Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2014

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

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