Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2009
| Documents added in 2009 | |||
|---|---|---|---|
| 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/CR-6998 | Review of Information for Spent Nuclear Fuel Burnup Confirmation | Dec 2009 | ML100210543 |
| NUREG/CR-6994 | Argonne Model Boiler Test Results | Dec 2009 | ML100082156 (Package) |
| NUREG/IA-0217 | Investigations of the VVER-1000 Coolant Transient Benchmark I with the Coupled Code System RELAP5/PARCS | Dec 2009 | ML093620091 |
| NUREG/IA-0219 | Estimation of Operator Action Time Windows By RELAP5/MOD3.3 | Dec 2009 | ML093620090 |
| NUREG/IA-0220 | Quantitative Code Assessment with Fast Fourier Transform Based Method Improved by Signal Mirroring | Dec 2009 | ML093620089 |
| NUREG-1910 S1 DFC | Environmental Impact Statement (EIS) for the Moore Ranch ISR Project in Campbell County, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Draft Report for Comment) | Dec 2009 | ML093350050 |
| NUREG-1910 S2 DFC | Environmental Impact Statement (EIS) for the Nichols Ranch ISR Project in Campbell and Johnson Counties, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Draft Report for Comment) | Dec 2009 | ML093340536 |
| NUREG-1910 S3 DFC | Environmental Impact Statement (EIS) for the Moore Ranch ISR Project in Campbell County, Wyoming: Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (Draft Report for Comment) | Dec 2009 | ML100540052 |
| NUREG/IA-0216 V1 | International HRA Empirical Study – Phase 1 Report: Description of Overall Approach and Pilot Phase Results from Comparing HRA Methods to Simulator Performance Data | Nov 2009 | ML093380283 |
| NUREG-1921 DFC | EPRI/NRC-RES Fire Human Reliability Analysis Guidelines | Nov 2009 | ML093350494 |
| NUREG-1929 V1 & V2 S1 | Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2 | Oct 2009 | ML093140250 |
| NUREG-1928 | Safety Evaluation Report Related to the License Renewal of Three Mile Island Nuclear Station, Unit 1 | Oct 2009 | ML092950458 (Package) |
| NUREG-1929 V1 | Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2 | Oct 2009 | ML093020274 (Package) |
| NUREG-1929 V2 | Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2 | Oct 2009 | ML093000278 |
| NUREG-1437 S39 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Prairie Island Units 1 and 2 (Draft for Comment) | Oct 2009 | ML093170484 |
| NUREG-1930 V1 | Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3 | Oct 2009 | ML093170451 |
| NUREG-1930 V2 | Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3 | Oct 2009 | ML093170671 |
| NUREG-1931 | Safety Evaluation Report Related to the License Renewal of Susquehanna Steam Electric Station, Units 1 and 2 | Oct 2009 | ML093170786 (Package) |
| NUREG/CR-7001 | Predictive Bias and Sensitivity in NRC Fuel Performance Codes | Oct 2009 | ML093070406 |
| NUREG/CR-6992 | Instrumentation and Controls in Nuclear Plants: An Emerging Technologies Update | Oct 2009 | ML093100200 |
| NUREG-1927 DFC | Standard Review Plan for Renewal of Independent Spent Fuel Storage Installation Licenses and Dry Cask Storage System Certificates of Compliance | Sept 2009 | ML100350309 |
| NUREG/CR-6997 | Modeling a Digital Feedwater Control System Using Traditional Probabilistic Risk Assessment Methods | Sept 2009 | ML101020169 |
| NUREG/BR-0456 | U.S. Nuclear Regulatory Commission Organizational Values | Sept 2009 | ML093130109 |
| NUREG/BR-0458 | Departamento de Justicia de los Estados Unidos Division de Derechos Cililes (Your Rights Under Title VI of the Civil Rights Act of 1964) | Sept 2009 | ML093000232 |
| NUREG/BR-0459 | Federal Protections Against National Origin Discrimination | Sept 2009 | ML093000290 |
| NUREG/BR-0460 | Nondiscrimination On The Basis of Sex in Federally Assisted Programs | Sept 2009 | ML093000298 |
| NUREG/BR-0462 | Americans with Disabilities Act | Sept 2009 | ML093000306 |
| NUREG-1907 S1 | Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station | Sept 2009 | ML092740567 |
| NUREG-0936 V28 N1 | NRC Regulatory Agenda; Semiannual Report January – June 2009 | Sept 2009 | ML092940708 |
| NUREG/CR-6791 R1 | Eddie Current Reliability Results From The Steam Generator Mock-Up Analysis Round-Robin | Sept 2009 | ML092870775 |
| NUREG-1925 | Research Activities 2009 | Sept 2009 | ML092790459 |
| NUREG-1924 DFC | Electric Raceway Fire Barrier Systems in U.S. Nuclear Power Plants (Draft for Comment) | Sept 2009 | ML092650002 |
| NUREG/CR-6991 | Design Practices for Communications and Workstations in Highly Integrated Control Rooms | Sept 2009 | ML092740566 |
| NUREG-1350 V21 | Information Digest 2009-2010 | Aug 2009 | ML092370512 |
| NUREG-1919 | Resolution of Generic Safety Issue 188: Steam Generator Tube Leaks or Ruptures Concurrent with Containment Bypass from Main Steam Line or Feedwater Line Breaches. | Aug 2009 | ML092180651 |
| NUREG-1520 R1 DFC | Standard Review Plan for the Review of a License Application for a Fuel Cycle Facelift (Draft for Comment) | Aug 2009 | ML092260348 |
| NUREG/CR-6879 | Steam Generator Tube Integrity Issues: Failure Maps, Leak Rate Correlation Models. And Leak Rates in Restricted Areas | July 2009 | ML092260349 |
| NUREG-1923 | Safety Evaluation Report for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant (VEGP) ESP Site | July 2009 | ML092290639 (Package) |
| NUREG/CR-6996 | Nondestructive and Destructive Examination Studies on Removed-From-Service Control Rod Drive Mechanism Penetrations | July 2009 | ML092170311 (Package) |
| NUREG-1885 R2 | 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 2008 | July 2009 | ML091950057 |
| NUREG-1437 V1 R1 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Main Report (Draft for Comment) | July 2009 | ML091770049 |
| NUREG-1437 V2 R1 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Appendices (Draft for Comment) | July 2009 | ML091770048 |
| NUREG-1555 S1 R1 DFC | Standard Review Plans for Environmental Reviews of Nuclear Power Plants Supplement1: Operating License Renewal (Draft for Comment) | July 2009 | ML090230497 |
| NUREG-1437 S37 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Three Mile Island Unit I (Final Report) | June 2009 | ML091751063 |
| NUREG/CR-6974 V1 | Symbolic Nuclear Analysis Package (SNAP): Common Application Framework for Engineering Analysis (CAFEAN) Preprocessor Plug-in Application Programming Interface Main Report | June 2009 | ML091980223 |
| NUREG/CR-6974 V2 | Symbolic Nuclear Analysis Package (SNAP): Common Application Framework for Engineering Analysis (CAFEAN) Preprocessor Plug-in Application Programming Interface Appendix A, Part A | June 2009 | ML091980061 |
| NUREG/CR-6974 V3 | Symbolic Nuclear Analysis Package (SNAP): Common Application Framework for Engineering Analysis (CAFEAN) Preprocessor Plug-in Application Programming Interface Appendix A, Part B | June 2009 | ML091980062 |
| NUREG/BR-0347 | Let's Talk! Improving Performance Feedback Discussions for Employees and Supervisors | June 2009 | ML092130009 |
| NUREG/CR-6989 | Methodology for Estimating Fabrication Flaw Density and Distribution – Reactor Pressure Vessel Welds | May 2009 | ML093140251 |
| NUREG-1379 R2 | NRC Editorial Style Guide | May 2009 | ML093280744 |
| NUREG/CR-6986 | Evaluations of Structural Failure Probabilities and Candidate Inservice Inspection Programs | May 2009 | ML091620307 |
| NUREG-1437 S36 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Beaver Valley Power Station, Units 1 and 2 (Final Report) | May 2009 | ML091260011 |
| NUREG-1911 R1 | NRC Periodic Compliance Monitoring Report for U.S. Deportment of Energy Non-High-Level Waste Disposal Actions; Annual Report Calendar Year 2008 | May 2009 | ML091400501 |
| NUREG-0980 V1 N8 | Nuclear Regulatory Legislation, 110th Congress, 2nd Session | May 2009 | ML091900183 |
| NUREG-0980 V2 N8 | Nuclear Regulatory Legislation, 110th Congress, 2nd Session | May 2009 | ML091900285 (Package) |
| NUREG-0090 V31 | Report to Congress on Abnormal Occurrences – Fiscal Year 2008 | April 2009 | ML091540747 |
| NUREG-1920 V1 | Safety Evaluation Report Related to the License Renewal of Vogtle Electric Generating Plant, Units 1 and 2 | April 2009 | ML091320259 (Package) |
| NUREG-1920 V2 | Safety Evaluation Report Related to the License Renewal of Vogtle Electric Generating Plant, Units 1 and 2 | April 2009 | ML091320236 |
| NUREG-0936 V27 N2 | NRC Regulatory Agenda; Semiannual Report July – December 2008 | April 2009 | ML091680401 |
| NUREG-1536 R1a DFC | Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility (Draft for Comment) | April 2009 | ML091060180 |
| NUREG-0386 D14 | Staff Practice and Procedure Digest | March 2009 | ML091310522 (Package) |
| NUREG/CR-6966 | Tsunami Hazard Assessment at Nuclear Power Plant Sites in the United States of America Final Report | March 2009 | ML091590193 |
| NUREG-1855 V1 | Guidance on the Treatment on Uncertainties Associated with PRAs in Risk-Informed Decision Making | March 2009 | ML090970525 |
| NUREG-1886 | Joint Canada – United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages Final Report | March 2009 | ML090930197 |
| NUREG/CR-6982 | Assessment of Noise Level for Eddy Current Inspection of Steam Generator Tubes | March 2009 | ML090771085 |
| NUREG/CR-6988 | Final Report – Evaluation of Chemical Effects Phenomena in Post-LOCA Coolant | March 2009 | ML090750683 |
| NUREG/CR-6977 | Redox and Sorption Reactions of Iodine and Cesium During Transport Through Aquifer Sediments | March 2009 | ML090790302 |
| NUREG/CR-6987 | Analysis of Structural Materials Exposed to a Severe Fire Environment | Feb 2009 | ML091050354 |
| NUREG-0847 S21 | Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant Unit 2 | Feb 2009 | ML090570741 |
| NUREG/CR-6985 | A Benchmark Implementation of Two Dynamic Methodologies for the Reliability Modeling of Digital Instrumentation and Control Systems | Feb 2009 | ML090750687 |
| NUREG-1814 R2 | Status of the Decommissioning Program | Feb 2009 | ML090500375 |
| NUREG-1830 V5 | Annual Report for FY 2008: Office of Investigations | Feb 2009 | ML090420506 |
| NUREG/CR-6990 | Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6 | Feb 2009 | ML090990663 |
| NUREG-1918 | Phenomena Identification and Ranking Table Evaluation of Chemical Effects Associated with Generic Safety Issue 191 | Feb 20009 | ML090780090 |
| NUREG-0383 V3 R24 | Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC-Approved Quality Assurance Programs for Radioactive Materials Packages | Jan 2009 | ML090370268 |
| NUREG-0383 V2 R27 | Directory of Certificates of Compliance for Radioactive Materials Packages: Certificates of Compliance | Jan 2009 | ML090410560 (Package) |
Page Last Reviewed/Updated Tuesday, June 23, 2026
Page Last Reviewed/Updated Tuesday, June 23, 2026