The NRC is modernizing nrc.gov with an updated design and improved navigation to enhance usability. We are committed to a smooth transition and will work to minimize any disruption. The site may be briefly unavailable at times during launch. Thank you for your patience.
Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2016
| 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 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026