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Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2012
| Documents added in 2012 | |||
|---|---|---|---|
| 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-0500 R1 Print Friendly Version | Safety Culture Policy Statement | Dec 2012 | ML13016A158 |
| NUREG/BR-0500 R1 | Safety Culture Policy Statement | Dec 2012 | ML12355A122 |
| NUREG/BR-0359 R1 | Modeling Potential Reactor Accident Consequences | Dec 2012 | ML12347A049 |
| NUREG/BR-0117 #12-03 | FSME News Link | Dec 2012 | ML12346A265 |
| NUREG/BR-0506 | Long-Term Research Program | Dec 2012 | ML12346A114 |
| NUREG/KM-0001 | Three Mile Island Accident of 1979 Knowledge Management Digest | Dec 2012 | ML12340A344 |
| NUREG-1542 V18 | Performance and Accountability Report FY 2012 | Nov 2012 | ML12355A201 |
| NUREG/CR-7041 | SCALE/TRITON Primer: A Primer for Light Water Reactor Lattice Physics Calculations | Nov 2012 | ML12338A215 |
| NUREG/CR-7128 | Void Swelling and Microstructure of Austenitic Stainless Steels Irradiated in the BOR-60 Reactor | Nov 2012 | ML12334A279 |
| NUREG-1935 | State-of-the-Art Reactor Consequence Analyses (Final) | Nov 2012 | ML12332A053 (Package) |
| NUREG-1437 Supp 48 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding South Texas Project, Units 1 and 2 (Draft for Comment) | Nov 2012 | ML12324A049 |
| NUREG-0711 R3 | Human Factors Engineering Program Review Model | Nov 2012 | ML12324A013 |
| NUREG-1934 | Nuclear Power Plant Fire Modeling Analysis Guidelines (NPP FIRE MAG): Final Report | Nov 2012 | ML12314A165 |
| NUREG/CR-7148 | Confirmatory Battery Testing: The Use of Float Current Monitoring to Determine Battery State-of-Charge | Nov 2012 | ML12313A413 |
| NUREG-1910 S4 V1 DFC | 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 4 (Draft for Comment) | Nov 2012 | ML12312A039 |
| NUREG-1910 S4 V2 DFC | 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 - Chapter 5 and Appendices (Draft for Comment) | Nov 2012 | ML12312A040 |
| NUREG-1635 V10 | Review and Evaluation of the Nuclear Regulatory Commission Safety Research Program: A Report to the U.S. Nuclear Regulatory Commission | Oct 2012 | ML12311A417 |
| NUREG/CR-7134 | The Estimation of Very-Low Probability Hurricane Storm Surges for Design and Licensing of Nuclear Power Plants in Coastal Areas | Oct 2012 | ML12310A025 |
| NUREG/CR-7150 V1 | Joint Assessment of Cable Damage and Quantification of Effects from Fire (JACQUE-FIRE): Phenomena Identification and Ranking Table (PIRT) Exercise for Nuclear Power Plant Fire-Induced Electrical Circuit Failure | Oct 2012 | ML12313A105 |
| NUREG/IA-0408 | IJS Procedure for Converting Input Deck from RELAP5 to TRACE | Oct 2012 | ML12305A164 |
| NUREG/IA-0418 | Application of TRACE V5.0 P2 to Natural Circulation Reactor Safety Analysis | Oct 2012 | ML12299A096 |
| NUREG-2152 DFC | Computational Fluid Dynamics Best Practice Guidelines for Dry Cask Applications (Draft For Comment) | Oct 2012 | ML12286A301 |
| NUREG/IA-0419 | Analysis with TRACE Code of ROSA Test 1.1: ECCS Water Injection Under Natural Circulation Condition | Oct 2012 | ML12283A191 |
| NUREG/BR-0362 | Protection of Safeguards Information: Requirements for Tribes Participating in the Advance Notification of Irradiated Reactor Fuel Shipments | Oct 2012 | ML12283A116 |
| NUREG/IA-0404 | The Development and Assessment of TRACE Model for Maanshan Nuclear Power Plant LOCA | Sept 2012 | ML12278A127 |
| NUREG-2124 V1 | Final Safety Evaluation Report Related to the Combined Licenses for Vogtle Electric Generating Plant, Units 3 and 4 | Sept 2012 | ML12271A045 |
| NUREG-2124 V2 | Final Safety Evaluation Report Related to the Combined Licenses for Vogtle Electric Generating Plant, Units 3 and 4 | Sept 2012 | ML12271A048 |
| NUREG-2124 V3 | Final Safety Evaluation Report Related to the Combined Licenses for Vogtle Electric Generating Plant, Units 3 and 4 | Sept 2012 | ML12271A049 |
| NUREG-1307 R15 DFC | Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities (Draft for Comment) | Sept 2012 | ML12257A191 |
| NUREG-1885 R5 | 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 2011 | Sept 2012 | ML12251A017 |
| NUREG-1350 V24 | Information Digest 2012-2013 | Aug 2012 | ML12241A166 |
| NUREG/CR-7142 | Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation | Aug 2012 | ML12241A160 |
| NUREG-1911 R4 | NRC Periodic Compliance Monitoring Report for U.S. Department of Energy Non-High-Level Waste Disposal Actions: Annual Report for Calendar Year 2011 | Aug 2012 | ML12234A576 |
| NUREG/CR-7139 | Assessment of Current Test Methods for Post-LOCA Cladding Behavior | Aug 2012 | ML12226A182 |
| NUREG-2113 | Environmental Impact Statement for the Proposed Fluorine Extraction Process and Depleted Uranium Deconversion Plant in Lea County, New Mexico (Final Report) | Aug 2012 | ML12220A380 |
| NUREG-1650 R4 | The United States of America National Report for the 2012 Convention on Nuclear Safety Extraordinary Meeting | July 2012 | ML12221A013 |
| NUREG-2118 V1 | Occupational Radiation Exposure at Agreement State-Licensed Materials Facilities, 1997-2010 | July 2012 | ML12220A081 |
| NUREG-1921 | EPRI/NRC-RES Fire Human Reliability Analysis Guidelines (Final Report) | July 2012 | ML12216A104 |
| NUREG/CR-7010 V1 | Cable Heat Release, Ignition, and Spread in Tray Installations During Fire (CHRISTIFIRE) Phase 1: Horizontal Trays (Final Report) | July 2012 | ML12213A056 |
| NUREG/BR-0117 #12-02 | FSME Newsletter | July 2012 | ML12213A049 |
| NUREG/CR-7107 | Validation of SCALE for High Temperature Gas-Cooled Reactor Analysis | July 2012 | ML12201A080 |
| NUREG/CR-7123 | A Literature Review of the Effects of Smoke from a Fire on Electrical Equipment | July 2012 | ML12185A086 |
| NUREG/BR-0164 R9 | NRC: Independent Regulator of Nuclear Safety | June 2012 | ML12335A261 |
| NUREG/CR-7137 | Stress Corrosion Cracking in Nickel-Base Alloys 690 and 152 Weld in Simulated PWR Environment - 2009 | June 2012 | ML12199A415 |
| NUREG/CR-6963 | An Assessment of PWR Steam Generator Condensation at the Oregon State University APEX Facility | June 2012 | ML12198A021 |
| NUREG/CR-7106 | Generation of a Broad-Group HTGR Library for Use with SCALE | June 2012 | ML12184A002 |
| NUREG/CR-7126 | Human-Performance Issues Related to the Design and Operation of Small Modular Reactors | June 2012 | ML12179A170 |
| NUREG-1437 S38 V4 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3 (Draft for Comment) | June 2012 | ML12174A244 |
| NUREG-2128 DFC | Electrical Cable Test Results and Analysis During Fire Exposure (ELECTRA-FIRE) Draft for Comment | June 2012 | ML12166A028 |
| NUREG/CR-7117 | Secure Network Design | June 2012 | ML12163A047 |
| NUREG/CR-7136 | Assessment of NDE Methods on Inspection of HDPE Butt Fusion Piping Joints for Lack of Fusion | May 2012 | ML12153A005 |
| NUREG-0713 V32 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2010: Forty-Third Annual Report | May 2012 | ML12153A003 |
| NUREG/BR-0240 R6 | Reporting Safety Concerns to the NRC | May 2012 | ML12146A003 |
| NUREG/BR-0240 R6 (Spanish Version) | Reportar Las Preocupaciones De Seguridad A La NRC (Reporting Safety Concerns to the NRC) | May 2012 | ML12146A004 |
| NUREG-2116 | Safety Evaluation Report for the International Isotopes Fluorine Products, Inc. Fluorine Extraction Process and Depleted Uranium Deconversion Plant in Lea County, New Mexico | May 2012 | ML12145A504 |
| NUREG-2110 | xLPR Pilot Study Report | May 2012 | ML12145A470 |
| NUREG/IA-0416 | Implementation of Advanced Multigroup Nodal and Pin Power Reconstruction Methods into PARCS 3.1 | May 2012 | ML12144A061 |
| NUREG-0090 V34 | Report to Congress on Abnormal Occurrences Fiscal Year 2011 | May 2012 | ML12142A194 |
| NUREG-2123 V1 | Safety Evaluation Report Related to the License Renewal of Columbia Generating Station | May 2012 | ML12139A300 |
| NUREG-2123 V2 | Safety Evaluation Report Related to the License Renewal of Columbia Generating Station | May 2012 | ML12139A302 |
| NUREG-1556 V1 R2 DFC | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Portable Gauge Licenses (Draft for Comment) | May 2012 | ML12139A008 |
| NUREG-2125 DFC | Spent Fuel Transportation Risk Assessment | May 2012 | ML12125A218 |
| NUREG/CR-6980 | RBHT Reflood Heat Transfer Experiments Data and Analysis | April 2012 | ML12128A368 |
| NUREG/IA-0407 | Proposal for the Development and Implementation of an Uncertainty and Sensitivity Analysis Module in SNAP | April 2012 | ML12123A177 |
| NUREG/IA-0414 | Comparison of the U.S. NRC PARCS Core Neutronics Simulator Against In-Core Detector Measurements for LWR Applications | April 2012 | ML12122A933 |
| NUREG/CR-7100 | Direct Current Electrical Shorting in Response to Exposure Fire (DESIREE-Fire):Test Results | April 2012 | ML12116A174 |
| NUREG-2117 R1 | Practical Implementation Guidelines for SSHAC Level 3 and 4 Hazard Studies | April 2012 | ML12118A445 |
| NUREG/CR-7108 | An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Isotopic Composition Predictions | April 2012 | ML12116A124 |
| NUREG/CR-7109 | An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Criticality (Keff) Predictions | April 2012 | ML12116A128 |
| NUREG-1941 V1 | Environmental Impact Statement for Combined Licenses (COLs) for Levy Nuclear Plant Units 1 and 2 (Chapters 1 to 5) | April 2012 | ML12100A063 |
| NUREG-1941 V2 | Environmental Impact Statement for Combined Licenses (COLs) for Levy Nuclear Plant Units 1 and 2 (Chapters 6 to 10) | April 2012 | ML12100A068 |
| NUREG-1941 V3 | Environmental Impact Statement for Combined Licenses (COLs) for Levy Nuclear Plant Units 1 and 2 (Chapters 6 to 10) | April 2012 | ML12100A070 |
| NUREG/CR-7103 V2 | Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys | April 2012 | ML12114A011 |
| NUREG/CR-7115 | Performance of Metal and Polymeric O-Ring Seals in Beyond-Design-Basis Temperature Excursions | April 2012 | ML12110A066 |
| NUREG-2150 | A Proposed Management Regulatory Framework | April 2012 | ML12109A277 |
| NUREG/BR-0117 #12-01 | FSME Newsletter | April 2012 | ML12104A251 |
| NUREG-1430 V1 R4 | Standard Technical Specifications: Babcock and Wilcox Plants- Specifications | April 2012 | ML12100A177 |
| NUREG-1430 V2 R4 | Standard Technical Specifications: Babcock and Wilcox Plants- Bases | April 2012 | ML12100A178 |
| NUREG-1431 V1 R4 | Standard Technical Specifications: Westinghouse Plants- Specifications | April 2012 | ML12100A222 |
| NUREG-1431 V2 R4 | Standard Technical Specifications: Westinghouse Plants- Bases | April 2012 | ML12100A228 |
| NUREG-1432 V1 R4 | Standard Technical Specifications: Combustion Engineering Plants- Specifications | April 2012 | ML12102A165 |
| NUREG-1432 V2 R4 | Standard Technical Specifications: Combustion Engineering Plants- Bases | April 2012 | ML12102A169 |
| NUREG-1433 V1 R4 | Standard Technical Specifications: General Electric BWR/4 Plants- Specifications | April 2012 | ML12104A192 |
| NUREG-1433 V2 R4 | Standard Technical Specifications: General Electric BWR/4 Plants- Bases | April 2012 | ML12104A193 |
| NUREG-1434 V1 R4 | Standard Technical Specifications: General Electric BWR/6 Plants- Specifications | April 2012 | ML12104A195 |
| NUREG-1434 V2 R4 | Standard Technical Specifications: General Electric BWR/6 Plants- Bases | April 2012 | ML12104A196 |
| NUREG/CR-7124 | Validation of LAPUR 6.0 Code | March 2012 | ML12104A126 |
| NUREG/CR-7047 | LAPUR 6.0 Benchmark Against Data from the GENESIS Facility | March 2012 | ML12104A121 |
| NUREG-1437 S47 V1 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Columbia Generating Station (Main Report) | March 2012 | ML12096A334 |
| NUREG-1437 S47 V2 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Columbia Generating Station (Appendices) | March 2012 | ML12096A336 (Package) |
| NUREG/CR-7120 | Radionuclide Behavior in Soils and Soil-to-Plant Concentration Ratios for Assessing Food Chain Pathways | March 2012 | ML12104A017 |
| NUREG-2121 | Fuel Fragmentation, Relocation, and Dispersal During the Loss-of-Coolant Accident | March 2012 | ML12090A018 |
| NUREG/IA-0412 | Assessment of TRACE 5.0 Against ROSA Test 3-2, High Power Natural Circulation | March 2012 | ML12087A002 |
| NUREG/IA-0413 | Assessment of TRACE 5.0 Against ROSA Test 3-1, Cold Leg SBLOCA | Feb 2012 | ML12087A003 |
| NUREG/CR-7122 | An Evaluation of Ultrasonic Phased Array Testing for Cast Austenitic Stainless Steel Pressurizer Surge Line Piping Welds | Feb 2012 | ML12087A004 (Package) |
| NUREG/IA-0409 | Post-Test Calculation of the ROSA/LSTF Test 3-1 Using RELAP5/Mod 3.3 | Feb 2012 | ML12083A011 |
| NUREG/IA-0410 | Post-Test Calculation of the ROSA/LSTF Test 3-2 Using RELAP5/Mod 3.3 | Feb 2012 | ML12083A012 |
| NUREG-2117 | Practical Implementation Guidelines for SSHAC Level 3 and 4 Hazard Studies | Feb 2012 | ML12073A311 |
| NUREG/BR-0240 R5 | Reporting Safety Concerns to the NRC | Feb 2012 | ML12073A150 |
| NUREG/BR-0240 R5 (Spanish Version) | Reportar Las Preocupaciones De Seguridad A La NRC (Reporting Safety Concerns to the NRC) | Feb 2012 | ML12073A086 |
| NUREG/CR-7016 | Human Reliability Analysis- Informed Insights on Cask Drops | Feb 2012 | ML12067A135 |
| NUREG/CR-7017 | Preliminary, Qualitative Human Reliability Analysis for Spent Fuel Handling | Feb 2012 | ML12067A137 |
| NUREG-2120 | Safety Evaluation Report for the General Electric-Hitachi Global Laser Enrichment LLC Laser-Based Uranium Enrichment Plant in Wilmington, North Carolina | Feb 2012 | ML12060A007 |
| NUREG-1830 V8 | Office of Investigations FY-2011 Annual Report | Feb 2012 | ML12049A001 |
| NUREG-1757 V3 R1 | Consolidated Decommissioning Guidance: Financial Assurance, Recordkeeping, and Timeliness | Feb 2012 | ML12048A683 |
| NUREG-1938 V1 | Environmental Impact Statement for the Proposed GE-Hitachi Global Laser Enrichment, LLC Facility in Wilmington, North Carolina (Final Report) | Feb 2012 | ML12047A040 |
| NUREG-1938 V2 | Environmental Impact Statement for the Proposed GE-Hitachi Global Laser Enrichment, LLC Facility in Wilmington, North Carolina (Appendices) | Feb 2012 | ML12047A042 |
| NUREG-2119 | Mechanical Behavior of Ballooned and Ruptured Cladding | Jan 2012 | ML12048A475 |
| NUREG/IA-0401 | Assessment of Two-Phase Critical Flow Models Performance in RELAP5 and TRACE Against Marviken Critical Flow Tests | Jan 2012 | ML12047A136 |
| NUREG/IA-0411 | Simulation of the Experimental Series F2.2 at PKL Facility Using RELAP5/Mod 3.3 | Jan 2012 | ML12047A141 |
| NUREG-1911 R3 | NRC Periodic Compliance Monitoring Report for U.S. Department of Energy Non-High-Level-Waste Disposal Actions | Jan 2012 | ML111890412 |
| NUREG-2115 V1 to V6 | Central and Eastern United States Seismic Source Characterization for Nuclear Facilities | Jan 2012 | ML12048A776 (Package) |
| NUREG/CR-7111 | A Summary of Aging Effects and Their Management in Reactor Spent Fuel Pools, Refueling Cavities, Tori, and Safety-Related Concrete Structures | Jan 2012 | ML12047A184 |
| NUREG/BR-0359 | Modeling Potential Reactor Accident Consequences | Jan 2012 | ML12026A470 |
| NUREG-1935 DFC | State-of-the-Art Reactor Consequence Analyses (SOARCA) Report (Draft for Comment) | Jan 2012 | ML120250406 |
| NUREG/CR-7110 V1 | State-of-the-Art Reactor Consequence Analyses Project: Peach Bottom Integrated Analysis | Jan 2012 | ML120260675 |
| NUREG/CR-7110 V2 | State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis | Jan 2012 | ML120260681 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026