Variation in Environmental Conditions on the Thermal Performance of Dry Storage Casks, Final Report | March 2016 | ML16081A181 |
| NUREG/IA-0465 | Fuel Rod Performance Uncertainty Analysis During Overpressurization Transient for Kuosheng Nuclear Power Plant with TRACE/ FRAPTRAN/ DAKOTA Codes in SNAP Interface | March 2016 | ML16076A077 |
| NUREG/IA-0464 | RELAP5/MOD3.3 Model Assessment and Hypothetical Accident Analysis of Kuosheng Nuclear Power Plant with SNAP Interface | March 2016 | ML16076A059 |
| NUREG/CR-7177, Errata, ERI/NRC 13-210 | Compendium of Analyses to Investigate Select Level 1 Probabilistic Risk Assessment End-State Definition and Success Criteria Modeling Issues | March 2016 | ML16077A102 |
| NUREG/CR-4251/PNL-5461, V2, P2 | Mitigative Techniques for Ground-Water Contamination Associated With Severe Nuclear Accidents, Case Study Analysis of Hydrologic Characterization and Mitigative Schemes | March 2016 | ML15278A116 |
| NUREG/CR-4251/PNL-5461, V2, P1 | Mitigative Techniques for Ground-Water Contamination Associated With Severe Nuclear Accidents, Case Study Analysis of Hydrologic Characterization and Mitigative Schemes | March 2016 | ML15278A117 |
| NUREG/CR-4251/PNL-5461, V1, P2 | Mitigative Techniques for Ground-Water Contamination Associated With Severe Nuclear Accidents, Anaylysis of Generic Site Conditions | March 2016 | ML15278A084 |
| NUREG/CR-4251/PNL-5461, V1, P1 | Mitigative Techniques for Ground-Water Contamination Associated With Severe Nuclear Accidents, Anaylysis of Generic Site Conditions | March 2016 | ML15278A083 |
| NUREG-1556, V2, R1 | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Industrial Radiography Licenses, Final Report | March 2016 | ML16062A091 |
| NUREG-2188 | U.S. Operating Experience with Thermally Treated Alloy 600 Steam Generator Tubes Through December 2013 | March 2016 | ML16061A159 |
| NUREG-1925, R3 | Research Activities FY 2015-FY 2017 | February 2016 | ML16060A414 |
| NUREG-1437, S57 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding LaSalle County Station, Units 1 and 2, Draft Report for Comment | February 2016 | ML16033A103 |
| NUREG-1100, V32 | Congressional Budget Justification: Fiscal Year 2017 | February 2016 | ML16036A086 |
| NUREG-1021, R11, DFC | Operator Licensing Examination Standards for Power Reactors, Draft Report for Comment | February 2016 | ML16028A409 |
| NUREG/BR-0128, R5 | A Guide to Open Commission Meetings February 2016 | February 2016 | ML16032A060 |
| NUREG/IA-0460 | Model 3D Cores for PWR Using Vessel Components in TRACEv5.OP3 | January 2016 | ML16032A231 |
| NUREG-2187, V2 | Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models—Byron Unit 1, Appendices D to G | January 2016 | ML16022A062 |
| NUREG-2187, V1 | Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models—Byron Unit 1, Chapters 1 to 8 - Appendices A to C | January 2016 | ML16021A423 |
| NUREG/CR-7209, PNNL-24792, DFC | A Compendium of Spent Fuel Transportation Package Response Analyses to Severe Fire Accident Scenarios, Draft Report for Comment | January 2016 | ML16015A016 |
| NUREG/BR-0117, N16-01 | NMSS Quarterly Newsletter Winter 2016 | January 2016 | ML16015A056 |
| NUREG-2114 | Cognitive Basis for Human Reliability Analysis | January 2016 | ML16014A045 |