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Publications Prepared by NRC Staff
`Search NUREG-Series Pubs
Documentation and staff-related information, including recruiting material, or general information about the NRC. Other staff reports may be available in ADAMS.
| Document Identifier | Title |
|---|---|
| NUREG-0050 | Recommendations Related to Browns Ferry Fire |
| NUREG-0061 | Safety Evaluation Report Related to the Operation of Browns Ferry, Units 1 and 2, Following the March 22, 1975 Fire |
| NUREG-75/014 | Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants (WASH-1400) |
| NUREG-75/087 | Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition |
| NUREG-0090 | Report to Congress on Abnormal Occurrences |
| NUREG-0133 | Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications |
| NUREG-0298 | Fire Protection Action Plan: Status Summary Report |
| NUREG-0302 | Remarks Presented (Questions/Answers Discussed) at Public Regional Meetings to Discuss Regulations (10 CFR Part 21) for Reporting of Defects and Noncompliance |
| NUREG-0386 | United States Nuclear Regulatory Commission Staff Practice and Procedure Digest: Commission, Appeal Board, and Licensing Board Decisions (July 1972 – September 2010) |
| NUREG-0396 | Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants |
| NUREG-0430 | Licensed Fuel Facility Status Report — Inventory Difference Data: July 1, 2001 – June 30, 2002 |
| NUREG-0492 | Fault Tree Handbook |
| NUREG-0498 | Draft Final Environmental Statement: Related to the Operation of Watts Bar Nuclear Plant, Unit 2 |
| NUREG-0544 | NRC Collection of Abbreviations |
| NUREG-0561 | Physical Protection of Shipments of Irradiated Reactor Fuel |
| NUREG-0585 | TMI-2 Lessons Learned Task Force Final Report |
| NUREG-0586 | Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities |
| NUREG-0588 | Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment |
| NUREG-0612 | Control of Heavy Loads at Nuclear Power Plants: Resolution of Generic Technical Activity A-36 |
| NUREG-0654 | Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (FEMA-REP-1) |
| NUREG-0693 | Analysis of Ultimate Heat Sink Cooling Ponds |
| NUREG-0696 | Functional Criteria for Emergency Response Facilities |
| NUREG-0700 | Human-System Interface Design Review Guidelines |
| NUREG-0711 | Human Factors Engineering Program Review Model |
| NUREG-0713 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities |
| NUREG-0725 | Public Information Circular for Shipments of Irradiated Reactor Fuel |
| NUREG-0733 | Analysis of Ultimate-Heat-Sink Spray Ponds |
| NUREG-0737 | Clarification of TMI Action Plan Requirements |
| NUREG-0750 | Nuclear Regulatory Commission Issuances, Hardbound Editions |
| NUREG-0782 | Draft Environmental Impact Statement on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Waste |
| NUREG-0800 | Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition |
| NUREG-0814 | Methodology for Evaluation of Emergency Response Facilities |
| NUREG-0847 | Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Units 1 and 2 |
| NUREG-0910 | NRC Comprehensive Records Disposition Schedule |
| NUREG-0917 | Nuclear Regulatory Commission Staff Computer Programs for Use with Meteorological Data |
| NUREG-0933 | Resolution of Generic Safety Issues (Formerly entitled "A Prioritization of Generic Safety Issues") |
| NUREG-0936 | NRC Regulatory Agenda: Semiannual Report |
| NUREG-0945 | Final Environmental Impact Statement on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Waste |
| NUREG-0980 | Nuclear Regulatory Legislation: 111th Congress |
| NUREG-1021 | Operator Licensing Examination Standards for Power Reactors |
| NUREG-1022 | Event Reporting Guidelines: 10 CFR 50.72 and 50.73 |
| NUREG-1055 | Improving Quality and the Assurance of Quality in the Design and Construction of Nuclear Power Plants: A Report to Congress |
| NUREG-1061 | Report of the U.S. Nuclear Regulatory Commission Piping Review Committee |
| NUREG-1065 | Acceptable Standard Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium Facilities |
| NUREG-1100 | Performance Budget/Congressional Budget Justification |
| NUREG-1122 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors |
| NUREG-1123 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors |
| NUREG-1148 | Nuclear Power Plant Fire Protection Research Program |
| NUREG-1150 | Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants |
| NUREG-1220 | Training Review Criteria and Procedures |
| NUREG-1250 | Report on the Accident at the Chernobyl Nuclear Power Station |
| NUREG-1262 | Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses |
| NUREG-1280 | Standard Format and Content Acceptance Criteria for the Material Control and Accounting (MC&A) Reform Amendment: 10 CFR Part 74, Subpart E |
| NUREG-1307 | Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities |
| NUREG-1335 | Individual Plant Examination: Submittal Guidance |
| NUREG-1350 | Information Digest |
| NUREG-1364 | Regulatory Analysis for the Resolution of Generic Safety Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas |
| NUREG-1367 | Functional Capability of Piping Systems |
| NUREG-1379 | NRC Editorial Style Guide |
| NUREG-1407 | Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities |
| NUREG-1409 | Backfitting Guidelines |
| NUREG-1415 | Office of the Inspector General Semiannual Report to Congress |
| NUREG-1430 | Standard Technical Specifications — Babcock and Wilcox Plants |
| NUREG-1431 | Standard Technical Specifications — Westinghouse Plants |
| NUREG-1432 | Standard Technical Specifications — Combustion Engineering Plants |
| NUREG-1433 | Standard Technical Specifications — General Electric Plants (BWR/4) |
| NUREG-1434 | Standard Technical Specifications — General Electric Plants (BWR/6) |
| NUREG-1437 | Generic Environmental Impact Statement for License Renewal of Nuclear Plants |
| NUREG-1449 | Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States |
| NUREG-1465 | Accident Source Terms for Light-Water Nuclear Power Plants |
| NUREG-1472 | Regulatory Analysis for the Resolution of Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment |
| NUREG-1475 | Applying Statistics |
| NUREG-1478 | Operator Licensing Examiner Standards for Research and Test Reactors |
| NUREG-1482 | Guidelines for Inservice Testing at Nuclear Power Plants |
| NUREG-1501 | Background as a Residual Radioactivity Criterion for Decommissioning: Appendix A to the Draft Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for Decommissioning of NRC-Licensed Nuclear Facilities |
| NUREG-1505 | A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys |
| NUREG-1513 | Integrated Safety Analysis Guidance Document |
| NUREG-1516 | Management of Radioactive Material Safety Programs at Medical Facilities |
| NUREG-1520 | Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility |
| NUREG-1521 | Technical Review of Risk-Informed, Performance-Based Methods for Nuclear Power Plant Fire Protection Analyses |
| NUREG-1526 | Lessons Learned from Early Implementation of The Maintenance Rule at Nine Nuclear Power Plants |
| NUREG-1536 | Standard Review Plan for Dry Cask Storage Systems |
| NUREG-1537 | Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors |
| NUREG-1542 | NRC's Performance and Accountability Report |
| NUREG-1547 | Methodology for Developing and Implementing Alternative Temperature-Time Curves for Testing the Fire Resistance of Barriers for Nuclear Power Plant Applications |
| NUREG-1552 | Fire Barrier Penetration Seals in Nuclear Power Plants |
| NUREG-1555 | Standard Review Plans for Environmental Reviews for Nuclear Power Plants: Environmental Standard Review Plan (with Supplement 1 for Operating Reactor License Renewal) |
| NUREG-1556 | Consolidated Guidance About Materials Licenses |
| NUREG-1563 | Branch Technical Position on the Use of Expert Elicitation in the High-Level Radioactive Waste Program |
| NUREG-1567 | Standard Review Plan for Spent Fuel Dry Storage Facilities |
| NUREG-1569 | Standard Review Plan for In Situ Leach Uranium Extraction License Applications |
| NUREG-1574 | Standard Review Plan on Transfer and Amendment of Antitrust License Conditions and Antitrust Enforcement |
| NUREG-1575 | Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) |
| NUREG-1576 | Multi-Agency Radiological Laboratory Analytical Protocols Manual |
| NUREG-1577 | Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance |
| NUREG-1609 | Standard Review Plan for Transportation Packages for Radioactive Material |
| NUREG-1611 | Aging Management of Nuclear Power Plant Containments for License Renewal |
| NUREG-1614 | Strategic Plan |
| NUREG-1617 | Standard Review Plan for Transportation Packages for Spent Nuclear Fuel |
| NUREG-1620 | 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 |
| NUREG-1624 | Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA) |
| NUREG-1628 | Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Reactors |
| NUREG-1635 | Review and Evaluation of the Nuclear Regulatory Commission Safety Research Program: A Report to the U.S. Nuclear Regulatory Commission |
| NUREG-1640 | Radiological Assessments for Clearance of Materials from Nuclear Facilities |
| NUREG-1648 | Lessons Learned From Maintenance Rule Baseline Inspections |
| NUREG-1649 | Reactor Oversight Process |
| NUREG-1650 | United States National Report for the Convention on Nuclear Safety |
| NUREG-1700 | Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans |
| NUREG-1703 | Characterization of Radioactive Slags |
| NUREG-1705 | Safety Evaluation Report Related to the License Renewal of Calvert Cliffs Nuclear Power Plant, Units 1 and 2 |
| NUREG-1713 | Standard Review Plan for Decommissioning Cost Estimates for Nuclear Power Reactors |
| NUREG-1714 | Final Environmental Impact Statement for the Construction and Operation of an Independent Spent Fuel Storage Installation on the Reservation of the Skull Valley Band of Goshute Indians and the Related Transportation Facility in Tooele County, Utah |
| NUREG-1717 | Systematic Radiological Assessment of Exemptions for Source and Byproduct Materials |
| NUREG-1718 | Standard Review Plan for the Review of an Application for a Mixed Oxide (MOX) Fuel Fabrication Facility |
| NUREG-1720 | Re-Evaluation of the Indoor Resuspension Factor for the Screening Analysis of the Building Occupancy Scenario for NRC’s License Termination Rule |
| NUREG-1723 | Safety Evaluation Report Related to the License Renewal of Oconee Nuclear Station, Units 1, 2, and 3 |
| NUREG-1725 | Human Interaction with Reused Soil: An Information Search |
| NUREG-1736 | Consolidated Guidance: 10 CFR Part 20 - Standards for Protection Against Radiation |
| NUREG-1738 | Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants |
| NUREG-1739 | Analysis of Public Comments on the Improved License Renewal Guidance Documents |
| NUREG-1742 | Perspectives Gained From the Individual Plant Examination of External Events (IPEEE) Program |
| NUREG-1743 | Safety Evaluation Report Related to the License Renewal of Arkansas Nuclear One, Unit 1 |
| NUREG-1748 | Environmental Review Guidance for Licensing Actions Associated with NMSS Programs |
| NUREG-1753 | Risk-Based Performance Indicators: Results of Phase 1 Development |
| NUREG-1757 | Consolidated Decommissioning Guidance |
| NUREG-1758 | Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray Fires |
| NUREG-1759 | Safety Evaluation Report Related to the License Renewal of Turkey Point Nuclear Plant, Units 3 and 4 |
| NUREG-1761 | Radiological Surveys for Controlling Release of Solid Materials |
| NUREG-1762 | Integrated Issue Resolution Status Report |
| NUREG-1764 | Guidance for the Review of Changes to Human Actions |
| NUREG-1765 | Basis Document for Large Early Release Frequency (LERF) Significance Determination Process (SDP): Inspection Findings that May Affect LERF |
| NUREG-1766 | Safety Evaluation Report Related to the License Renewal of North Anna Power Station, Units 1 and 2, and Surry Power Station, Units 1 and 2 |
| NUREG-1767 | Environmental Impact Statement on the Construction and Operation of a Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South Carolina |
| NUREG-1768 | United States Nuclear Regulatory Commission Package Performance Study Test Protocols |
| NUREG-1769 | Safety Evaluation Report Related to the License Renewal of Peach Bottom Atomic Power Station, Units 2 and 3 |
| NUREG-1772 | Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2, and Catawba Nuclear Station, Units 1 and 2 |
| NUREG-1773 | Environmental Impact Statement for the Proposed Idaho Spent Fuel Facility at the Idaho National Engineering and Environmental Laboratory in Butte County, Idaho |
| NUREG-1774 | A Survey of Crane Operating Experience at U.S. Nuclear Power Plants from 1968 through 2002 |
| NUREG-1775 | ISCORS Assessment of Radioactivity in Sewage Sludge: Radiological Survey Results and Analysis |
| NUREG-1776 | Regulatory Effectiveness of the Station Blackout Rule |
| NUREG-1777 | Regulatory Effectiveness Assessment of Option B of Appendix J |
| NUREG-1778 | Knowledge Base for Post-Fire Safe-Shutdown Analysis |
| NUREG-1779 | Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2 |
| NUREG-1780 | Regulatory Effectiveness of the Anticipated Transient Without Scram Rule |
| NUREG-1781 | CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident |
| NUREG-1782 | Safety Evaluation Report Related to the License Renewal of the Fort Calhoun Station, Unit 1 |
| NUREG-1783 | ISCORS Assessment of Radioactivity in Sewage Sludge: Modeling to Assess Radiation Doses |
| NUREG-1784 | Operating Experience Assessment — Effects of Grid Events on Nuclear Power Plant Performance |
| NUREG-1785 | Safety Evaluation Report Related to the License Renewal of H.B. Robinson Steam Electric Plant, Unit 2 |
| NUREG-1786 | Safety Evaluation Report Related to the License Renewal of R.E. Ginna Nuclear Power Plant |
| NUREG-1787 | Safety Evaluation Report Related to the License Renewal of the Virgil C. Summer Nuclear Station |
| NUREG-1788 | CFD Analysis of Full-Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident |
| NUREG-1789 | 10 CFR Part 52 Construction Inspection Program Framework Document |
| NUREG-1790 | Environmental Impact Statement for the Proposed National Enrichment Facility in Lea County, New Mexico |
| NUREG-1791 | Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m) |
| NUREG-1792 | Good Practices for Implementing Human Reliability Analysis (HRA) |
| NUREG-1793 | Final Safety Evaluation Report Related to Certification of the AP1000 Standard Design |
| NUREG-1795 | FAVOR Code Versions 2.4 and 3.1 Verification and Validation Summary Report |
| NUREG-1796 | Safety Evaluation Report Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2 |
| NUREG-1800 | Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants |
| NUREG-1801 | Generic Aging Lessons Learned (GALL) Report |
| NUREG-1803 | Safety Evaluation Report Related to the License Renewal of the Edwin I. Hatch Nuclear Plant, Units 1 and 2 |
| NUREG-1804 | Yucca Mountain Review Plan |
| NUREG-1805 | Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program |
| NUREG-1806 | Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50.61) |
| NUREG-1807 | Probabilistic Fracture Mechanics — Models, Parameters, and Uncertainty Treatment Used in FAVOR Version 04.1 |
| NUREG-1808 | Sensitivity Studies of the Probabilistic Fracture Mechanics Model Used in FAVOR |
| NUREG-1811 | Environmental Impact Statement for an Early Site Permit (ESP) at the North Anna ESP Site |
| NUREG-1814 | Status of the Decommissioning Program |
| NUREG-1815 | Environmental Impact Statement for an Early Site Permit (ESP) at the Exelon ESP Site |
| NUREG-1816 | Independent Verification of the Mitigating Systems Performance Index (MSPI) Results for the Pilot Plants |
| NUREG-1817 | Environmental Impact Statement for an Early Site Permit (ESP) at the Grand Gulf ESP Site |
| NUREG-1821 | Final Safety Evaluation Report on the Construction Authorization Request for the Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South Carolina |
| NUREG-1823 | U.S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials |
| NUREG-1824 | Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications |
| NUREG-1825 | Safety Evaluation Report Related to the License Renewal of the Joseph M. Farley Nuclear Plant, Units 1 and 2 |
| NUREG-1826 | APEX-AP1000 Confirmatory Testing To Support AP1000 Design Certification (Non-Proprietary) |
| NUREG-1827 | Safety Evaluation Report for the National Enrichment Facility in Lea County, New Mexico, Louisiana Energy Services |
| NUREG-1828 | Safety Evaluation Report Related to the License Renewal of the Arkansas Nuclear One, Unit 2 |
| NUREG-1829 | Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process |
| NUREG-1830 | Office of Investigations Annual Report |
| NUREG-1831 | Safety Evaluation Report Related to the License Renewal of the Donald C. Cook Nuclear Plant, Units 1 and 2 |
| NUREG-1832 | Analysis of Public Comments on the Revised License Renewal Guidance Documents |
| NUREG-1833 | Technical Bases for Revision to the License Renewal Guidance Documents |
| NUREG-1834 | Environmental Impact Statement for the Proposed American Centrifuge Plant in Piketon, Ohio |
| NUREG-1835 | Safety Evaluation Report for an Early Site Permit (ESP) at the North Anna ESP Site |
| NUREG-1836 | Standard Review Plan for Releasing Part of a Reactor Facility or Site for Unrestricted Use Before Approval of the License Termination Plan |
| NUREG-1837 | Regulatory Effectiveness Assessment of Generic Issue 43 and Generic Letter 88-14 |
| NUREG-1838 | Safety Evaluation Report Related to the License Renewal of the Millstone Power Station, Units 2 and 3 |
| NUREG-1839 | Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 and 2 |
| NUREG-1840 | Safety Evaluation of Early Site Permit Application in the Matter of System Energy Resources, Inc., a Subsidiary of Entergy Corporation, for the Grand Gulf Early Site Permit Site |
| NUREG-1842 | Evaluation of Human Reliability Analysis Methods Against Good Practices |
| NUREG-1843 | Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2, and 3 |
| NUREG-1844 | Safety Evaluation Report for an Early Site Permit (ESP) at the Exelon Generation Company, LLC (EGC) ESP Site |
| NUREG-1850 | Frequently Asked Questions on License Renewal of Nuclear Power Reactors |
| NUREG-1851 | Safety Evaluation Report for the American Centrifuge Plant in Piketon, Ohio |
| NUREG-1852 | Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire |
| NUREG-1853 | History and Framework of Commercial Low-Level Radioactive Waste Management in the United States: ACNW White Paper |
| NUREG-1854 | NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations |
| NUREG-1855 | Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making |
| NUREG-1856 | Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units 1 and 2 |
| NUREG-1860 | Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing, Volumes 1 and 2 |
| NUREG-1861 | Peer Review of GSI-191 Chemical Effects Research Program |
| NUREG-1862 | Development of a Pressure Drop Calculation Method for Debris-Covered Sump Screens in Support of Generic Safety Issue 191 |
| NUREG-1863 | Review of Responses to NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity" |
| NUREG-1864 | A Pilot Probabilistic Risk Assessment of a Dry Cask Storage System at a Nuclear Power Plant |
| NUREG-1865 | Safety Evaluation Report Related to the License Renewal of the Monticello Nuclear Generating Plant |
| NUREG-1871 | Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant |
| NUREG-1872 | Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site |
| NUREG-1873 | Environmental Impact Statement for License Renewal of the National Bureau of Standards Reactor |
| NUREG-1874 | Recommended Screening Limits for Pressurized Thermal Shock (PTS) |
| NUREG-1875 | Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station |
| NUREG-1880 | ATHEANA User’s Guide |
| NUREG-1885 | Report to Congress on the Security Inspection Program for Commercial Power Reactor and Category I Fuel Cycle Facilities: Results and Status Update - Annual Reports |
| NUREG-1886 | Joint Canada - United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages |
| NUREG-1887 | RASCAL 3.0.5: Description of Models and Methods |
| NUREG-1888 | Environmental Impact Statement for the Reclamation of the Sequoyah Fuels Corporation Site in Gore, Oklahoma |
| NUREG-1890 | Evaluating Igneous Activity at Yucca Mountain: Technical Basis for Decisionmaking |
| NUREG-1891 | Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station |
| NUREG-1900 | Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 and 2 |
| NUREG-1903 | Seismic Considerations for the Transition Break Size |
| NUREG-1907 | Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station |
| NUREG-1908 | Information Technology/Information Management Strategic Plan |
| NUREG-1909 | Background, Status, and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Facilities: ACNW&M White Paper |
| NUREG-1910 | Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities |
| NUREG-1911 | NRC Periodic Compliance Monitoring Report for U.S. Department of Energy Non-High-Level Waste Disposal Actions |
| NUREG-1912 | Summary and Analysis of Public Comments Received on Proposed Revisions to 10 CFR Part 26 – Fitness for Duty Programs |
| NUREG-1913 | Design Control in Pursuit of Engineering Excellence: A Quick Reference Guide for NRC Inspectors |
| Supplemental Environmental Impact Statement for the Combined License (COL) for North Anna Power Station Unit 3 | |
| NUREG-1918 | Phenomena Identification and Ranking Table Evaluation of Chemical Effects Associated with Generic Safety Issue 191 |
| 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 |
| NUREG-1921 | EPRI/NRC-RES Fire Human Reliability Analysis Guidelines – Final Report |
| NUREG-1922 | Computational Fluid Dynamics Analysis of Natural Circulation Flows in a Pressurized-Water Reactor Loop under Severe Accident Conditions |
| NUREG-1923 | Safety Evaluation Report for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant (VEGP) ESP Site |
| NUREG-1924 | Electric Raceway Fire Barrier Systems in U.S. Nuclear Power Plants |
| NUREG-1925 | Research Activities |
| NUREG-1927 | Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance |
| NUREG-1928 | Safety Evaluation Report Related to the License Renewal of Three Mile Island Nuclear Station, Unit 1: Docket No. 50-289, Exelon Generation Company, LLC |
| NUREG-1929 | Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2 |
| NUREG-1930 | Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 |
| NUREG-1931 | Safety Evaluation Report Related to the License Renewal of Susquehanna Steam Electric Station, Units 1 and 2 |
| NUREG-1934 | Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG) |
| NUREG-1935 | State-of-the-Art Reactor Consequence Analyses (SOARCA) Report: Draft Report for Comment |
| NUREG-1936 | Final Environmental Impact Statement for the Combined License (COL) for Calvert Cliffs Nuclear Power Plant Unit 3 |
| NUREG-1937 | Environmental Impact Statement for Combined Licenses (COLs) for South Texas Project Electric Generating Station Units 3 and 4 |
| NUREG-1938 | Environmental Impact Statement for the Proposed GE-Hitachi Global Laser Enrichment, LLC Facility in Wilmington, North Carolina |
| NUREG-1939 | Final Environmental Impact Statement for Combined Licenses for Virgil C. Summer Nuclear Station, Units 2 and 3 |
| NUREG-1941 | Final Environmental Impact Statement for Combined Licenses (COLs) for Levy Nuclear Plant Units 1 and 2 |
| NUREG-1943 | Final Environmental Impact Statement for Combined Licenses (COLs) for Comanche Peak Nuclear Power Plant Units 3 and 4 |
| NUREG-1945 | Environmental Impact Statement for the Proposed Eagle Rock Enrichment Facility in Bonneville County, Idaho |
| NUREG-1946 | Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants |
| NUREG-1947 | Final Supplemental Environmental Impact Statement for Combined License (COLs) for Vogtle Electric Generating Plant Unit 3 and 4 |
| NUREG-1949 | Safety Evaluation Report Related to Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada; Volume 1: General Information |
| NUREG-1950 | Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800 |
| NUREG-1951 | Safety Evaluation Report for the Eagle Rock Enrichment Facility in Bonneville County, Idaho |
| NUREG-1953 | Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models—Surry and Peach Bottom |
| NUREG-1954 | Enterprise Content Management: Streamlining How Staff and Stakeholders Work within the Nuclear Regulatory Commission’s Regulatory Environment |
| NUREG-1955 | Safety Evaluation Report Related to the License Renewal of Duane Arnold Energy Center |
| NUREG-1958 | Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station: Docket No. 50-305, Dominion Energy Kewaunee, Inc. |
| NUREG-1959 | Intrusion Detection Systems and Subsystems: Technical Information for NRC Licensees |
| NUREG-1960 | Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plant Units 1 and 2 |
| NUREG-1961 | Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 |
| NUREG-1962 | Guidance on the Implementation of Integrated Safety Analysis Requirements for 10 CFR Part 40 Facilities Authorized to Possess 2,000 Kilograms or More of Uranium Hexafluoride — Draft Report for Comment |
| NUREG-1964 | Access Control Systems: Technical Information for NRC Licensees |
| NUREG-2101 | Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station |
| NUREG-2102 | Safety Evaluation Report Related to the License Renewal of Hope Creek Generating Station |
| NUREG-2103 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized-Water Reactors |
| NUREG-2104 | Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling-Water Reactors |
| NUREG-2105 | Draft Environmental Impact Statement for Combined License (COL) for Enrico Fermi Unit 3 |
| NUREG-2107 | Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Repository License Application – Postclosure Volume: Repository Safety After Permanent Closure |
| NUREG-2108 | Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Repository License Application – Preclosure Volume: Repository Safety Before Permanent Closure |
| NUREG-2109 | Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Repository License Application – Administrative and Programmatic Volume |
| NUREG-2113 | Final Environmental Impact Statement for the Proposed Fluorine Extraction Process and Depleted Uranium Deconversion Plant |
| NUREG-2111 | Draft Environmental Impact Statement for Combined Licenses (COLs) for William States Lee III Nuclear Station Units 1 and 2 |
| NUREG-2115 | Central and Eastern United States Seismic Source Characterization for Nuclear Facilities |
| 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 |
| NUREG-2117 | Practical Implementation Guidelines for SSHAC Level 3 and 4 Hazard Studies |
| NUREG-2118 | Occupational Radiation Exposure at Agreement State-Licensed Materials Facilities, 1997-2010 |
| NUREG-2123 | Safety Evaluation Report Related to the License Renewal of Columbia Generating Station |
| NUREG-2125 | Spent Fuel Transportation Risk Assessment |
| NUREG-2128 | Electrical Cable Test Results and Analysis During Fire Exposure (ELECTRA-FIRE), A Consolidation of Three Major Fire-Induced Circuit and Cable Failure Experiments Performed Between 2001 and 2011 |
| NUREG-2150 | A Proposed Risk Management Regulatory Framework |
Page Last Reviewed/Updated Tuesday, September 04, 2012
