Publications Prepared by NRC Staff
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-0016 | Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors: GALE-BWR 3.2 Code |
| NUREG-0017 | Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors: GALE-PWR 3.2 Code |
| NUREG-0040 | Licensee Contractor and Vendor Inspection Status Report – Quarterly Report |
| 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-75/038 | Environmental Survey of Transportation of Radioactive Materials to and from Nuclear Power Plants, Supplement 1 |
| NUREG-75/087 | Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (reissued as NUREG-0800) |
| NUREG-0090 | Report to Congress on Abnormal Occurrences |
| NUREG-0116 | Environmental Survey of the Reprocessing and Waste Management Portion of the LWR Fuel Cycle: A Task Force Report |
| NUREG-0133 | Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications |
| NUREG-0172 | Age-Specific Radiation Dose Commitment Factors for a one-year Chronic Year |
| 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-0313 | Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping |
| NUREG-0383 | Directory of Certificates of Compliance for Radioactive Materials Packages |
| 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-0410 | NRC Program for the Resolution of Generic Issues Related to Nuclear Power Plants |
| NUREG-0430 | Licensed Fuel Facility Status Report — Inventory Difference Data: July 1, 2001 – June 30, 2002 |
| NUREG-0456 | A Classification System for Radioactive Waste Disposal – What Waste Goes Where? |
| NUREG-0459 | Generic Adversary Characteristics Summary Report |
| NUREG-0484 | Methodology for Combining Dynamic Responses |
| NUREG-0492 | Fault Tree Handbook |
| NUREG-0498 | Final Environmental Statement: Related to the Operation of Watts Bar Nuclear Plant, Unit 2 |
| NUREG-0525 | Annual Safeguards Summary Event List (SSEL) |
| NUREG-0543 | Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) |
| NUREG-0544 | Collection of Abbreviations |
| NUREG-0561 | Physical Protection of Shipments of Irradiated Reactor Fuel |
| NUREG-0570 | Toxic Vapor Concentrations in the Control Room Following a Postulated Accidental Release |
| 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-0609 | Asymmetric Blowdown Loads on PWR Primary Systems – Resolution of Generic Task Action Plan A-2 |
| NUREG-0612 | Control of Heavy Loads at Nuclear Power Plants: Resolution of Generic Technical Activity A-36 |
| NUREG-0650 | Preparing NUREG-Series Publications, Revision 2 |
| 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-0783 | Suppression Pool Temperature Limits for BWR Containments |
| 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-0902 | Site Suitability, Selection and Characterization: Branch Technical Position — Low-Level Radioactive Waste |
| 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-0940 | Enforcement Actions: Significant Actions Resolved Individual Actions Semiannual Progress Report: July–December 1999 |
| NUREG-0945 | Final Environmental Impact Statement on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Waste |
| NUREG-0980 | Nuclear Regulatory Legislation: 117th Congress |
| NUREG-1021 | Operator Licensing Examination Standards for Power Reactors |
| NUREG-1022 | Event Reporting Guidelines: 10 CFR 50.72 and 50.73 |
| NUREG-1028 | Ruptured Cesium-137 Well-Logging Source at Shelwell Services, Inc., Hebron, Ohio |
| 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-1125 | A Compilation of Reports of The Advisory Committee on Reactor Safeguards |
| NUREG-1148 | Nuclear Power Plant Fire Protection Research Program |
| NUREG-1150 | Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants |
| NUREG-1164 | Information on the Confinement Capability of the Facility Disposal Area at West Valley, New York |
| NUREG-1199 | Standard Format and Content of a License Application for a Low-Level Radioactive Waste Disposal Facility |
| NUREG-1200 | Standard Review Plan for the review of a license application for a Low-Level Radioactive Waste Disposal Facility |
| NUREG-1213 | Plans and Schedules for Implementation of U.S. Nuclear Regulatory Commission Responsibilities under the Low-Level Radioactive Waste Amendments Act of 1985 (P.L. 99-240) |
| NUREG-1220 | Training Review Criteria and Procedures |
| NUREG-1250 | Report on the Accident at the Chernobyl Nuclear Power Station |
| NUREG-1251 | Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States |
| NUREG-1262 | Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses |
| NUREG-1274 | Review Process for Low-Level Radioactive Waste Disposal License Application Under Low-Level Radioactive Waste Policy Amendments Act |
| NUREG-1275 | Operating Experience Feedback Reports |
| 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-1293 | Quality Assurance Guidance for a Low-Level Radioactive Waste Disposal Facility |
| NUREG-1301 | Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors |
| NUREG-1302 | Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1 |
| NUREG-1307 | Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilitiess |
| NUREG-1322 | Acceptance Criteria for the Evaluation of Category I Fuel Cycle Facility Physical Security Plans |
| NUREG-1335 | Individual Plant Examination: Submittal Guidance |
| NUREG-1339 | Resolution of Generic Safety Issue 29: Bolting Degradation or Failure in Nuclear Power Plants |
| 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-1388 | Environmental Monitoring of Low-Level Radioactive Waste Disposal Facility |
| NUREG-1394 | Emergency Response Data System |
| NUREG-1407 | Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities |
| NUREG-1409 | Backfitting Guidelines |
| NUREG-1412 | Foundation for the Adequacy of the Licensing Bases – A Supplement to the Statement of Considerations for the Rule on Nuclear Power Plant License Renewal (10 CFR Part 54) |
| NUREG-1415 | Office of the Inspector General Semiannual Report to Congress |
| NUREG-1423 | Compilation of Reports Advisory Committee on Nuclear Waste |
| 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 BWR/6 Plants |
| 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-1456 | An Alternative Format for Category I Fuel Cycle Facility Physical Protection Plans |
| 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-1480 | Loss of an Iridium-192 Source and Therapy Misadministration at Indiana Regional Cancer Center Indiana, Pennsylvania, on November 16, 1992 |
| NUREG-1482 | Guidelines for Inservice Testing at Nuclear Power Plants |
| NUREG-1496 | Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRC-Licensed Nuclear Facilities |
| 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-1503 | Final Safety Evaluation Report: Related to the Certification of the Advanced Boiling Water Reactor Design |
| NUREG-1505 | A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys |
| NUREG-1507 | Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions |
| NUREG-1511 | Reactor Pressure Vessel Status Report |
| NUREG-1512 | Final Safety Evaluation Report: Related to Certification of the AP600 Standard Design |
| NUREG-1513 | Integrated Safety Analysis Guidance Document |
| NUREG-1516 | Management of Radioactive Material Safety Programs at Medical Facilities |
| NUREG-1520 | Standard Review Plan for Fuel Cycle Facilities License Applications |
| 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-1530 | Reassessment of NRC's Dollar Per Person-Rem Conversion Factor Policy |
| 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-1538 | Preliminary Performance-Based Analyses Relevant to Dose-Based Performance Measures for Proposed Geologic Repository at Yucca Mountain |
| 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-1573 | A Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities: Recommendations of NRC's Performance Assessment Working Group |
| 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-1600 | General Statement of Policy and Procedure for NRC Enforcement Actions |
| NUREG-1601 | Chemical Process Safety at Fuel Cycle Facilities |
| NUREG-1609 | Standard Review Plan for Transportation Packages for Radioactive Material |
| NUREG-1610 | Controlling the Atom: The Beginnings of Nuclear Regulation 1946-1962 |
| 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-1623 | Design of Erosion Protection for Long-Term Stabilization |
| 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-1668 | NRC Sensitivity and Uncertainty Analyses for a Proposed HLW Repository at Yucca Mountain, Nevada Using TPA 3.1: Conceptual Models and Data |
| NUREG-1669 | A Risk Analysis of Fixed Nuclear Gauges |
| NUREG-1700 | Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans |
| NUREG-1702 | Standard Review Plan for the Review of a License Application for the Tank Waste Remediation System Privatization (TWRS-P) Project |
| 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-1707 | Interagency Steering Committee on Radiation Standards |
| NUREG-1709 | Selection of Sample Rate and Computer Wordlength in Digital Instrumentation and Control Systems |
| NUREG-1710 | History of Water Development: A Literature Review |
| NUREG-1712 | Nuclear Byproduct Material Risk Review |
| 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-1715 | Component Performance Study: 1987-1998 |
| 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-1719 | Pipe Cracking in U.S. BWRs: A Regulatory History |
| 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-1724 | Standard Review Plan for the Review of DOE Plans for Achieving Regulatory Compliance at Sites With Contaminated Ground Water Under Title I of the Uranium Mill Tailings Radiation Control Act |
| NUREG-1725 | Human Interaction with Reused Soil: An Information Search |
| NUREG-1727 | NMSS Decommissioning Standard Review Plan |
| NUREG-1736 | Consolidated Guidance: 10 CFR Part 20 - Standards for Protection Against Radiation |
| NUREG-1737 | Software Quality Assurance Procedures for NRC Thermal Hydraulic Codes |
| 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-1740 | Voltage-Based Alternative Repair Criteria |
| NUREG-1741 | RASCAL 3.0: Description of Models and Methods |
| 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-1744 | Assessment of the TRAC-M Codes Using Flecht-Seaset Reflood and Steam Cooling Data |
| NUREG-1745 | Standard Format and Content for Technical Specifications for 10 CFR Part 72 Cask Certificates of Compliance |
| NUREG-1746 | System-Level Repository Sensitivity Analyses, Using TPA Version 3.2 Code |
| NUREG-1747 | Overview & Summary of NRC Involvement with DOE in Tank Waste Remediation System-Privatization (TWRS-P) Program |
| NUREG-1748 | Environmental Review Guidance for Licensing Actions Associated with NMSS Programs |
| NUREG-1749 | Implications From The Phenomenon Identification and Ranking Tables (PIRTs) and Suggested Research Activities for High Burnup Fuel |
| NUREG-1750 | Assessment of Soil Amplification of Earthquake Ground Motion Using the "CARES" Code Version 1.2 |
| NUREG-1752 | Assessment of Modernization and Integration of BWR Components and Spatial Kinetics in the TRAC-M, Version 3690, Code |
| NUREG-1753 | Risk-Based Performance Indicators: Results of Phase 1 Development |
| NUREG-1754 | A Comparative Analysis of LWR Fuel Designs |
| NUREG-1755 | Some Observations On Risk-Informing Appendices A & B to 10 CFR Part 50 |
| NUREG-1756 | Safety Culture: A Survey of the State-of-the-Art |
| 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-1760 | Aging Assessment of Safety-Related Fuses Used in Low- & Medium-Voltage Applications in Nuclear Power Plants |
| NUREG-1761 | Radiological Surveys for Controlling Release of Solid Materials |
| NUREG-1762 | Integrated Issue Resolution Status Report |
| NUREG-1763 | Differing Professional Views or Opinions: 2002 Special Review Panel 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-1771 | U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes |
| 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-1794 | Loss of Control of Cesium-137 Well Logging Source Resulting in Radiation Exposures to Members of the Public |
| 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-1802 | Role and Direction of Nuclear Regulatory Research |
| 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-1841 | U.S. Operating Experience with Thermally Treated Alloy 690 Steam Generator Tubes |
| 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-1889 | RASCAL 3.0.5 Workbook |
| 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-1905 | Safety Evaluation Report Relating to the License Renewal of James A. FitzPatrick Nuclear Power Plant |
| 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 |
| NUREG-1914 | Dissolution Kinetics of Commercial Spent Nuclear Fuels in the Potential Yucca Mountain Repository Environment |
| NUREG-1915 | Safety Evaluation Report Related to the License Renewal of Wolf Creek Generating Station |
| NUREG-1916 | Safety Evaluation Report Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1 |
| NUREG-1917 | 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-1920 | Safety Evaluation Report Related to the License Renewal of Vogtle Electric Generating Plant, Units 1 and 2 |
| 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 Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel |
| 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-1933 | Containing the Atom: Nuclear Regulation in a Changing Environment, 1963-1971 |
| NUREG-1934 | Nuclear Power Plant Fire Modeling Analysis Guidelines (NPP FIRE MAG) |
| NUREG-1935 | State-of-the-Art Reactor Consequence Analyses (SOARCA) Report |
| 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-1940 | RASCAL 4: Description of Models and Methods |
| 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-1944 | Safety Evaluation Report Related to the License Renewal of Cooper Nuclear Station |
| 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-1948 | Final Safety Evaluation Report: Related to the Aircraft Impact Amendment to the U.S. Advanced Water Reactor (ABWR) Design Certification |
| NUREG-1949 | Safety Evaluation Report Related to Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada |
| 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-1966 | Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design |
| 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 | Final 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-2110 | xLPR Pilot Study Report |
| NUREG-2111 | Final Environmental Impact Statement for Combined Licenses (COLs) for William States Lee III Nuclear Station Units 1 and 2 |
| NUREG-2112 | Public Comment Analysis and Adjudication: Supplement 3 to NUREG-0654/FEMA-REP-1, "Guidance for Protective Action Strategies" |
| NUREG-2113 | Environmental Impact Statement for the Proposed Fluorine Extraction Process and Depleted Uranium Deconversion Plant in Lea County, New Mexico – Final Report |
| NUREG-2114 | Cognitive Basis for Human Reliability Analysis |
| 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-2119 | Mechanical Behavior of Ballooned and Ruptured Cladding |
| NUREG-2120 | Safety Evaluation Report for the General Electric-Hitachi Global Laser Enrichment LLC Laser-Based Uranium Enrichment Plant in Wilmington, North Carolina |
| NUREG-2121 | Fuel Fragmentation, Relocation, and Dispersal During the Loss-of-Coolant Accident |
| NUREG-2122 | Glossary of Risk-Related Terms in Support of Risk-Informed Decisionmaking |
| NUREG-2123 | Safety Evaluation Report Related to the License Renewal of Columbia Generating Station |
| NUREG-2124 | Final Safety Evaluation Report Related to the Combined Licenses for Vogtle Electric Generating Plant, Units 3 and 4 |
| NUREG-2125 | Spent Fuel Transportation Risk Assessment |
| NUREG-2126 | Standard Review Plan for Conventional Uranium Mill and Heap Leach Facilities |
| NUREG-2127 | The International HRA Empirical Study: Lessons Learned from Comparing HRA Methods Predictions to HAMMLAB Simulator Data |
| 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 |
| NUREG-2151 | Early Leak Detection External to Structures at Nuclear Power Plants |
| NUREG-2152 | Computational Fluid Dynamics Best Practice Guidelines for Dry Cask Applications |
| NUREG-2153 | Final Safety Evaluation Report Related to the Combined Licenses for Virgil C. Summer Nuclear Station, Units 2 and 3 |
| NUREG-2154 | Acceptability of Corrective Action Programs for Fuel Cycle Facilities: Draft Report for Comment |
| NUREG-2155 | Implementation Guidance for 10 CFR Part 37, "Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material" |
| NUREG-2156 | The U.S. HRA Empirical Study – Assessment of HRA Method Predictions against Operating Crew Performance on a U.S. Nuclear Power Plant Simulator |
| NUREG-2157 | Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel |
| NUREG-2159 | Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance – Final Report |
| NUREG-2160 | Post-Test Examination Results from Integral, High-Burnup, Fueled LOCA Tests at Studsvik Nuclear Laboratory |
| NUREG-2161 | Consequence Study of a Beyond-Design-Basis Earthquake Affecting the Spent Fuel Pool for a U.S. Mark I Boiling Water Reactor |
| NUREG-2162 | Weld Residual Stress Finite Element Analysis Validation: Part 1 – Data Development Effort |
| NUREG-2163 | Technical Basis for Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule |
| NUREG-2164 | Consolidation of the 1985 Sandia National Laboratories/Factory Mutual Main Control Room and Electrical Cabinet Fire Test Data |
| NUREG-2165 | Safety Culture Common Language |
| NUREG-2166 | Physical Security Best Practices for the Protection of Risk-Significant Radioactive Material |
| NUREG-2168 | Environmental Impact Statement for an Early Site Permit (ESP) at the PSEG Site |
| NUREG-2169 | Nuclear Power Plant Fire Ignition Frequency and Non-Suppression Probability Estimation Using the Updated Fire Events Database: United States Fire Event Experience Through 2009 |
| NUREG-2170 | A Risk-Informed Approach to Understanding Human Error in Radiation Therapy |
| NUREG-2171 | Safety Evaluation Report Related to the License Renewal of Limerick Generating Station, Units 1 and 2 |
| NUREG-2172 | Safety Evaluation Report Related to the License Renewal of Callaway Plant, Unit 1 |
| NUREG-2173 | Tribal Protocol Manual |
| NUREG-2174 | Impact of Variation in Environmental Conditions on the Thermal Performance of Dry Storage Casks |
| NUREG-2175 | Guidance for Conducting Technical Analyses for 10 CFR Part 61 |
| NUREG-2176 | Environmental Impact Statement for Combined Licenses (COLs) for Turkey Point Nuclear Plant Units 6 and 7 |
| NUREG-2178 | Refining And Characterizing Heat Release Rates From Electrical Enclosures During Fire (RACHELLE-FIRE) |
| NUREG-2179 | Environmental Impact Statement for the Combined License (COL) for the Bell Bend Nuclear Power Plant |
| NUREG-2180 | Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities (DELORES-VEWFIRE) |
| NUREG-2181 | Safety Evaluation Report Related to the License Renewal of Sequoyah Nuclear Plant Units 1 and 2 Docket Numbers 50-327 and 50-328 Tennessee Valley Authority |
| NUREG-2182 | Final Safety Evaluation Report for the Combined License for Enrico Fermi 3, Dockett Number 52-033, DTE Electric Company |
| NUREG-2183 | Environmental Impact Statement for the Construction Permit for the SHINE Medical Radioisotope Production Facility |
| NUREG-2184 | Supplement to the U.S. Department of Energy's Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada |
| NUREG-2186 | Compliance Review Guide: Procedural Processes for Conducting Pre-award Compliance Reviews and Post-award Compliance Reviews |
| NUREG-2187 | Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models—Byron Unit 1 |
| NUREG-2188 | U.S. Operating Experience with Thermally Treated Alloy 600 Steam Generator Tubes Through December 2013 |
| NUREG-2189 | Safety Evaluation Report Related to SHINE Medical Technologies, Inc. Construction Permit Application for a Medical Radioisotope Production Facility |
| NUREG-2190 | Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 |
| NUREG-2191 | Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report |
| NUREG-2192 | Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants |
| NUREG-2193 | Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station Docket Number 50-346 FirstEnergy Nuclear Operating Company |
| NUREG-2194 | Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants |
| NUREG-2195 | Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treated Alloy 600 and 690 Steam Generator Tubes |
| NUREG-2196 | BWR ECCS Pump Suction Concerns following a LOCA |
| NUREG-2198 | The General Methodology of an Integrated Human Event Analysis System (IDHEAS-G) |
| NUREG-2199 | An Integrated Human Event Analysis System (IDHEAS) for Nuclear Power Plant Internal Events At-Power Application |
| NUREG-2201 | Probabilistic Risk Assessment and Regulatory Decisionmaking: Some Frequently Asked Questions |
| NUREG-2202 | Safety Evaluation Report – Related to the Early Site Permit Application in the Matter of PSEG Power, LLC and PSEG Nuclear, LLC for the PSEG Early Site Permit Site – Docket No. 52-043 – PSEG Power, LLC and PSEG Nuclear, LLC |
| NUREG-2203 | Glossary of Security Terms for Nuclear Power Reactors |
| NUREG-2205 | Safety Evaluation Report, Related to the License Renewal of LaSalle County Station, Units 1 and 2, Docket Nos. 50-373 and 50-374, Exelon Generation Company, LLC |
| NUREG-2206 | Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Reactors with Mark I and Mark II Containments |
| NUREG-2208 | Validation of Computational Fluid Dynamics Methods Using Prototypic Light Water Reactor Spent Fuel Assembly Thermal-Hydraulic Data |
| NUREG-2209 | Environmental Impact Statement for Construction Permit for the Northwest Medical Isotopes Radioisotope Production Facility |
| NUREG-2210 | Safety Evaluation Report: Related to the License Renewal of Fermi 2, Docket Number 50-341, DTE Electric Company |
| NUREG-2211 | Safety Evaluation Report: Related to the License Renewal of Grand Gulf Nuclear Station, Unit 1, Docket Number 50-416, Entergy Operations, Inc. |
| NUREG-2212 | Standard Review Plan for Applications for 10 CFR Part 70 Licenses for Possession and Use of Special Nuclear Materials of Critical Mass but Not Subject to the Requirements in 10 CFR Part 70, Subpart H – Draft Report for Comment |
| NUREG-2213 | Updated Implementation Guidelines for SSHAC Hazard Studies |
| NUREG-2214 | Managing Aging Processes In Storage (MAPS) Report |
| NUREG-2215 | Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities |
| NUREG-2216 | Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material |
| NUREG-2218 | An International Phenomena Identification and Ranking Table (PIRT) Expert Elicitation Exercise for High Energy Arcing Faults (HEAFs) |
| NUREG-2220 | Agency Financial Report |
| NUREG-2221 | Technical Bases for Changes in the Subsequent License Renewal Guidance Documents NUREG–2191 and NUREG–2192 |
| NUREG-2222 | Disposition of Public Comments on the Draft Subsequent License Renewal Guidance Documents NUREG–2191 and NUREG–2192 |
| NUREG-2223 | Safety Evaluation Report: Related to the License Renewal of South Texas Project Units 1 and 2, Docket Nos. 50-498 and 50-499, South Texas Project Nuclear Operating Company |
| NUREG-2224 | Dry Storage and Transportation of High Burnup Spent Nuclear Fuel |
| NUREG-2225 | Basis for the Treatment of Potential Common-Cause Failure in the Significance Determination Process |
| NUREG-2226 | Environmental Impact Statement for an Early Site Permit (ESP) at the Clinch River Nuclear Site |
| NUREG-2228 | Weld Residual Stress Finite Element Analysis Validation: Part II—Proposed Validation Procedure |
| NUREG-2229 | Safety Evaluation Report: Northwest Medical Isotopes, LLC Construction Permit Application for a Radioisotope Production Facility |
| NUREG-2230 | Methodology for Modeling Fire Growth and Suppression Response for Electrical Cabinet Fires in Nuclear Power Plants |
| NUREG-2232 | Heat Release Rate and Fire Characteristics of Fuels Representative of Typical Transient Fire Events in Nuclear Power Plants |
| NUREG-2233 | Methodology for Modeling Transient Fires in Nuclear Power Plant Fire Probabilistic Risk Assessment |
| NUREG-2236 | Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Plant Analysis Risk Models–Duane Arnold |
| NUREG-2237 | Environmental Impact Statement for the Holtec International's License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico – Final Report |
| NUREG-2238 | Validation of a Computational Fluid Dynamics Method Using Vertical Dry Cask Simulator Data |
| NUREG-2239 | Environmental Impact Statement for Interim Storage Partners LLC's License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas – Final Report |
| NUREG-2240 | Flood Penetration Seal Testing Protocol Research |
| NUREG-2242 | Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 – Final Report |
| NUREG-2243 | Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in McKinley County, New Mexico – Final Report |
| NUREG-2244 | HABIT 2.2 Description of Models and Methods |
| NUREG-2245 | Technical Review of the 2017 Edition of ASME Code, Section III, Division 5, "High Temperature Reactors" |
| NUREG-2246 | Fuel Qualification for Advanced Reactors |
| NUREG-2247 | Extremely Low Probability of Rupture Version 2 Probabilistic Fracture Mechanics Code |
| NUREG-2248 | Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina |
| NUREG-2249 | Generic Environmental Impact Statement for Licensing of New Nuclear Reactors – Final Report |
| NUREG-2250 | Annual Evaluation Plan |
| NUREG-2251 | Capacity Assessment: For Statistics, Research, Evaluation, and Other Analysis |
| NUREG-2252 | Evidence Building Plan |
| NUREG-2254 | Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project |
| NUREG-2255 | Guidance for Conducting Expert Elicitation in Risk-Informed Decisionmaking Activities |
| NUREG-2256 | Integrated Human Event Analysis System for Event and Condition Assessment (IDHEAS-ECA) |
| NUREG-2261 | Artificial Intelligence Strategic Plan: Fiscal Years 2023-2027 |
| NUREG-2262 | High Energy Arcing Fault Frequency and Consequence Modeling – Final Report |
| NUREG-2263 | Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor – Final Report |
| NUREG-2264 | Weapons Safety Assessment |
| NUREG-2266 | Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels – Final Report |
| NUREG-2267 | NRCDose3 Code, Version 1.1.4: User Guide and Technical Manual |
| NUREG-2268 | Environmental Impact Statement for the Construction Permit Application for Kemmerer Power Station Unit 1 |
| NUREG-2271 | Guidelines for Preparing and Reviewing Applications Under 10 CFR Part 57 — Draft Report for Comment |
Page Last Reviewed/Updated Friday, May 01, 2026
Page Last Reviewed/Updated Friday, May 01, 2026