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# Safety Evaluation Report Related to the Operation of Browns Ferry, Units 1 and 2, Following the March 22, 1975 Fire (NUREG-0061)

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          - 10 CFR Part 52 Construction Inspection Program Framework Document (NUREG-1789)
          - A Classification System for Radioactive Waste Disposal – What Waste Goes Where? (NUREG-0456, FBDU-22
          - A Comparative Analysis of LWR Fuel Designs (NUREG-1754)
          - A Compilation of Reports of The Advisory Committee on Nuclear Waste (NUREG-1423)
          - A Compilation of Reports of The Advisory Committee on Reactor Safeguards (NUREG-1125)
          - A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning 
          - A Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities: Recommenda
          - A Pilot Probabilistic Risk Assessment of a Dry Cask Storage System at a Nuclear Power Plant (NUREG-1
          - A Proposed Risk Management Regulatory Framework (NUREG-2150)
          - A Risk Analysis of Fixed Nuclear Gauges (NUREG-1669)
          - A Risk-Informed Approach to Understanding Human Error in Radiation Therapy  (NUREG-2170)
          - 2002
          - Acceptability of Corrective Action Programs for Fuel Cycle Facilities: Draft Report for Comment (NUR
          - Acceptable Standard Format and Content for Fundamental Nuclear Material Control (FNMC) Plan Required
          - Access Control Systems: Technical Information for NRC Licensees (NUREG-1964)
          - Accident Source Terms for Light-Water Nuclear Power Plants (NUREG-1465)
          - Agency Financial Report (NUREG-2220)
          - Age-Specific Radiation Dose Commitment Factors for a one-year Chronic Year (NUREG-0172)
          - Aging Assessment of Safety-Related Fuses Used in Low- & Medium-Voltage Applications in Nuclear Power
          - Aging Management of Nuclear Power Plant Containments for License Renewal (NUREG-1611)
          - An Integrated Human Event Analysis System (IDHEAS) for Nuclear Power Plant Internal Events At-Power 
          - An International Phenomena Identification and Ranking Table (PIRT) Expert Elicitation Exercise for H
          - Analysis of Public Comments on the Improved License Renewal Guidance Documents (NUREG-1739)
          - Analysis of Public Comments on the Revised License Renewal Guidance Documents (NUREG-1832)
          - Analysis of Ultimate Heat Sink Cooling Ponds (NUREG-0693)
          - Analysis of Ultimate-Heat-Sink Spray Ponds (NUREG-0733)
          - Annual Safeguards Summary Event List (SSEL) (NUREG-0525)
          - Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regula
          - APEX-AP1000 Confirmatory Testing To Support AP1000 Design Certification (Non-Proprietary) (NUREG-182
          - Applying Statistics (NUREG-1475, Revision 1)
          - Assessment of Modernization and Integration of BWR Components and Spatial Kinetics in the TRAC-M, Ve
          - Assessment of Soil Amplification of Earthquake Ground Motion Using the "CARES" Code Version 1.2 (NUR
          - Assessment of the TRAC-M Codes Using Flecht-Seaset Reflood and Steam Cooling Data (NUREG-1744)
          - Asymmetric Blowdown Loads on PWR Primary Systems – Resolution of Generic Task Action Plan A-2 (NUREG
          - ATHEANA User's Guide (NUREG-1880)
          - Backfitting Guidelines (NUREG-1409)
          - Background as a Residual Radioactivity Criterion for Decommissioning: Appendix A to the Draft Generi
          - Background, Status, and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Faci
          - Basis Document for Large Early Release Frequency (LERF) Significance Determination Process (SDP): In
          - Basis for the Treatment of Potential Common-Cause Failure in the Significance Determination Process 
          - Branch Technical Position on the Use of Expert Elicitation in the High-Level Radioactive Waste Progr
          - BWR ECCS Pump Suction Concerns following a LOCA (NUREG-2196)
          - NUREG-0017
          - Central and Eastern United States Seismic Source Characterization for Nuclear Facilities (NUREG-2115
          - CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident (NUREG-
          - CFD Analysis of Full-Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident (NUREG-1
          - Characterization of Radioactive Slags (NUREG-1703)
          - Clarification of TMI Action Plan Requirements (NUREG-0737)
          - Cognitive Basis for Human Reliability Analysis (NUREG-2114)
          - Collection of Abbreviations (NUREG-0544, Revision 5)
          - Compliance Review Guide: Procedural Processes for Conducting Pre-award Compliance Reviews and Post-a
          - Component Performance Study: 1987-1998  (NUREG-1715)
          - Computational Fluid Dynamics Analysis of Natural Circulation Flows in a Pressurized-Water Reactor Lo
          - Computational Fluid Dynamics Best Practice Guidelines for Dry Cask Applications: Final Report (NUREG
          - Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Pla
          - Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Pla
          - Consequence Study of a Beyond-Design-Basis Earthquake Affecting the Spent Fuel Pool for a U.S. Mark 
          - Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treate
          - Consolidated Decommissioning Guidance (NUREG-1757)
          - Consolidated Guidance About Materials Licenses (NUREG-1556)
          - Consolidated Guidance: 10 CFR Part 20 — Standards for Protection Against Radiation (NUREG-1736)
          - Consolidation of the 1985 Sandia National Laboratories/Factory Mutual Main Control Room and Electric
          - Control of Heavy Loads at Nuclear Power Plants: Resolution of Generic Technical Activity A-36 (NUREG
          - NUREG-0654
          - Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire (NUREG-
          - Design Control in Pursuit of Engineering Excellence: A Quick Reference Guide for NRC Inspectors (NUR
          - Design of Erosion Protection for Long-Term Stabilization (NUREG-1623, Final Report)
          - Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detect
          - Development of a Pressure Drop Calculation Method for Debris-Covered Sump Screens in Support of Gene
          - 2002
          - Directory of Certificates of Compliance for Radioactive Materials Packages (NUREG-0383)
          - Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Docum
          - Disposition of Public Comments on the Draft Subsequent License Renewal Guidance Documents NUREG–2191
          - Dissolution Kinetics of Commercial Spent Nuclear Fuels in the Potential Yucca Mountain Repository En
          - Draft Environmental Impact Statement on 10 CFR Part 61 Licensing Requirements for Land Disposal of R
          - Dry Storage and Transportation of High Burnup Spent Nuclear Fuel – Final Report (NUREG-2224)
          - Early Leak Detection External to Structures at Nuclear Power Plants (NUREG-2151)
          - Electric Raceway Fire Barrier Systems in U.S. Nuclear Power Plants — Final Report (NUREG-1924)
          - Electrical Cable Test Results and Analysis During Fire Exposure (ELECTRA-FIRE), A Consolidation of T
          - Enforcement Actions: Significant Actions Resolved Individual Actions Semiannual Progress Report July
          - Enterprise Content Management: Streamlining How Staff and Stakeholders Work within the Nuclear Regul
          - Environmental Impact Statement for an Early  Site Permit (ESP) at the Exelon ESP Site (NUREG-1815)
          - Environmental Impact Statement for an Early Site Permit (ESP) at the Clinch River Nuclear Site: Fina
          - Environmental Impact Statement for an Early Site Permit (ESP) at the Grand Gulf ESP Site (NUREG-1817
          - Environmental Impact Statement for an Early Site Permit (ESP) at the North Anna ESP Site (NUREG-1811
          - Environmental Impact Statement for an Early Site Permit (ESP) at the PSEG Site, Final Report (NUREG-
          - Environmental Impact Statement for Combined Licenses (COLs) for South Texas Project Electric Generat
          - Environmental Impact Statement for Combined Licenses (COLs) for Turkey Point Nuclear Plant Units 6 a
          - Environmental Impact Statement for Construction Permit for the Northwest Medical Isotopes Radioisoto
          - Environmental Impact Statement for License Renewal of the National Bureau of Standards Reactor (NURE
          - Environmental Impact Statement for the Combined License (COL) for the Bell Bend Nuclear Power Plant 
          - NUREG-2183
          - Environmental Impact Statement for the Proposed American Centrifuge Plant in Piketon, Ohio (NUREG-18
          - Environmental Impact Statement for the Proposed Eagle Rock Enrichment Facility in Bonneville County,
          - Environmental Impact Statement for the Proposed Fluorine Extraction Process and Depleted Uranium Dec
          - Environmental Impact Statement for the Proposed GE-Hitachi Global Laser Enrichment, LLC Facility in 
          - Environmental Impact Statement for the Proposed Idaho Spent Fuel Facility at the Idaho National Engi
          - Environmental Impact Statement for the Proposed National Enrichment Facility in Lea County, New Mexi
          - Environmental Impact Statement for the Reclamation of the Sequoyah Fuels Corporation Site in Gore, O
          - Environmental Impact Statement on the Construction and Operation of a Mixed Oxide Fuel Fabrication F
          - Environmental Monitoring of Low-Level Radioactive Waste Disposal Facility (NUREG-1388)
          - Environmental Review Guidance for Licensing Actions Associated with NMSS Programs (NUREG-1748)
          - Environmental Survey of the Reprocessing and Waste Management Portion of the LWR Fuel Cycle: A Task 
          - EPRI/NRC-RES Fire Human Reliability Analysis Guidelines – Final Report (NUREG-1921)
          - Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process (NUREG-1829)
          - Evaluating Igneous Activity at Yucca Mountain: Technical Basis for Decisionmaking (NUREG-1890)
          - Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray Fires (NUREG-1758)
          - Evaluation of Human Reliability Analysis Methods Against Good Practices (NUREG-1842)
          - Event Reporting Guidelines: 10 CFR 50.72 and 50.73 (NUREG-1022)
          - Fault Tree Handbook (NUREG-0492)
          - FAVOR Code Versions 2.4 and 3.1 Verification and Validation Summary Report (NUREG-1795)
          - Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Li
          - Final Environmental Impact Statement for the Construction and Operation of an Independent Spent Fuel
          - Final Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle ESP Electric Gener
          - Final Environmental Impact Statement for Combined License (COL) for Enrico Fermi Unit 3 (NUREG-2105)
          - Final Environmental Impact Statement for Combined Licenses (COLs) for Comanche Peak Nuclear Power Pl
          - Final Environmental Impact Statement for Combined Licenses (COLs) for Levy Nuclear Plant Units 1 and
          - Final Environmental Impact Statement for Combined Licenses (COLs) for William States Lee III Nuclear
          - Final Environmental Impact Statement for Combined Licenses for Virgil C. Summer Nuclear Station, Uni
          - Final Environmental Impact Statement for the Combined License (COL) for Calvert Cliffs Nuclear Power
          - Final Environmental Impact Statement on 10 CFR Part 61 Licensing Requirements for Land Disposal of R
          - Final Environmental Statement: Related to the Operation of Watts Bar Nuclear Plant, Unit 2 (NUREG-04
          - Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities (NUREG-0586)
          - Final Safety Evaluation Report for the Combined License for Enrico Fermi 3, Dockett Number 52-033, D
          - Final Safety Evaluation Report on the Construction Authorization Request for the Mixed Oxide Fuel Fa
          - Final Safety Evaluation Report Related to Certification of the AP600 Standard Design (NUREG-1512)
          - Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water
          - Final Safety Evaluation Report Related to the Combined Licenses for Virgil C. Summer Nuclear Station
          - Final Safety Evaluation Report Related to the Combined Licenses for Vogtle Electric Generating Plant
          - Final Safety Evaluation Report: Related to the Aircraft Impact Amendment to the U.S. Advanced Boilin
          - Final Supplemental Environmental Impact Statement for Combined License (COLs) for Vogtle Electric Ge
          - Fire Barrier Penetration Seals in Nuclear Power Plants (NUREG-1552)
          - Fire Dynamics Tools (FDTs) – Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulato
          - Fire Protection Action Plan: Status Summary Report, Volume 1, No. 1  (NUREG-0298)
          - Foundation for the Adequacy of the Licensing Bases – A Supplement to the Statement of Considerations
          - Frequently Asked Questions on License Renewal of Nuclear Power Reactors (NUREG-1850)
          - Fuel Fragmentation, Relocation, and Dispersal During the Loss-of-Coolant Accident (NUREG-2121)
          - Functional Capability of Piping Systems (NUREG-1367)
          - Functional Criteria for Emergency Response Facilities (NUREG-0696)
          - General Statement of Policy and Procedure for NRC Enforcement Actions (NUREG-1600)
          - Generic  Environmental Impact Statement for License Renewal of Nuclear Plants  (NUREG-1437)
          - Generic Adversary Characteristics Summary Report (NUREG-0459)
          - Generic Aging Lessons Learned (GALL) Report  (NUREG-1801)
          - Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report  (NUREG-2191)
          - Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel (NUREG-2157)
          - Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (NUREG-1910)
          - Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License
          - Glossary of Risk-Related Terms in Support of Risk-Informed Decisionmaking (NUREG-2122)
          - Good Practices for Implementing Human Reliability Analysis (HRA) (NUREG-1792)
          - Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Re
          - Guidance for Conducting Technical Analyses for 10 CFR Part 61, Draft Report for Comment (NUREG-2175)
          - Guidance for the Review of Changes to Human Actions (NUREG-1764)
          - Guidance on the Implementation of Integrated Safety Analysis Requirements for 10 CFR Part 40 Facilit
          - Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making (NU
          - NUREG-1482
          - Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors (NUREG-1
          - History and Framework of Commercial Low-Level Radioactive Waste Management in the United States: ACN
          - History of Water Development: A Literature Review (NUREG-1710)
          - Human Factors Engineering Program Review Model (NUREG-0711, Revision 3)
          - Human Interaction with Reused Soil: An Information Search (NUREG-1725)
          - Human-System Interface Design Review Guidelines (NUREG-0700)
          - Impact of Variation in Environmental Conditions on the Thermal Performance of Dry Storage Casks, Fin
          - Implementation Guidance for 10 CFR Part 37, "Physical Protection of Category 1 and Category 2 Quanti
          - Implications From The Phenomenon Identification and Ranking Tables (PIRTs) and Suggested Research Ac
          - Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants i
          - Improving Quality and the Assurance of Quality  in the Design and Construction of Nuclear Power Plan
          - Independent Verification of the Mitigating Systems Performance Index (MSPI) Results for the Pilot Pl
          - Individual Plant Examination: Submittal Guidance  (NUREG-1335)
          - Information Digest, 2022–2023 (NUREG-1350, Volume 34)
          - Information on the Confinement Capability of the Facility Disposal Area at West Valley, New York (NU
          - Information Technology/Information Management Strategic Plan (NUREG-1908)
          - Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restraints (
          - Integrated Issue Resolution Status Report (NUREG-1762)
          - Integrated Safety Analysis Guidance Document (NUREG-1513)
          - Interagency Steering Committee on Radiation Standards (ISCORS) (NUREG-1707)
          - Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment (NUREG-
          - Intrusion Detection Systems and Subsystems: Technical Information for NRC Licensees (NUREG-1959, Rev
          - ISCORS Assessment of Radioactivity in Sewage Sludge: Modeling to Assess Radiation Doses  (NUREG-1783
          - ISCORS Assessment of Radioactivity in Sewage Sludge: Radiological Survey Results and Analysis (NUREG
          - Joint Canada - United States Guide for Approval of Type B(U) and Fissile Material Transportation Pac
          - Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling-Water Reactors (
          - Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors (NUREG-112
          - Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (NUREG
          - NUREG-2103
          - Knowledge Base for Post-Fire Safe-Shutdown Analysis - Draft Report for Comment (NUREG-1778)
          - Lessons Learned from Early Implementation of The Maintenance Rule at Nine Nuclear Power Plants (NURE
          - Lessons Learned From Maintenance Rule Baseline Inspections (NUREG-1648)
          - 2002
          - Licensee Contractor and Vendor Inspection Status Report – Quarterly Report (NUREG-0040)
          - Loss of Control of Cesium-137 Well Logging Source Resulting in Radiation Exposures to Members of the
          - Management of Radioactive Material Safety Programs at Medical Facilities (NUREG-1516)
          - Managing Aging Processes In Storage (MAPS) Report: Final Report (NUREG-2214)
          - Mechanical Behavior of Ballooned and Ruptured Cladding (NUREG-2119)
          - Methodology for Combining Dynamic Responses (NUREG-0484, Revision 1)
          - Methodology for Developing and Implementing Alternative Temperature-Time Curves for Testing the Fire
          - Methodology for Evaluation of Emergency Response Facilities (NUREG-0814)
          - Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 
          - Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (NUREG-1575)
          - Multi-Agency Radiological Laboratory Analytical Protocols Manual (NUREG-1576)
          - NMSS Decommissioning Standard Review Plan (NUREG-1727)
          - NRC Comprehensive Records Disposition Schedule (NUREG-0910, Revision 4)
          - NRC Editorial Style Guide (NUREG-1379, Revision 3)
          - NRC Periodic Compliance Monitoring Report for U.S. Department of Energy Non-High-Level Waste Disposa
          - NRC Regulatory Agenda: Semiannual Report (NUREG-0936)
          - NRC Sensitivity and Uncertainty Analyses for a Proposed HLW Repository at Yucca   Mountain, Nevada U
          - NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations - Draft 
          - Nuclear Byproduct Material Risk Review (NUREG-1712, Final Report)
          - Nuclear Power Plant Fire Ignition Frequency and Non-Suppression Probability Estimation Using the Upd
          - Nuclear Power Plant Fire Modeling Analysis Guidelines (NPP FIRE MAG) — Final Report (NUREG-1934, EPR
          - Nuclear Power Plant Fire Protection Research Program (NUREG-1148)
          - Nuclear Regulatory Commission Issuances (NUREG-0750)
          - Nuclear Regulatory Commission Staff Computer Programs for Use with Meteorological Data (NUREG-0917)
          - Nuclear Regulatory Legislation: 113th Congress (NUREG-0980)
          - 2010
          - NUREG-0713
          - Office of Investigations Annual Report (NUREG-1830)
          - Office of the Inspector General Semiannual Report to Congress (NUREG-1415)
          - Offsite Dose Calculation Manual Guidance:  Standard Radiological Effluent Controls for Boiling Water
          - Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Wa
          - Operating Experience Assessment — Effects of Grid Events on Nuclear Power Plant Performance (NUREG-1
          - Operating Experience Feedback Reports (NUREG-1275)
          - Operator Licensing Examination Standards for Power Reactors (NUREG-1021)
          - Operator Licensing Examiner Standards for Research and Test Reactors (NUREG-1478, Revision 2)
          - Overview & Summary of NRC Involvement with DOE in Tank Waste Remediation System-Privatization (TWRS-
          - Peer Review of GSI-191 Chemical Effects Research Program (NUREG-1861)
          - Performance and Accountability Report (NUREG-1542)
          - Performance Budget/Congressional Budget Justification (NUREG-1100)
          - Perspectives Gained From the Individual Plant Examination of External Events (IPEEE) Program (NUREG-
          - Phenomena Identification and Ranking Table Evaluation of Chemical Effects Associated with Generic Sa
          - Physical Protection of Shipments of Irradiated Reactor Fuel: Final Report (NUREG-0561, Revision 2)
          - Physical Security Best Practices for the Protection of Risk-Significant Radioactive Material (NUREG-
          - Pipe Cracking in U.S. BWRs: A Regulatory History (NUREG-1719)
          - Planning  Basis for the Development of State and Local Government Radiological Emergency  Response P
          - Plans and Schedules for Implementation of U.S. Nuclear Regulatory Commission Responsibilities under 
          - Post-Test Examination Results from Integral, High-Burnup, Fueled LOCA Tests at Studsvik Nuclear Labo
          - Practical Implementation Guidelines for SSHAC Level 3 and 4 Hazard Studies (NUREG-2117, Revision 1)
          - Preliminary Performance-Based Analyses Relevant to Dose-Based Performance Measures for Proposed Geol
          - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance M
          - Preparing NUREG-Series Publications, Revision 2 (NUREG-0650)
          - Probabilistic Fracture Mechanics — Models, Parameters, and Uncertainty Treatment Used in FAVOR Versi
          - Probabilistic Risk Assessment and Regulatory Decisionmaking: Some Frequently Asked Questions (NUREG-
          - Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) fo
          - Public Comment Analysis and Adjudication: Supplement 3 to NUREG-0654/FEMA-REP-1, "Guidance for Prote
          - Public Information Circular For Shipments of Irradiated Reactor Fuel (NUREG-0725,  Revision 15)
          - Quality Assurance Guidance for a Low-Level Radioactive Waste Disposal Facility (NUREG-1293, Revision
          - Radiological Assessments for Clearance of  Materials from Nuclear Facilities (NUREG-1640)
          - Radiological Surveys for Controlling Release of Solid Materials – Draft Report for Comment  (NUREG-1
          - RASCAL 3.0.5 Workbook (NUREG-1889)
          - RASCAL 3.0.5: Description of Models and Methods (NUREG-1887)
          - RASCAL 3.0: Description of Models and Methods (NUREG-1741)
          - RASCAL 4.0: Description of Models and Methods
          - Reactor Oversight Process (NUREG-1649, Revision 6)
          - Reactor Pressure Vessel Status Report (NUREG-1511, Supplement 2)
          - Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants [NUREG
          - Reassessment of NRC's Dollar Per Person-Rem Conversion Factor Policy (NUREG-1530)
          - Recommendations Related to Browns Ferry Fire (NUREG-0050)
          - Recommended Screening Limits for Pressurized Thermal Shock (PTS) (NUREG-1874)
          - Re-Evaluation of the Indoor Resuspension Factor for the Screening Analysis of the Building Occupancy
          - Refining And Characterizing Heat Release Rates From Electrical Enclosures During Fire (RACHELLE-FIRE
          - Regulatory Analysis for the Resolution of Generic Issue 57: Effects of Fire Protection System Actuat
          - Regulatory Analysis for the Resolution of Generic Safety Issue 106: Piping and the Use of Highly Com
          - Regulatory Effectiveness Assessment of Generic Issue 43 and Generic Letter 88-14 (NUREG-1837)
          - Regulatory Effectiveness Assessment of Option B of Appendix J (NUREG-1777)
          - Regulatory Effectiveness of the Anticipated Transient Without Scram Rule (NUREG-1780)
          - Regulatory Effectiveness of the Station Blackout Rule (NUREG-1776)
          - Remarks Presented (Questions/Answers Discussed) at Public Regional Meetings to Discuss Regulations (
          - Report of the U.S. Nuclear Regulatory Commission Piping Review Committee (NUREG-1061, Volume 4)
          - Report on the Accident at the Chernobyl Nuclear Power Station (NUREG-1250)
          - NUREG-1307
          - Report to Congress on Abnormal Occurrences (NUREG-0090)
          - NUREG-1885
          - Research Activities (NUREG-1925)
          - Resolution of Generic Safety Issue 188: Steam  Generator Tube Leaks or Ruptures Concurrent with Cont
          - Review and Evaluation of the Nuclear Regulatory Commission Safety Research Program: A Report to the 
          - 2003
          - Review Process for Low-Level Radioactive Waste Disposal License Application Under Low-Level Radioact
          - Risk-Based Performance Indicators: Results of Phase 1 Development (NUREG-1753)
          - Role and Direction of Nuclear Regulatory Research (NUREG-1802)
          - Safety Evaluation Report Related to the License Renewal of Hope Creek Generating Station (NUREG-2102
          - Safety  Evaluation Report Related to the License Renewal of Salem Nuclear Generating  Station  (NURE
          - Safety Culture Common Language (NUREG-2165)
          - Safety Culture: A Survey of the State-of-the-Art (NUREG-1756)
          - Safety Evaluation of Early Site Permit Application in the Matter of System Energy Resources, Inc., a
          - Safety Evaluation Report – Related to the Early Site Permit Application in the Matter of PSEG Power,
          - Safety Evaluation Report Related to the License Renewal of Three Mile Island Nuclear Station, Unit 1
          - Safety Evaluation Report for an Early Site Permit (ESP) at the Exelon Generation Company, LLC (EGC) 
          - Safety Evaluation Report for an Early Site Permit (ESP) at the North Anna ESP Site (NUREG-1835)
          - Safety Evaluation Report for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant (VEG
          - Safety Evaluation Report for the American Centrifuge Plant in Piketon, Ohio (NUREG-1851)
          - Safety Evaluation Report for the Eagle Rock Enrichment Facility in Bonneville County, Idaho (NUREG-1
          - Safety Evaluation Report for the General Electric-Hitachi Global Laser Enrichment LLC Laser-Based Ur
          - Safety Evaluation Report for the International Isotopes Fluorine Products, Inc. Fluorine Extraction 
          - Safety Evaluation Report for the National Enrichment Facility in Lea County, New Mexico, Louisiana E
          - Safety Evaluation Report Related to Disposal of High-Level Radioactive Wastes in a Geologic Reposito
          - Safety Evaluation Report Related to SHINE Medical Technologies, Inc. Construction Permit Application
          - Safety Evaluation Report Related to the  License Renewal of H.B. Robinson Steam Electric Plant, Unit
          - Safety Evaluation Report Related to the  License Renewal of R.E. Ginna Nuclear Power Plant (NUREG-17
          - Safety Evaluation Report Related to the  License Renewal of the Edwin I. Hatch Nuclear Plant, Units 
          - Safety Evaluation Report Related to the License Renewal of Arkansas Nuclear One, Unit 1 (NUREG-1743)
          - Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 
          - Safety Evaluation Report Related to the License Renewal of Callaway Plant, Unit 1 (NUREG-2172)
          - Safety Evaluation Report Related to the License Renewal of Calvert Cliffs Nuclear Power Plant, Units
          - Safety Evaluation Report Related to the License Renewal of Columbia Generating Station (NUREG-2123)
          - Safety Evaluation Report Related to the License Renewal of Cooper Nuclear Station (NUREG-1944)
          - Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station Docket 
          - Safety Evaluation Report Related to the License Renewal of Duane Arnold Energy Center (NUREG-1955)
          - Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos.
          - Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station: Docket No. 50-305
          - Safety Evaluation Report Related to the License Renewal of Limerick Generating Station, Units 1 and 
          - Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2, a
          - Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 
          - Safety Evaluation Report Related to the License Renewal of North Anna Power Station, Units 1 and 2, 
          - Safety Evaluation Report Related to the License Renewal of Oconee Nuclear Station, Units 1, 2, and 3
          - Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station (NUREG-18
          - Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant (NUREG-1871)
          - Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Un
          - Safety Evaluation Report Related to the License Renewal of Peach Bottom Atomic Power Station, Units 
          - Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station (NUREG-1891
          - Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plant U
          - Safety Evaluation Report Related to the License Renewal of Sequoyah Nuclear Plant Units 1 and 2 Dock
          - Safety Evaluation Report Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 
          - Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2 (N
          - Safety Evaluation Report Related to the License Renewal of Susquehanna Steam Electric Station, Units
          - Safety Evaluation Report Related to the License Renewal of the Arkansas Nuclear One, Unit 2 (NUREG-1
          - Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 
          - Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units
          - Safety Evaluation Report Related to the License Renewal of the Donald C. Cook Nuclear Plant, Units 1
          - Safety Evaluation Report Related to the License Renewal of the Dresden Nuclear Power Station, Units 
          - Safety Evaluation Report Related to the License Renewal of the Fort Calhoun Station, Unit 1 (NUREG-1
          - Safety Evaluation Report Related to the License Renewal of the Joseph M. Farley Nuclear Plant, Units
          - Safety Evaluation Report Related to the License Renewal of the Millstone Power Station, Units 2 and 
          - Safety Evaluation Report Related to the License Renewal of the Monticello Nuclear Generating Plant (
          - Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 an
          - Safety Evaluation Report Related to the License Renewal of the Virgil C. Summer Nuclear Station (NUR
          - Safety Evaluation Report Related to the License Renewal of Turkey Point Nuclear Plant, Units 3 and 4
          - Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station (NUR
          - Safety Evaluation Report Related to the License Renewal of Vogtle Electric Generating Plant, Units 1
          - Safety Evaluation Report Related to the License Renewal of Wolf Creek Generating Station (NUREG-1915
          - Safety Evaluation Report Related to the Operation of Browns Ferry, Units 1 and 2, Following the Marc
          - Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Units 1 and 2 (NUREG-0
          - Safety Evaluation Report Relating to the License Renewal of James A. FitzPatrick   Nuclear Power Pla
          - Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidw
          - Safety Evaluation Report, Related to the License Renewal of LaSalle County Station, Units 1 and 2, D
          - Safety Evaluation Report: Related to the License Renewal of Fermi 2, Docket Number 50-341, DTE Elect
          - Safety Evaluation Report: Related to the License Renewal of Grand Gulf Nuclear Station, Unit 1, Dock
          - Seismic Considerations for the Transition Break Size (NUREG-1903)
          - Selection of Sample Rate and Computer Wordlength in Digital Instrumentation and Control Systems (NUR
          - Sensitivity Studies of the Probabilistic Fracture Mechanics Model Used in FAVOR (NUREG-1808)
          - Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants (NUREG-1150)
          - Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the   United States (NUREG-14
          - Site Suitability, Selection and Characterization: Branch Technical Position — Low-Level Radioactive 
          - Software Quality Assurance Procedures for NRC Thermal Hydraulic Codes (NUREG-1737)
          - Some Observations On Risk-Informing Appendices A & B to 10 CFR Part 50 (NUREG-1755)
          - Spent Fuel Transportation Risk Assessment – Final Report (NUREG-2125)
          - Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Reactors (
          - Standard Format and Content Acceptance Criteria for the Material Control and Accounting (MC&A) Refor
          - Standard Format and Content for Technical Specifications for 10 CFR Part 72 Cask Certificates of Com
          - Standard Format and Content of a License Application for a Low-Level Radioactive Waste Disposal Faci
          - Standard Review Plan for Conventional Uranium Mill and Heap Leach Facilities — Draft Report for Comm
          - Standard Review Plan for Decommissioning Cost Estimates for Nuclear Power Reactors (NUREG-1713)
          - Standard Review Plan for Dry Cask Storage Systems (NUREG-1536)
          - Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans (NUREG-1700, Rev
          - Standard Review Plan for Fuel Cycle Facilities License Applications (NUREG-1520)
          - Standard Review Plan for In Situ Leach Uranium Extraction License Applications (NUREG-1569)
          - Standard Review Plan for Releasing Part of a Reactor Facility or Site for Unrestricted Use Before Ap
          - Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage
          - Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (NUREG-1800
          - NUREG-2192
          - Standard Review Plan for Spent Fuel Dry Storage Facilities (NUREG-1567)
          - Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities - Final Report (NUREG-2215)
          - Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material: Final Repo
          - Standard Review Plan for the review of a license application for a Low-Level Radioactive Waste Dispo
          - Standard Review Plan for the Review of a License Application for the Tank Waste Remediation System P
          - Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings Sites Under Title II of 
          - Standard Review Plan for the Review of an Application for a Mixed Oxide (MOX) Fuel Fabrication Facil
          - Standard Review Plan for the Review of DOE Plans for Achieving Regulatory Compliance at Sites With C
          - NUREG-0800
          - Standard Review Plan for Transportation Packages for Radioactive Material (NUREG-1609)
          - Standard Review Plan for Transportation Packages for Spent Nuclear Fuel (NUREG-1617)
          - Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding 
          - Standard Review Plan on Transfer and Amendment of Antitrust License Conditions and Antitrust Enforce
          - Standard Review Plans for Environmental Reviews for Nuclear Power Plants: Environmental Standard Rev
          - Standard Technical Specifications — Babcock and Wilcox  Plants (NUREG-1430,  Revision 5)
          - Standard Technical Specifications — Combustion Engineering Plants (NUREG-1432, Revision 5)
          - Standard Technical Specifications — General Electric Plants (BWR/4) (NUREG-1433, Revision 5)
          - Standard Technical Specifications – General Electric BWR/6 Plants (NUREG-1434, Revision 5)
          - Standard Technical Specifications – Westinghouse Plants (NUREG-1431, Revision 5)
          - Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants (NUREG-2194)
          - State-of-the-Art Reactor Consequence Analyses (SOARCA) Report (NUREG-1935)
          - Status of the Decommissioning Program (NUREG-1814)
          - Strategic Plan (NUREG-1614)
          - Summary and Analysis of Public Comments Received on Proposed Revisions to 10 CFR Part 26 – Fitness f
          - Supplement to the U.S. Department of Energy's Environmental Impact Statement for a Geologic Reposito
          - Supplemental Environmental Impact Statement for the Combined License (COL) for North Anna Power Stat
          - Suppression Pool Temperature Limits for BWR Containments (Generic Technical Activity A-39) (NUREG-07
          - Systematic Radiological Assessment of Exemptions for Source and Byproduct Materials (NUREG-1717)
          - System-Level Repository Sensitivity Analyses, Using TPA Version 3.2 Code (NUREG-1746)
          - Technical Bases for Changes in the Subsequent License Renewal Guidance Documents NUREG–2191 and NURE
          - Technical Bases for Revision to the License Renewal Guidance Documents (NUREG-1833)
          - Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA) (NU
          - Technical Basis for Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule, Final Repor
          - Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule 
          - Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Re
          - Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Reposit
          - Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Reposit
          - Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain Reposit
          - Technical Review of Risk-Informed, Performance-Based Methods for Nuclear Power Plant Fire Protection
          - Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants (NUREG-1738
          - The International HRA Empirical Study: Lessons Learned from Comparing HRA Methods Predictions to HAM
          - The U.S. HRA Empirical Study – Assessment of HRA Method Predictions against Operating Crew Performan
          - The U.S. Nuclear Regulatory Commission's External Complaint Processing and Investigation Procedures 
          - NUREG-1650
          - TMI-2 Lessons Learned Task Force Final Report (NUREG-0585)
          - Training Review Criteria and Procedures (NUREG-1220, Revision 1)
          - Tribal Protocol Manual (NUREG-2173, Revision 1)
          - U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes (NUREG-1771)
          - U.S. Operating Experience with Thermally Treated Alloy 600 Steam Generator Tubes Through December 20
          - U.S. Operating Experience with Thermally Treated Alloy 690 Steam Generator Tubes  (NUREG-1841)
          - U.S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressu
          - United States Nuclear Regulatory Commission Package Performance Study Test Protocols - Draft Report 
          - United States Nuclear Regulatory Commission Staff Practice and Procedure Digest: Commission, Appeal 
          - Updated Implementation Guidelines for SSHAC Hazard Studies (NUREG-2213)
          - Validation of Computational Fluid Dynamics Methods Using Prototypic Light Water Reactor Spent Fuel A
          - Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications (NUREG-1824
          - Voltage-Based Alternative Repair Criteria (NUREG-1740)
          - Weld Residual Stress Finite Element Analysis Validation: Part 1 – Data Development Effort (NUREG-216
          - Weld Residual Stress Finite Element Analysis Validation: Part II—Proposed Validation Procedure – Dra
          - xLPR Pilot Study Report (NUREG-2110)
          - Yucca Mountain Review Plan (NUREG-1804, Revision 2)
          - Toxic Vapor Concentrations in the Control Room Following a Postulated Accidental Release (NUREG-0570
          - Office of the Inspector General Semiannual Report to Congress (NUREG-1415, Volume 33, No. 2)
          - Safety Evaluation Report: Related to the License Renewal of South Texas Project Units 1 and 2, Docke
          - Safety Evaluation Report: Related to the License Renewal of South Texas Project Units 1 and 2, Docke
          - Safety Evaluation Report: Related to the License Renewal of South Texas Project Units 1 and 2, Docke
          - Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants
          - Safety Evaluation Report: Northwest Medical Isotopes, LLC Construction Permit Application for a Radi
          - Methodology for Modeling Fire Growth and Suppression Response for Electrical Cabinet Fires in Nuclea
          - Heat Release Rate and Fire Characteristics of Fuels Representative of Typical Transient Fire Events 
          - Environmental Impact Statement for Interim Storage Partners LLC's License Application for a Consolid
          - NUREG-2237
          - Methodology for Modeling Transient Fires in Nuclear Power Plant Fire Probabilistic Risk Assessment (
          - Final Safety Evaluation Report: Related to the Certification of the Advanced Boiling Water Reactor D
          - Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Pla
          - Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill
          - Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 – Final Report (NUREG-2242)
          - HABIT 2.2 Description of Models and Methods (NUREG-2244)
          - The General Methodology of An Integrated Human Event Analysis System (IDHEAS-G) (NUREG-2198)
          - Fuel Qualification for Advanced Reactors, Final (NUREG-2246)
          - Environmental Impact Statement for the License Renewal of  the Columbia Fuel Fabrication Facility in
          - Controlling the Atom: The Beginnings of Nuclear Regulation 1946-1962 (NUREG-1610) 
          - Containing the Atom: Nuclear Regulation in a Changing Environment, 1963-1971 (NUREG-1933)
          - Technical Review of the 2017 Edition of ASME Code, Section III, Division 5, "High Temperature Reacto
          - Extremely Low Probability of Rupture Version 2 Probabilistic Fracture Mechanics Code (NUREG-2247)
          - Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required fo
          - Flood Penetration Seal Testing Protocol Research (NUREG-2240)
          - Annual Evaluation Plan (NUREG-2250)
          - Capacity Assessment: For Statistics, Research, Evaluation, and Other Analysis (NUREG-2251)
          - Evidence Building Plan (NUREG-2252)
          - Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary P
          - Artificial Intelligence Strategic Plan: Fiscal Years 2023-2027  (NUREG-2261)
          - Emergency Response Data System (NUREG-1394, Revision 2)
          - Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor – Fina
          -  Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project (
          - Integrated Human Event Analysis System for Event and Condition Assessment (IDHEAS-ECA) (NUREG-2256)
          - Glossary of Security Terms for Nuclear Power Reactors (NUREG-2203)
          - Standard Review Plan for Applications for 10 CFR Part 70 Licenses for Possession and Use of Special 
          - Weapons Safety Assessment (NUREG-2264)
          - High Energy Arcing Fault Frequency and Consequence Modeling – Final Report (NUREG-2262, EPRI 3002025
          - Resolution of Generic Safety Issue 29: Bolting Degradation or Failure in Nuclear Power Plants (NUREG
          - Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Leve
          - An Alternative Format for Category I Fuel Cycle Facility Physical Protection Plans (NUREG-1456)
          - Acceptance Criteria for the Evaluation of Category I Fuel Cycle Facility Physical Security Plans (NU
          - NRC Program for the Resolution of Generic Issues Related to Nuclear Power Plants (NUREG-0410)

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