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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)

File	Title	Date
Supplement 1	Safety Evaluation Report Supporting Operation After the Restoration and Modification of the Browns Ferry Nuclear Plant, Units 1 and 2, Following the March 22, 1975 Fire	June 1976
Initial Report	Safety Evaluation for Operations of Browns Ferry, Units 1 and 2, Following the March 22, 1975 Fire	March 1976

Page Last Reviewed/Updated Tuesday, July 20, 2021

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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)
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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)
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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
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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)
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Development of a Pressure Drop Calculation Method for Debris-Covered Sump Screens in Support of Gene
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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
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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
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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)
NRCDose3 Code, Version 1.1.4: User Guide and Technical Manual (NUREG-2267)
Chemical Process Safety at Fuel Cycle Facilities (NUREG-1601)

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Page Last Reviewed/Updated Tuesday, July 20, 2021

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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