| Documents added in 2014 |
| 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/IA-0216, V3 | International HRA Empirical Study – Phase 3 Report: Results from Comparing HRA Methods Predictions to HAMMLAB Simulator Data on LOFW Scenarios | Dec 2014 | ML14358A254 |
NUREG-1437
S54 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54, Regarding Byron Station Units 1 and 2 | Dec 2014 | ML14357A042 |
| NUREG/CR-7191 | Thermal Analysis of Horizontal Storage Casks for Extended Storage Applications | Dec 2014 | ML14352A098 |
| NUREG/KM-0008 | Reflections on Fukushima - NRC Senior Leadership Visit to Japan, 2014 | Dec 2014 | ML14353A089 |
| NUREG-1021, R10 | Operator Licensing Examination Standards for Power Reactors | Dec 2014 | ML14352A297 |
| NUREG-1949, V4 | Safety Evaluation Report Related to Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada, Volume 4: Administrative and Programmatic Requirements | Dec 2014 | ML14346A071 |
NUREG-1824
Supp1 DFC | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications | Dec 2014 | ML14338A237 |
NUREG-1650, Rev 5,
Supplement 1 | Answers to Questions from the Peer Review by Contracting Parties on the United States of America Sixth National Report for the Convention on Nuclear Safety | Dec 2014 | ML14337A015 |
| NUREG–2173 | Tribal Protocol Manual | Dec 2014 | ML14274A014 |
NUREG/CR-7187
PNNL-23659 | Managing PWSCC in Butt Welds by Mitigation and Inspection | Nov 2014 | ML14329A085 |
NUREG-1437 S50
Final Report | General Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 50 Regarding Grand Gulf Nuclear Station, Unit 1 Final Report | Nov 2014 | ML14328A171 |
| NUREG-2126 | Standard Review Plan for Conventional Uranium Mill and Heap Leach Facilities | Nov 2014 | ML14325A634 |
| NUREG/CR-7141 | The U.S. Nuclear Regulatory Commission's Cyber Security Regulatory Framework for Nuclear Power Reactors | Nov 2014 | ML14323A203 |
| NUREG-1542, V20 | Performance and Accountability Report – Fiscal Year 2014 | Nov 2014 | ML14322A246 |
| NUREG/IA-0417 | Post-Test Thermal-Hydraulic Analysis of PKL Tests F1.1 and F1.2 | Oct 2014 | ML14301A522 |
| NUREG/IA-0415 | TRACE (V 5.0 Patch 2) Validation Based on the RELAP5-Calculation of FIX-III LOCA Experiments NO 5052 4011 3051 | Oct 2014 | ML14303A184 |
NUREG/CR-7024
Rev. 1 | Material Property Correlations: Comparisons between FRAPCON-3.5, FRAPTRAN-1.5, and MATPRO | Oct 2014 | ML14296A063 |
NUREG/CR-7023
Vol. 2, Rev. 1 | FRAPTRAN-1.5: Integral Assessment | Oct 2014 | ML14295A633 |
NUREG/CR-7023
Vol. 1 Rev. 1 | FRAPTRAN-1.5: A Computer Code for the Transient Analysis of Oxide Fuel Rods | Oct 2014 | ML14295A596 |
NUREG/CR-7022
Vol. 2, Rev. 1 | FRAPCON-3.5: Integral Assessment | Oct 2014 | ML14295A559 |
NUREG/CR-7022
Vol. 1 Rev. 1 | FRAPCON-3.5: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup | Oct 2014 | ML14295A539 |
| NUREG-1437, S51 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Callaway Plant, Unit 1 (Final Report) | Oct 2014 | ML14289A140 |
| NUREG-1949, V3 | Safety Evaluation Report Related to Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada | Oct 2014 | ML14288A121 |
| NUREG/CR-7153, V5 | Expanded Materials Degradation Assessment (EMDA): Aging of Cables and Cable Systems | Oct 2014 | ML14279A461 |
| NUREG/CR-7153, V4 | Expanded Materials Degradation Assessment (EMDA): Aging of Concrete and Civil Structures | Oct 2014 | ML14279A430 |
| NUREG/CR-7153, V3 | Expanded Materials Degradation Assessment (EMDA): Aging of Reactor Pressure Vessels | Oct 2014 | ML14279A349 |
| NUREG/CR-7153, V2 | Expanded Materials Degradation Assessment (EMDA): Aging of Core Internals and Piping Systems | Oct 2014 | ML14279A331 |
| NUREG/CR-7153, V1 | Expanded Materials Degradation Assessment (EMDA): Executive Summary of EMDA Process and Results | Oct 2014 | ML14279A321 |
| NUREG-2171 | Safety Evaluation Report Related to the License Renewal of Limerick Generating Station, Units 1 and 2 | Sep 2014 | ML14276A156 |
| NUREG-2171 Supp 1 | Safety Evaluation Report Related to the License Renewal of Limerick Generating Station, Units 1 and 2 | Sep 2014 | ML14276A160 |
| NUREG/CR-7175 | Susceptibility of Nuclear Stations of External Faults | Sep 2014 | ML14269A261 |
NUREG-1022, Rev. 3
Supp 1 | Event Report Guidelines: 10 CFR 50.72(b)(3)(xiii) | Sep 2014 | ML14267A447 |
| NUREG-1966, S1 | Final Safety Evaluation Report: Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design, Supplement 1 | Sep 2014 | ML14265A084 |
| NUREG/CR-7186 | Experimental Measurement of Suppression Pool Void Distribution During Blowdown in Support of Generic Issue 193 | Sep 2014 | ML14255A123 |
| NUREG/BR-0464 R2 | Equal Employment Opportunity Advisory Committees | Sep 2014 | ML14252A164 |
| NUREG-2157 V2 | Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel: Final Report. | Sep 2014 | ML14196A107 |
| NUREG-2157 V1 | Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel: Final Report. | Sep 2014 | ML14196A105 |
| NUREG/CR-7009 | MACCS Best Practices as Applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project | Aug 2014 | ML14234A148 |
| NUREG/CR-7008 | MELCOR Best Practices as Applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project | Aug 2014 | ML14234A136 |
| NUREG-1614 V6 | USNRC Strategic Plan Fiscal Years 2014-2018 | Aug 2014 | ML14246A439 |
| NUREG/IA-0446 | Assessment of Channel Coolant Voiding in RD-14M Test Facility using TRACE | Aug 2014 | ML14233A430 |
| NUREG-2127 | The International HRA Empirical Study: Lessons Learned from Comparing HRA Methods Predictions to HAMMLAB Simulator Data | Aug 2014 | ML14227A197 |
NUREG-1910 S5
Errata No. 2 | Environmental Impact Statement for the Ross ISR Project in Crook County, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Final Report) | Aug 2014 | ML14226A701 |
| NUREG-1437 S53 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Sequoyah Nuclear Plant, Units 1 and 2 (Draft Report for Comment) | July 2014 | ML14211A454 |
| NUREG/IA-0449 | Post-Test Analysis of Upper Plenum 11% Break at PSB-VVER Facility using TRACE V5.0 and RELAP5/MOD3.3 Code | July 2014 | ML14213A344 |
| NUREG/IA-0448 | Uncertainty Analysis for Maanshan LBLOCA by TRACE and DAKOTA | July 2014 | ML14212A560 |
| NUREG/BR-0117 #14-03 | FSME NewsLink | July 2014 | ML14212A155 |
| NUREG/IA-0445 | The Establishment and Assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP Model | July 2014 | ML14211A160 |
| NUREG/IA-0447 | RELAP5/MOD3.3 Assessment by Comparison with PKL III G3.1 Experiment (small break in the main steam line) | July 2014 | ML14212A106 |
| NUREG/BR-0521 | Decommissioning Nuclear Power Plants | July 2014 | ML14210A472 |
NUREG/CR-7174 | Transfer Factors for Contaminant Uptake by Fruit and Nut Trees | July 2014 | ML14210A095 |
| NUREG/BR-0522 | Fire Protection Program for Operating Reactors | July 2014 | ML14209A040 |
| NUREG/CR-6918 R2 | VARSKIN 5: A Computer Code for Skin Contamination Dosimetry | July 2014 | ML14204A361 |
| NUREG/BR-0500 R2 | Safety Culture Policy Statement | June 2014 | ML14203A360 |
| NUREG/IA-0443 | Research Reactor ‘MARIA’ Primary Cooling Loop Transient Analysis Using RELAP5 Mod 3.3 | July 2014 | ML14195A106 |
| NUREG/IA-0402 | Implementation of the Control Rod Movement Option by means of Control Variables in RELAP5/PARCS v2.7 Coupled Code | July 2014 | ML14191A191 |
| NUREG-1885 R7 | 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 2013 | July 2014 | ML14184A646 |
| NUREG/CR-7183 | Best Practices for Behavioral Observation Programs at Operating Power Reactors and Power Reactor Construction Sites | June 2014 | ML14189A355 |
| NUREG/CR-7167 | Assessing the Potential for Biorestoration of Uranium In Situ Recovery Sites | June 2014 | ML14184B139 |
| NUREG/BR-0518 | No Undue Risk: Regulating the Safety of Operating Nuclear Power Plants | June 2014 | ML14181A493 |
| NUREG-1556 V18 R1 DFC | Consolidated Guidance about Materials Licenses Program Specific Guidance about Service Provider Licenses (Draft Report for Comment) | June 2014 | ML14171A526 |
| NUREG/CR-7169 | Sensors and Monitoring to Assess Grout and Vault Behavior for Performance Assessments | June 2014 | ML14164A267 |
| NUREG/BR-0520 | State Programs at the U.S. Nuclear Regulatory Commission | June 2014 | ML14155A318 |
| NUREG-1520 R1 DFC | Standard Review Plan for License Applications for Fuel Cycle Facilities (Draft Report for Comment) | May 2014 | ML14150A417 |
| NUREG-2166 | Physical Security Best Practices for the Protection of Risk-Significant Radioactive Material | May 2014 | ML14150A382 |
| NUREG-0090 V36 | Report to Congress on Abnormal Occurrences: Fiscal Year 2013 | May 2014 | ML14150A073 |
| NUREG/CR-7152 | Rod Bundle Heat Transfer Facility – Steady-State Steam Cooling Experiments | May 2014 | ML14149A137 |
| NUREG-1556 V14 R1 DFC | Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Well Logging, Tracer, and Field Flood Study Licenses (Draft Report for Comment) | May 2014 | ML14148A165 |
| NUREG/CR-7163 | A Formalized Approach for the Collection of HRA Data from Nuclear Power Plant Simulators | May 2014 | ML14148A128 |
| NUREG/CR-7177 | Compendium of Analyses to Investigate Select Level 1 Probabilistic Risk Assessment End-State Definition and Success Criteria Modeling Issues | May 2014 | ML14148A126 |
| NUREG/BR-0519 | U.S. Nuclear Regulatory (NRC) Nonproliferation Considerations in the Licensing of Enrichment and Reprocessing Facilities | May 2014 | ML14149A091 |
| NUREG/CR-7150 V2 | Joint Assessment of Cable Damage and Quantification of Effects from Fire (JACQUE-FIRE) | May 2014 | ML14141A129 |
| NUREG/KM-0007 | NRC Program on Knowledge Management for Liquid-Metal-Cooled Reactors | April 2014 | ML14128A346 |
| NUREG-0713 V34 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2012:Forty-Fifth Annual Report | April 2014 | ML14126A597 |
| NUREG/BR-0117 #14-02 | FSME NewsLink | April 2014 | ML14122A076 |
| NUREG/IA-0444 | Simulation of LSTF Hot Leg Break (OECD/NEA ROSA-2 Test 1) with TRACE Code: Application to a PWR NPP Model | April 2014 | ML14115A092 |
| NUREG-1022 Rev 3 Supp 1 DFC | Event Report Guidelines 10 CFR 50.72(b)(3)(xiii) (Draft Report for Comment) | April 2014 | ML14114A384 |
| NUREG-1910 S5 Errata | Environmental Impact Statement for the Ross ISR Project in Crook County, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Final Report) | April 2014 | ML14113A151 |
| NUREG-1556 V10 R1 DFC | Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Master Materials Licenses (Draft Report for Comment) | April 2014 | ML14105A093 |
| NUREG-1966 V 1 | Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design (Chapters 1 – 3) | April 2014 | ML14099A519 |
| NUREG-1966 V 2 | Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design (Chapters 4 – 8) | April 2014 | ML14099A522 |
| NUREG-1966 V 3 | Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design (Chapters 9 – 15) | April 2014 | ML14099A532 |
| NUREG-1966 V 4 | Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design (Chapters 16 – 24) | April 2014 | ML14100A187 |
| NUREG-1966 V 5 | Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design (Appendix A) | April 2014 | ML14100A190 |
| NUREG-1966 V 6 | Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design (Appendices B – F) | April 2014 | ML14100A194 |
| NUREG/BR-0007 R6 | Errata for “Instructions for the Preparation and Distribution of Material Status Reports (DOE/NRC Forms 742 and 742C) | April 2014 | ML14097A321 |
| NUREG-1542 V19 S1 | Fiscal Year 2013 Summary of Performance and Financial Information | March 2014 | ML14090A478 |
| NUREG/IA-0426 | Simulation of LSTF Upper Head Break (OECD/NEA ROSA Test 6.1) with TRACE Code. Application to a PWR NPP Model | March 2014 | ML14091A315 |
| NUREG-2162 | Weld Residual Stress Finite Element Analysis Validation: Part 1 – Data Development Effort | March 2014 | ML14087A118 |
| NUREG/CR-6909 R1 DFC | Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials (Draft for Comment) | March 2014 | ML14087A068 |
| NUREG-2165 | Safety Culture Common Language | March 2014 | ML14083A200 |
| NUREG-1556 V15 R1 DFC | Consolidated Guidance about Materials Licenses: Guidance about Changes of Control and about Bankruptcy Involving Byproduct, Source, or Special Nuclear Materials Licenses (Draft for Comment) | March 2014 | ML14078A110 |
| NUREG/IA-0438 | ATWS Analysis of Lungmen ABWR for MSIV Closure Transient | March 2014 | ML14073A124 |
| NUREG/IA-0439 | TRACE Analysis on Heat Removal Decrease Accidents for AP1000 | March 2014 | ML14073A128 |
| NUREG/IA-0440 | The Alternate Mitigation Strategies Study of Chinshan BWR/4 by Using the LOCA and SBO Analysis of TRACE | March 2014 | ML14073A132 |
| NUREG/IA-0442 | RELAP5/MOD3.3 Analysis of Steam Generator Tube Rupture (SGTR) Accident for NPP Krško | March 2014 | ML14073A134 |
| NUREG-1100 V30 | FY 2015 Congressional Budget Justification | March 2014 | ML14064A167 |
| NUREG/BR-0476 V3 | 2013 New Reactor Program | March 2014 | ML14055A176 |
| NUREG-1830 V10 | FY 2013 Office of Investigations Annual Report | Feb 2014 | ML14058A899 |
| NUREG-1910 S5 | Environmental Impact Statement for the Ross ISR Project in Crook County, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Final Report) | Feb 2014 | ML14056A096 |
| NUREG/IA-0436 | Assessment of LONF ATWS for Maanshan PWR Using TRACE Code | Feb 2014 | ML14056A027 |
| NUREG/IA-0437 | Sensitivity Study of the DEG LBLOCA Transient on the Counter-Current Flow Limitation by Using TRACE | Feb 2014 | ML14056A028 |
| NUREG-1649 R5 | Reactor Oversight Process | Feb 2014 | ML14052A306 |
| NUREG/CR-7170 | Assessment of Stress Corrosion Cracking Susceptibility for Austenitic Stainless Steels Exposed to Atmospheric Chloride and Non-Chloride Salts | Feb 2014 | ML14051A417 |
| NUREG/BR-0117 #14-01 | FSME NewsLink | Feb 2014 | ML14051A395 |
| NUREG/IA-0441 | Assessment Against ACHILLES Reflood Experiment with TRACE V5.0 Patch2 | Feb 2014 | ML14050A387 |
| NUREG/CR-7176 | Safety and Regulatory Issues of the Thorium Fuel Cycle | Feb 2014 | ML14050A083 |
| NUREG-1437 S52 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Davis-Besse Nuclear Power Station (Draft For Comment) | Feb 2014 | ML14050A290 |
| NUREG-1437 S51 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Callaway Plant, Unit 1 (Draft For Comment) | Feb 2014 | ML14041A373 |
| NUREG/KM-0002 R1 | The Browns Ferry Fire of 1975 Knowledge Management Digest | Feb 2014 | ML14038A115 |
| NUREG/KM-0005 | 2002 Davis-Besse Reactor Pressure Vessel Head Degradation Knowledge Management Digest | Feb 2014 | ML14038A119 |
| NUREG/KM-0003 | Fire Protection and Fire Research Knowledge Management Digest 2013 | Feb 2014 | ML14038A134 |
| NUREG-2125 | Spent Fuel Transportation Risk Assessment | Jan 2014 | ML14031A323 |
| NUREG/CR-7172 | Knowledge Base Report on Emergency Core Cooling Sump Performance in Operating Light Water Reactors | Jan 2014 | ML14031A075 |
| NUREG-1910 S4 V1 | Environmental Impact Statement for the Dewey-Burdock Project in Custer and Fall River Counties, South Dakota: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Chapters 1 to 5) | Jan 2014 | ML14024A477 |
| NUREG-1910 S4 V2 | Environmental Impact Statement for the Dewey-Burdock Project in Custer and Fall River Counties, South Dakota: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Chapters 6 to 11 and Appendices) | Jan 2014 | ML14024A478 |
| NUREG-1556 V7 R1 DFC | Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Academic, Research and Development, and Other Licenses of Limited Scope Including Electron Capture Devices and X-Ray Fluorescence Analyzers (Draft for Comment) | Jan 2104 | ML14015A110 |
| NUREG-1556 V11 R1 DFC | Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Licenses of Broad Scope (Draft for Comment) | Jan 2014 | ML14015A114 |