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Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2003
| Documents added in 2003 | |||
|---|---|---|---|
| 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-6820 | Application of Surface Complexation Modeling to Describe Uranium (VI) Adsorption and Retardation at the Uranium Mill Tailings Site at Naturita, Colorado | Dec 2003 | ML040210168 |
| NUREG-0933 S27 | A Prioritization of Generic Safety Issues | Dec 2003 | ML040070409 |
| NUREG/CR-6577 S2 | U.S. Nuclear Power Plant Operating Cost and Experience Summaries | Dec 2003 | ML040070512 |
| NUREG-1437 S13 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding H.B. Robinson Steam Electric Plant, Unit No. 2 (Final Report) | Dec 2003 | ML033450517 |
| NUREG-1614 V3 | FY 2004-2009 Strategic Plan (Draft for Comment) | Dec 2003 | ML033360673 |
| NUREG-1437 S17 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Regarding Dresden Nuclear Power Station, Units 2 and 3 (Draft for Comment) | Dec 2003 | ML033280676 |
| NUREG-1784 | Operating Experience Assessment - Effects of Grid Events on Nuclear Power Plant Performance | Dec 2003 | ML033530400 |
| NUREG/CP-0183 | Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop | Nov 2003 | ML033500412 |
| NUREG-1783 DFC | Interagency Steering Committee on Radiation Standards (ISCORS) Assessment of Radioactivity in Sewage Sludge: Modeling to Assess Radiation Doses (Draft for Comment) | Nov 2003 | ML033280626 |
| NUREG-1781 | CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident | Nov 2003 | ML033140399 |
| NUREG-1775 | Interagency Steering Committee on Radiation Standards (ISCORS) Assessment of Radioactivity in Sewage Sludge: Radiological Survey Results and Analysis | Nov 2003 | ML033140171 |
| NUREG-1437 S16 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Quad Cities Nuclear Power Station, Units 1 and 2 (Draft for Comment) | Nov 2003 | ML033020456 |
| NUREG-0713 Vol 24 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2002," Thirty-Fifth Annual Report | Oct 2003 | ML033230542 |
| NUREG/CP-0181 | International Collaborative Project to Evaluate Models for Nuclear Power Plant Applications: Proceedings of 5th Meeting | Oct 2003 | ML033370128 |
| NUREG-0933 S26 | A Prioritization of Generic Safety Issues | Oct 2003 | ML033100437 |
| NUREG/CR-6818 | Drop Test Results for Combustion Engineering Model ABB-2901 Fuel Pellet Shipping Package | Oct 2003 | ML033030180 |
| NUREG-1782 | Safety Evaluation Report Related to the License Renewal of the Fort Calhoun Station, Unit 1 | Oct 2003 | ML033020438 |
| NUREG-1777 | Regulatory Effectiveness Assessment of Option B of Appendix J | Oct 2003 | ML033030547 |
| NUREG-1779 | Safety Evaluation Report Related to License Renewal of St. Lucie Nuclear Plant, Units 1 and 2 | Sept 2003 | ML032940205 |
| NUREG/CR-6834 | Circuit Analysis - Failure Mode and Likelihood Analysis | Sept 2003 | ML032731464 |
| NUREG/CR-6782 | Comparison of U.S. Military and International Electromagnetic Compatibility Guidance | Sept 2003 | ML033000345 |
| NUREG/CR-5609 | Electromagnetic Compatibility Testing for Conducted Susceptibility Along Interconnecting Signal Lines --Final Report | Sept 2003 | ML032960137 |
| NUREG/CR-6823 | Handbook of Parameter Estimation for Probabilistic Risk Assessment | Sept 2003 | ML032900131 |
| NUREG/CR-6835 | Effects of Fuel Failure on Criticality Safety and Radiation Dose for Spent Fuel Casks | Sept 2003 | ML032880058 |
| NUREG/CR-6836 | Comparing Ground-Water Recharge Estimates Using Advanced Monitoring Techniques and Models | Sept 2003 | ML032880047 |
| NUREG-1780 | Regulatory Effectiveness of the Anticipated Transient Without Scram Rule | Sept 2003 | ML032790414 |
| NUREG/CR-6834 | Circuit Analysis - Failure Mode and Likelihood Analysis | Sept 2003 | ML032731464 |
| NUREG/CR-6833 | Formal Methods of Decision Analysis Applied to Prioritization of Research and Other Topics | Sept 2003 | ML033000339 |
| NUREG/CR-6804 | Second U.S. Nuclear Regulatory Commission International Steam Generator Tube Integrity Research Program | Sept 2003 | ML032681071 |
| NUREG/CR-6831 | Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage | Sept 2003 | ML032731021 |
| NUREG/CR-6815 | Review of the Margins for ASME Code Fatigue Design Curve - Effects of Surface Roughness and Material Variability | Sept 2003 | ML032670639 |
| NUREG-1757 V1 R1 | Consolidated NMSS Decommissioning Guidance: Decommissioning Process for Materials Licensees --Final Report | Sept 2003 | ML032530410 |
| NUREG-1757 V2 | Consolidated NMSS Decommissioning Guidance: Characterization, Survey, and Determination of Radiological Criteria-- Final Report | Sept 2003 | ML032530405 |
| NUREG-1757 V3 | Consolidated NMSS Decommissioning Guidance: Financial Assurance, Recordkeeping, and Timeliness--Final Report | Sept 2003 | ML032471471 |
| NUREG/BR-0010 R4 | Citizen's Guide to U.S. Nuclear Regulatory Commission Information | Aug 2003 | ML032660837 |
| NUREG-0936 V22 N1 | NRC Regulatory Agenda, Semiannual Report, January - June 2003 | Aug 2003 | ML032540376 |
| NUREG-1748 | Environmental Review Guidance for Licensing Actions Associated with NMSS Programs, Final Report. | Aug 2003 | ML032540811 |
| NUREG/CR-6832 | Regulatory Effectiveness of Unresolved Safety Issue (USI) A-45, Shutdown Decay Heat Removal Requirements | Aug 2003 | ML032550456 |
| NUREG/CR-6825 | Literature Review and Assessment of Plant and Animal Transfer Factors Used in Performance Assessment Modeling | Aug 2003 | ML032680646 |
| NUREG-1437 S12 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Fort Calhoun Station, Unit 1, Final Report | Aug 2003 | ML032230075 |
| NUREG/BR-0006 R6 | Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC Forms 741 and 740M) Effective Date: October 1, 2003 | Aug 2003 | ML032540406 |
| NUREG/BR-0006 R6 Errata | Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC Forms 741 and 740M) Effective Date: October 1, 2003 | Dec 2005 | ML060300140 |
| NUREG/BR-0007 R5 | Instructions for the Preparation and Distribution of Material Status Reports (DOE/NRC Forms 742 and 742C) Effective Date: October 1, 2003 | Aug 2003 | ML032540392 |
| NUREG/BR-0007 R5 Errata | Instructions for the Preparation and Distribution of Material Status Reports (DOE/NRC Forms 742 and 742C) Effective Date: October 1, 2003 | Jan 2006 | ML060300141 |
| NUREG/CR-6826 | Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless Steels | Aug 2003 | ML032320557 |
| NUREG/BR-0146 R3 | The IG at the NRC | Aug 2003 | ML032410486 |
| NUREG-1776 | Regulatory Effectiveness of the Station Blackout Rule | Aug 2003 | ML032450542 |
| NUREG/CR-6595 R1 DFC | An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events (Draft For Comment) | Aug 2003 | ML032330225 |
| NUREG/CR-6525 R1 | SECPOP 2000: Sector Population, Land Fraction, and Economic Estimation Program | Aug 2003 | ML032310279 |
| NUREG/CR-6824 | Materials Behavior in HTGR Environments | July 2003 | ML032370015 |
| NUREG/CR-6814 | Final Report on Advanced Nondestructive Evaluation for Steam Generator Tubing for the Second International Steam Generator Tube Integrity Program | July 2003 | ML032471423 |
| NUREG-1774 | A Survey of Crane Operating Experience at U.S. Nuclear Power Plants From 1968 Through 2002 | July 2003 | ML032060160 |
| NUREG/BR-0240 R2 | Reporting Safety Concerns to NRC | July 2003 | ML032390327 |
| NUREG/CR-6805 | A Comprehensive Strategy of Hydrogeologic Modeling and Uncertainty Analysis for Nuclear Facilities and Sites | July 2003 | ML032470827 |
| NUREG-1415 V15 N2 | Office of the Inspector General Semiannual Report | July 2003 | ML031920600 |
| NUREG-1804 R2 | Yucca Mountain Review Plan: Final Report | July 2003 | ML032030389 |
| NUREG-1620 R1 | Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings Sites Under Title II of the Uranium Mill Tailings Radiation Control Act of 1978 | June 2003 | ML032250190 |
| NUREG-1569 | Standard Review Plan for In Situ Leach Uranium Extraction License Applications | June 2003 | ML032250177 |
| NUREG-1640 V1 | Radiological Assessments for Clearance of Materials From Nuclear Facilities: Main Report | June 2003 | ML032250178 |
| NUREG-1640 V3 | Radiological Assessments for Clearance of Materials From Nuclear Facilities: Appendices F and G | June 2003 | ML032250706 (Package) |
| NUREG-0386 Digest N12 | United States Nuclear Regulatory Commission Staff Practice and Procedure Digest Commission, Appeal Board and Licensing Board Decisions July 1972 - June 30, 2002. | June 2003 | ML032060515 (Package) |
| NUREG-1805 V1 DFC | Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program (Draft or Comment) | June 2003 | ML031990145 |
| NUREG-1805 V2 DFC | Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program: Appendices (Draft for Comment) | June 2003 | ML031980360 |
| NUREG/CR-6811 | Strategies for Application of Isotopic Uncertainties in Burnup Credit | June 2003 | ML032130638 |
| NUREG-1125 V24 | A Compilation of Reports of The Advisory Committee on Reactor Safeguards, 2002 Annual | June 2003 | ML032020395 |
| NUREG-1635 V5 | Review and Evaluation of the Nuclear Regulatory Commission Safety Research Program | June 2003 | ML031920286 |
| NUREG-1773 | Environmental Impact Statement for the Proposed Idaho Spent Fuel Facility at the Idaho National Engineering and Environmental Laboratory in Butte County, Idaho," Draft Report for Comment | June 2003 | ML031810193 |
| NUREG-1437 S15 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Virgil C. Summer Nuclear Station (Draft for Comment) | June 2003 | ML031960328 |
| NUREG/CR-6822 | Collaborative Study of NUPEC Seismic Field Test Data for NPP Structures | June 2003 | ML031910007 |
| NUREG-1437 S14 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding R.E. Ginna Nuclear Power Plant (Draft for Comment) | June 2003 | ML031750834 |
| NUREG/CR-4667 V32 | Environmentally Assisted Cracking in Light Water Reactors, Annual Report January - December 2001 | June 2003 | ML031750770 |
| NUREG/CR-6819 V1 | Common-Cause Failure Event Insights: Emergency Diesel Generators | May 2003 | ML031710318 |
| NUREG/CR-6819 V2 | Common-Cause Failure Event Insights: Motor-Operated Valves | May 2003 | ML031710328 |
| NUREG/CR-6819 V3 | Common-Cause Failure Event Insights: Pumps | May 2003 | ML031710336 |
| NUREG/CR-6819 V4 | Common-Cause Failure Event Insights: Circuit Breakers | May 2003 | ML031710861 |
| NUREG-1707 V5 | Interagency Steering Committee on Radiation Standards: 2002 Annual Report | May 2003 | ML031840320 |
| NUREG/CR-6778 | The Effects of Composition and Heat Treatment on Hardening and Embrittlement of Reactor Pressure Vessel Steels | May 2003 | ML031700122 |
| NUREG/CR-6792 | Behavior of PWR Reactor Coolant System Components, Other than Steam Generator Tubes, Under Severe Accident Conditions, Phase I Final Report | May 2003 | ML031500699 |
| NUREG/CR-6802 | Recommendations for Shielding Evaluations for Transport & Storage Packages | May 2003 | ML031330514 |
| NUREG-1437 S11 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 11 Regarding St. Lucie Units 1 and 2, Final Report | May 2003 | ML031360709 (Package) |
| NUREG-1437 S13 DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding H. B. Robinson Steam Electric Plant, Unit 2 (Draft for Comment) | May 2003 | ML031250201 (Package) |
| NUREG/BR-0135 R3 | Drug- Free Workplace Program | April 2003 | ML031500691 |
| NUREG/IA-0209 | Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR Transient Codes and Updating of MATPRO Package for Modeling of LOCA and RIA Validation Cases with Zr-1%Nb (VVER type) Cladding | April 2003 | ML031340376 |
| NUREG/BR-0007 R4 | Instructions for Preparation & Distribution of Material Status Reports, (DOE/NRC Forms 742 and 742C), Effective Date: October 1, 2003 | April 2003 | ML031120372 |
| NUREG/BR-0006 R5 | Instructions for Completing Nuclear Material Transaction Reports (DOE/NRC Forms 741 and 740M), Effective Date: October 1, 2003 | April 2003 | ML031120440 |
| NUREG/CR-6813 | Issues and Recommendations for Advancement of PRA Technology in Risk-Informed Decision Making | April 2003 | ML031060514 |
| NUREG-1771 | U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes | April 2003 | ML031140094 (Package) |
| NUREG-1700 R1 | Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans | April 2003 | ML031270391 |
| NUREG-0090 V25 | Report to Congress on Abnormal Occurrences, Fiscal Year 2002 | April 2003 | ML031000094 |
| NUREG/CR-6810 | Overpressurization Test of a 1:4 Scale Prestressed Concrete Containment Vessel Model | March 2003 | ML032040014 |
| NUREG/CR-6812 | Emerging Technologies in Instrumentation and Controls | March 2003 | ML031900433 |
| NUREG/CP-0180 | Proceedings of the 2002 Nuclear Safety Research Conference, Held at Marriott Hotel at Metro Center Washington, DC, October 28-30, 2002 | March 2003 | ML031060154 (Package) |
| NUREG/CR-6801 | Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses | March 2003 | ML031110292 |
| NUREG-0383 V2 R24 | Directory of Certificates of Compliance for Radioactive Materials Packages, Certificates of Compliance | March 2003 | ML031080247 (Package) |
| NUREG-0383 V3 R21 | Directory of Certificates of Compliance for Radioactive Materials Packages. Report of NRC-Approved Quality Assurance Programs for Radioactive Materials Packages | March 2003 | ML031070443 |
| NUREG-1772 | Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2, and Catawba Nuclear Station, Units 1 & 2 | March 2003 | ML030850251 (Package) |
| NUREG-1769 | Safety Evaluation Report Related to License Renewal of Peach Bottom Atomic Power Station, Units 2 & 3 | March 2003 | ML031010136 (Package) |
| NUREG/CR-6799 | Analysis of Rail Car Components Exposed to Tunnel Fire Environment | March 2003 | ML031050501 |
| NUREG/CR-6807 | Results of NRC-Sponsored Stellite 6 Aging & Friction Testing | March 2003 | ML030850725 |
| NUREG/CR-6806 | MOV Stem Lubricant Aging Research | March 2003 | ML030780590 |
| NUREG/CR-6800 | Assessment of Reactivity Margins & Loading Curves for PWR Burnup-Credit Cask Designs | March 2003 | ML031110280 |
| NUREG/CR-6808 | Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance | Feb 2003 | ML030920542 (Package) |
| NUREG/CR-6795 | A Comparison of Three Round Robin Studies on ISI Reliability of Wrought Stainless Steel Piping | Feb 2003 | ML030710592 |
| NUREG/CR-6793 | Numerical Simulation of the Howard Street Tunnel Fire, Baltimore, Maryland, July 2001 | Feb 2003 | ML030550670 |
| NUREG-1768 DFC | United States Nuclear Regulatory Commission Package Performance Study Test Protocols (Draft For Comment) | Feb 2003 | ML030510389 |
| NUREG-1100 V19 | Budget Estimates and Performance Plan Fiscal Year 2004 | Feb 2003 | ML030380500 (Package) |
| NUREG-1542 V8 | USNRC Performance and Accountability Report - FY2002 | Jan 2003 | ML040910017 |
| NUREG-0936 V21 N2 | NRC Regulatory Agenda Semiannual Report, July - December 2002 | Jan 2003 | ML030570362 |
| NUREG/CR-6798 | Isotopic Analysis of High-Burnup PWR Spent Fuel Samples From the Takahama-3 Reactor | Jan 2003 | ML030570346 |
| NUREG-1556 V9 App BB | Consolidated Guidance About Materials Licenses, Program-Specific Guidance About Medical Use Licenses: Appendix BB (Final Report) | Jan 2003 | ML030440154 |
| NUREG/CR-6781 | Recommendations on the Credit for Cooling Time in PWR Burnup Credit Analyses | Jan 2003 | ML030290585 |
| NUREG-1437 S10 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Peach Bottom Atomic Power Station, Units 2 & 3 (Final Report) | Jan 2003 | ML030270059 (Package) |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026