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Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2007
| Documents added in 2007 | |||
|---|---|---|---|
| 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-0338 | Capture of E-Mail Records | Dec 2007 | ML11119A001 |
| NUREG/CR-6951 | Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit | Dec 2007 | ML080701107 |
| NUREG-1860 V1 | Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing – Main Report | Dec 2007 | ML080440170 |
| NUREG-1860 V2 | Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing – Appendices A-L | Dec 2007 | ML080440215 |
| NUREG/CR-6953 V1 | Review of NUREG-0654, Supplement 3, “Criteria for Protective Action Recommendations for Severe Accidents” | Dec 2007 | ML080360602 |
| NUREG/CR-6949 | The Employment of Empirical Data and Bayesian Methods in Human Reliability Analysis: A Feasibility Study | Dec 2007 | ML080230610 |
| NUREG-0713 V28 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2006 - 39th Annual Report | Dec 2007 | ML080100423 |
| NUREG-1873 | Environmental Impact Statement (EIS) for the License Renewal of the National Bureau of Standards Reactor (Final Report) | Dec 2007 | ML073620086 |
| NUREG-1437 S33 DFC | Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Shearon Harris Nuclear Power Plant, Unit 1 (Draft for Comment) | Dec 2007 | ML073320364 |
| NUREG-1574 R2 | Standard Review Plan on Transfer and Amendment of Antitrust License Conditions and Antitrust Enforcement | Dec 2007 | ML073410572 |
| NUREG-1542 V13 | Performance and Accountability Report FY 2007 | Nov 2007 | ML080100199 |
| NUREG-1855 DFC | Guidance on the Treatment of Uncertainties Associated with PRA’s in Risk-Informed Decision Making (Draft For Comment) | Nov 2007 | ML080040199 |
| NUREG/CR-6903 V2 | Human Event Repository and Analysis (HERA): The HERA Coding Manual and Quality Assurance | Nov 2007 | ML073470315 |
| NUREG/CR-6948 V1 | Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites: Logic, Strategic Approach and Discussion | Nov 2007 | ML073310297 |
| NUREG/CR-6948 V2 | Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites: Case Study Applications | Nov 2007 | ML073320395 |
| NUREG-1891 | Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station | Nov 2007 | ML073241016 |
| NUREG-1556 V13 R1 | Consolidated Guidance About Material Licenses: Program-Specific Guidance About Commercial Radiopharmacy Licenses (Final Report) | Nov 2007 | ML073180179 |
| NUREG/CR-6943 | A Study of Remote Visual Methods to Detect Cracking in Reactor Components | Oct 2007 | ML073110060 |
| NUREG/CR-6942 | Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments | Oct 2007 | ML073030092 |
| NUREG-1021 R1 S1 | Operator Licensing Examination Standards for Power Reactors -- Final Report | Oct 2007 | ML072970315 |
| NUREG-1122 R2 S1 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors – Final Report | Oct 2007 | ML072970334 |
| NUREG-1123 R2 S1 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors – Final Report | Oct 2007 | ML072970322 |
| NUREG/BR-0238 R15 | Materials Annual Fee Billing Handbook | Oct 2007 | ML072690040 |
| NUREG-1556 V21 | Consolidated Guidance About Material Licenses: Program-Specific Guidance About Possession Licenses for Production of Radioactive Material Using an Accelerator | Oct 2007 | ML072900058 |
| NUREG-1852 | Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire | Oct 2007 | ML073020676 |
| NUREG/IA-0215 | Spatial Effects and Uncertainty Analysis for Rod Ejection Accidents in a PWR | Sept 2007 | ML073380691 |
| NUREG-1650 R2 | The United States of America Fourth National Report for the Convention on Nuclear Safety | Sept 2007 | ML073110536 |
| NUREG-1889 | RASCAL 3.0.5 Workbook | Sept 2007 | ML072970068 |
| NUREG/CR-6268 R1 | Common-Cause Failure Database ad Analysis System: Event Data Collection, Classification, and Coding | Sept 2007 | ML072970404 |
| NUREG/BR-0050 R5 | ACNW & M FY2007 – FY2008 Action Plan | Sept 2007 | ML072850216 |
| NUREG-1885 | Report to Congress on the Security Inspection Program for Commercial Power Reactor and Category 1 Fuel Cycle Facilities: Results and Status Update | Sept 2007 | ML072640242 |
| NUREG-1888 DFC | Generic Environmental Impact Statement for the Reclamation of the Sequoyah Fuels Corporation Site in Gore, Oklahoma (Draft for Comment) | Sept 2007 | ML072570039 |
| NUREG-1764 R1 | Guidance for the Review of Changes to Human Actions | Sept 2007 | ML072640413 |
| NUREG-1437 S32 DFC | Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Wolf Creek Generating Station (Draft for Comment) | Sept 2007 | ML072540026 |
| NUREG-1872 V1 DFC | Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site -- Main Report (Draft for Comment) | Sept 2007 | ML072410045 |
| NUREG-1872 V2 DFC | Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site – Appendices (Draft for Comment) | Sept 2007 | ML072410049 |
| NUREG/CR-4667 V36 w/Errata | Environmentally Assisted Cracking in Light Water Reactors – Annual Report 2005 (Errata issued for pages 45 and 48 has been incorporated into document) | Aug 2007 | ML073120263 |
| NUREG-1350 V19 | USNRC Information Digest 2007-2008 | Aug 2007 | ML072960367 |
| NUREG/CR-6941 | Soil-to-Plant Concentration Ratios for Assessing Food Chain Pathways in Biosphere Models | Aug 2007 | ML072780220 |
| NUREG-1806 V1 | Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50,61) - Main Report | Aug 2007 | ML072830074 (Package) |
| NUREG-1806 V2 | Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50,61) - Appendices | Aug 2007 | ML072820691 |
| NUREG-1795 | FAVOR Code Versions 2.3 and 3.1 Verification and Validation Summary Report | Aug 2007 | ML072820045 |
| NUREG/CR-6954 | Fracture Analysis of Vessels – Oak Ridge FAVOR, v04.1, Computer Code User’s Guide | Aug 2007 | ML072840547 |
| NUREG/CR-6955 | Fracture Analysis of Vessels – Oak Ridge FAVOR, v04.1, Computer Code User’s Guide | Aug 2007 | ML072760089 |
| NUREG/CP-0152 V6 | Proceedings of the Ninth NRC/ASME Symposium on Valves, Pumps and Inservice Testing – July 17-19, 2006 | Aug 2007 | ML072700042 |
| NUREG-1887 | RASCAL 3.0.5: Description of Models and Methods | Aug 2007 | ML072480633 |
| NUREG-1854 | NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations - Draft Final Report for Interim Use | Aug 2007 | ML072360184 |
| NUREG-1841 | U.S. Operating Experience with Thermally Treated Alloy 690 Steam Generator Tubes | Aug 2007 | ML072330588 |
| NUREG-0933 S31 | A Prioritization of Generic Safety Issues | July 2007 | ML080710250 |
| NUREG-0936 V26 N1 | NRC Regulatory Agenda Semiannual Report Jan - June 2007 | July 2007 | ML072360180 |
| NUREG/BR-0117 #07-02 | NMSS Licensee Newsletter | July 2007 | ML072330088 |
| NUREG/CR-6940 | Combined Estimation of Hydrogeologic Conceptual Model, Parameter, and Scenario Uncertainty with Applications to Uranium Transport at the Hanford Site 300 Area | July 2007 | ML072330538 |
| NUREG/CR-6939 | Consistence Assessment of Industrial Wireless Protocols in the Nuclear Facility Environment | July 2007 | ML072210179 |
| NUREG-1437 S30 V1 | Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Vermont Yankee Nuclear Power Station - Main Report | July 2007 | ML072050012 |
| NUREG-1437 S30 V2 | Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Vermont Yankee Nuclear Power Station - Appendices | July 20007 | ML072050013 |
| NUREG-1437 S29 V1 | Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Pilgrim Nuclear Plant Station - Main Report | July 2007 | ML071990020 |
| NUREG-1437 S29 V2 | Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Pilgrim Nuclear Plant Station - Appendices | July 20007 | ML071990027 |
| NUREG-1556 V9 R2 DFC | Consolidated Guidance About Material Licenses: Program-Specific Guidance About Medical Use Licenses (Draft For Comment) | July 2007 | ML071860070 |
| NUREG-1125 V28 | A Compilation of Reports of The Advisory Committee on Reactor Safeguards: 2006 Annual | June 2007 | ML072210749 |
| NUREG/CR-6938 | Assessment of Potential Phosphate Ion-Cementitious Materials Interactions - Final Report | June 2007 | ML072200039 |
| NUREG/CR-6932 | Baseline Risk Index Initiating Events (BRIIE) | June 2007 | ML072080252 |
| NUREG-1880 | ATHEANA User's Guide | June 2007 | ML072130359 |
| NUREG-1807 | Probabilistic Fracture Mechanics - Models, Parameters, and Uncertainty Treatment Used in FAVOR Version 04.1 | June 2007 | ML072010411 |
| NUREG-1478 R2 | Operator Licensing Examiner Standards for Research and Test Reactors | June 2007 | ML072000059 |
| NUREG/IA-0206 | Simulation of the Propagation of Pressure Waves in Piping Systems with RELAP/MOD 3.2.2 Comparison of Computed and Measured Results | June 2007 | ML071930551 |
| NUREG-1873 DFC | Draft Environmental Impact Statement (DEIS) for the License Renewal of the National Bureau of Standards Reactor (Draft for Comment) | June 2007 | ML072140496 |
| NUREG-1556 V13 R1 DFC | Consolidated Guidance About Material Licenses: Program-Specific Guidance About Commercial Radiopharmacy Licenses (Draft For Comment) | June 2007 | ML071581047 |
| NUREG-1437 S31 DFC | Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding James A. FitzPatrick Nuclear Power Plant (Draft for Comment) | June 2007 | ML071420019 |
| NUREG/BR-0333 | Know Your EEO Rights | May 2007 | ML102700488 |
| NUREG/IA-0210 | In-Tube Steam Condensation In The Presence of Air Under Transient Conditions | May 2007 | ML072070054 |
| NUREG-1824 V1 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications: Main Report | May 2007 | ML071650546 |
| NUREG-1824 V2 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications: Experimental Uncertainty | May 2007 | ML071730305 |
| NUREG-1824 V3 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications: Fire Dynamic Tools | May 2007 | ML071730493 |
| NUREG-1824 V4 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications: Fire Induced Vulnerability | May 2007 | ML071730499 |
| NUREG-1824 V5 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications: Consolidated Fire Growth...... | May 2007 | ML071730527 |
| NUREG-1824 V6 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications: MAGIC | May 2007 | ML071730504 |
| NUREG-1824 V7 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications: Fire Dynamic Simulator | May 2007 | ML071730543 |
| NUREG/CR-6934 | Fatigue Crack Flaw Tolerance in Nuclear Power Plant Piping | May 2007 | ML071760205 |
| NUREG-1021 R9 S1 DFC | Operator Licensing Examination Standards for Power Reactors (Draft For Comment) | May 2007 | ML071580694 |
| NUREG-1122 R2 S1 DFC | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors (Draft for Comment) | May 2007 | ML071580631 |
| NUREG-1123 R2 S1 DFC | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (Draft for Comment) | May 2007 | ML071580691 |
| NUREG-1556 V21 DFC | Consolidated Guidance About Material Licenses: Program-Specific Guidance About Possession Licenses for Production of Radioactive Materials Using An Accelerator (Draft For Comment) | May 2007 | ML071500523 |
| NUREG/CR-6936 | Probabilities of Failure and Uncertainty Estimate Information for Passive Components - A Literature Review | May 2007 | ML071430371 |
| NUREG/CR-6935 | Sensitivity Studies of Failure of Steam Generator Tubes During Main Steam Line Break and Other Secondary Side Depressurization Events | May 2007 | ML071430396 |
| NUREG-1875 V1 | Safety Evaluation Report Relating to the License Renewal of Oyster Creek Generating Station | April 2007 | ML071290023 |
| NUREG-1875 V2 | Safety Evaluation Report Relating to the License Renewal of Oyster Creek Generating Station | April 2007 | ML071310246 |
| NUREG/IA-0204 | OLKILUOTO 2 - RELAP5//MOD 3.2.1.2: Analysis of the Reactor Scram on June 13, 1997 | April 2007 | ML071290556 |
| NUREG-0090 V29 | Report to Congress on Abnormal Occurrences - Fiscal Year 2006 | April 2007 | ML071080195 |
| NUREG-1864 | A Probabilistic Risk Assessment of a Dry Cask Storage System at a Nuclear Power Plant | March 2007 | ML071340012 |
| NUREG/CR-6933 | Assessment of Crack Detection in Heavy-Walled Cast Stainless Steel Piping Welds Using Advanced Low-Frequency Ultrasonic Methods | March 2007 | ML071020409 (Package) |
| NUREG/CR-6924 | Non-Destructive and Failure Evaluation of Tubing Steam Generator | March 2007 | ML070950140 |
| NUREG/BR-0164 R5 | NRC - Regulators of Nuclear Safety | March 2007 | ML071020089 |
| NUREG/CR-6930 | Temperature Dependence of Weibull Stress Parameters: Studies Using the Euro-Material Similar to ASME A508 Class-3 Steel | March 2007 | ML070810521 |
| NUREG/CR-6917 | Experimental Measurement of Pressure Drop Across Sump Screen Debris Beds in Support of GSI-191 | Feb 2007 | ML071910178 (Package) |
| NUREG-1862 | Development of a Pressure Drop Calculation Method for Debris-Covered Sump Screens in Support of Generic safety issue 191 | Feb 2007 | ML071520440 |
| NUREG/CR-6927 | Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors | Feb 2007 | ML070850183 |
| NUREG/CR-4461 R2 | Tornado Climatology of the Contiguous United States | Feb 2007 | ML070810400 |
| NUREG-1574 R2 DFC | Standard review Plan on Transfer and Amendment of Antitrust License Condition and Antitrust Enforcement | Feb 2007 | ML070160586 |
| NUREG-0936 V25 N2 | NRC Regulatory Agenda Semiannual Report July - December 2006 | Feb 2007 | ML070740647 |
| NUREG/BR-0007 R6 DFC | Instruction for the Preparation and Distribution of Material Status Reports (DOE/NRC Forms 742 and 742C) | Feb 2007 | ML070750363 |
| NUREG/BR-0006 R7 DFC | Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC Forms 741 and 740M | Feb 2007 | ML070750371 |
| NUREG/CR-6929 | Assessments of Eddy Currents Testing for the Detection of Cracks in Cast Stainless Steel Reactor Piping Components | Feb 2007 | ML070670477 |
| NUREG/CR-6923 | Expert Panel Report on Proactive Materials Degradation Assessments | Feb 2007 | ML070710255 (Package) |
| NUREG/CR-6923 | Expert Panel Report on Proactive Materials Degradation Assessments; Appendices D, E, and F | Feb 2007 | ML070930117 (Package) |
| NUREG/CR-6909 | Effects of LWR Coolant Environments on the Fatigue Life of Reactor Materials - Final Report | Feb 2007 | ML070660620 |
| NUREG/BR-0099 R12 | The United States Nuclear Regulatory Commission | Feb 2007 | ML070460435 |
| NUREG-1830 V3 | Office of Investigations Annual Report FY2006 | Feb 2007 | ML070460329 |
| NUREG/BR-0332 | U.S. Nuclear Regulatory Commission Training and Development Strategic Plan: Safety Through Knowledge | Feb 2007 | ML070370271 |
| NUREG-1814 R1 | Status of the Decommissioning Program - 2006 Annual Report | Feb 2007 | ML070600680 |
| NUREG/CR-6925 | Assessment of Analysis Methods for Seismic Shear Wall Capacity Using JNES/NUPEC Multi-Axial Cyclic and Shaking Table Test Data | Jan 2007 | ML071900254 |
| NUREG/CR-6922 | P-CARES: Probabilistic Computer Analysis for Rapid Evaluation of Structures | Jan 2007 | ML070850261 (Package) |
| NUREG-1853 | History and Framework of Commercial Low-Level Radioactive Waste Management in the United States - ACNW White Paper | Jan 2007 | ML070600684 |
| NUREG-1871 | Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant | Jan 2007 | ML070600578 |
| NUREG/CR-6894 R1 | Spent Fuel Transportation Package Response to the Caldecott Tunnel Fire Scenario | Jan 2007 | ML070460351 |
| NUREG/CR-6870 | Consideration of Geochemical Issues in Groundwater Restoration at Uranium In-Situ Leach Mining Facilities | Jan 2007 | ML070600405 |
| NUREG-1437 S28 V2 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Oyster Creek Nuclear Generating Station, Appendices - Final | Jan 2007 | ML070100258 |
| NUREG-1437 S28 V1 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Oyster Creek Nuclear Generating Station, Main Report - Final | Jan 2007 | ML070100234 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026