Books by U. S. Nuclear Commission
Environmental Impact Statement
Environmental Impact Statement for Construction Permit for the Northwest Medical Isotopes Radioisotope Production Facilit
10 CFR Part 52 Construction In
10 CFR Part 52 Construction Inspection Program Framework Document
Accident Source Terms for Ligh
Accident Source Terms for Light-Water Nuclear Power Plants
Aging Assessment of Safety-Rel
Aging Assessment of Safety-Related Fuses Used in Low-And Medium-Voltage Application in Nuclear Power Plants
Assessment of Current Test Met
Assessment of Current Test Methods for Post-LOCA Cladding Behavior
Background, Status, and Issues
Background, Status, and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Facilities
CFD Analysis of Full-Scale Ste
CFD Analysis of Full-Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident
Computational Benchmark for Es
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit
Computational Fluid Dynamics A
Computational Fluid Dynamics Analysis of Natural Circulation Flows in a Pressurized-Water Reactor Loop under Severe Accident Conditions
Confirmatory Battery Testing
Confirmatory Battery Testing
Consolidated Decommissioning G
Consolidated Decommissioning Guidance
Consolidated Decommissioning G
Consolidated Decommissioning Guidance Characterization, Survey, and Determination of Radiological Criteria
Consolidated Guidance about Ma
Consolidated Guidance about Materials Licenses : Guidance about Administrative Licensing Procedures
Criteria for Preparation and E
Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants Guidance for Protective Action Strategies
Cross Section Generation Guide
Cross Section Generation Guidelines for Trace-Parcs
Design Control in Pursuit of E
Design Control in Pursuit of Engineering Excellence
Electric Raceway Fire Barrier
Electric Raceway Fire Barrier Systems in U. S. Nuclear Power Plants
Emergency Preparedness Signifi
Emergency Preparedness Significance Quantification Process
Enterprise Content Management
Enterprise Content Management Streamlining How Staff and Stakeholders Work Within the Nuclear Regulatory Commission?s Regulatory Environment
Environmental Impact Statement
Environmental Impact Statement for an Early Site Permit at the Exelon ESP Site
Environmental Impact Statement
Environmental Impact Statement for the Dewey-Burdock Project in Custer and Fall River Countries, South Dakota
Environmental Impact Statement
Environmental Impact Statement on the Construction and Operation of a Proposed Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South Carolina
Environmental Impact Statement
Environmental Impact Statements for License Renewal of the National Bureau of Standards Reactor
Environmental Review Guidance
Environmental Review Guidance for Licensing Actions Associated with NMSS Programs
Estimating Loss-Of-Coolant Acc
Estimating Loss-Of-Coolant Accident Frequencies Through the Elicitation Process
Estimating Loss-Of-Coolant Acc
Estimating Loss-Of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process Appendices a Through M
Event Report Guidelines 10 CFR
Event Report Guidelines 10 CFR 50. 72 and 50. 73
Feasibility Study for a Risk-I
Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing
Final Safety Evaluation Report
Final Safety Evaluation Report on the Construction Authorization Request for the Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South Carolina
Final Supplemental Environment
Final Supplemental Environmental Impact Statement for Combined Licenses for Vogtle Electric Generating Plant Units 3 and 4
Fire Dynamics Tools Quantitat
Fire Dynamics Tools Quantitative Fire Hazard Analysis Methods for the U. S. Nuclear Regulatory Commission Fire Protection Inspection Program
Fiscal Year 2009 Performance a
Fiscal Year 2009 Performance and Accountability Report
Fiscal Year 2011
Fiscal Year 2011
Foundation for the Adequacy of
Foundation for the Adequacy of the Licensing Bases
Functional Capability of Pipin
Functional Capability of Piping Systems
Generic Aging Lessons Learned
Generic Aging Lessons Learned (GALL) Report
Generic Environmental Impact S
Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 38
Good Practices for Implementin
Good Practices for Implementing Human Reliability Analysis
Guidance for Assessing Exempti
Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50. 54(m)
Guidance for the Review of Cha
Guidance for the Review of Changes to Human Actions Final Report
Independent Verification of th
Independent Verification of the Mitigating Systems Performance Index (MSPI) Results for the Pilot Plants
Information Technology/Informa
Information Technology/Information Management
Interagency Steering Committee
Interagency Steering Committee on Multimedia Environmental Models
Lessons Learned from Early Imp
Lessons Learned from Early Implementation of the Maintenance Rule at Nine Nuclear Power Plants
Loss of Control of Cesium-137
Loss of Control of Cesium-137 Well Logging Source Resulting in Radiation Exposures to Members of the Public
Multi-Agency Radiation Survey
Multi-Agency Radiation Survey and Assessment of Materials and Equipment Manual (MARSAME)
Nonparametric Statistical Meth
Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys
NRC Staff Guidance for Activit
NRC Staff Guidance for Activities Related to U. S. Departments of Energy Waste Determinations
Nuclear Power Plant Fire Model
Nuclear Power Plant Fire Modeling Analysis Guidelines
Nuclear Power Plant Fire Prote
Nuclear Power Plant Fire Protection Research Program
Nuclear Regulatory Legislation
Nuclear Regulatory Legislation 112th Congress; 2nd Session
NUREG, Volume 9, February 2013
NUREG, Volume 9, February 2013
Occupational Radiation Exposur
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2011
Operator Licensing Examiner St
Operator Licensing Examiner Standards for Research and Test Reactors
Phenomena Identification and R
Phenomena Identification and Ranking Table Evaluation of Chemical Effects Associated with Generic Safety Issue 191
Probabilistic Fracture Mechani
Probabilistic Fracture Mechanics - Models, Parameters, and Uncertainty Treatment Used in Favor Version 04. 1
Procedural and Submittal Guida
Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities
Proceedings of the Advisory Co
Proceedings of the Advisory Committee on Nuclear Waste
Proceedings of the Cybersecuri
Proceedings of the Cybersecurity in Cyber-Physical Systems Workshop, April 23-24 2012
Proceedings of the Nuclear Fue
Proceedings of the Nuclear Fuels Sessions of the 2004 Nuclear Safety Research Conference
Proposed Risk Management Regul
Proposed Risk Management Regulatory Framework
Public Information Circular fo
Public Information Circular for Shipments of Irradiated Reactor Fuel
RASCAL 3. 0. 5
RASCAL 3. 0. 5
Regulatory Effectiveness Asses
Regulatory Effectiveness Assessment of Generic Issue 43 and Generic Letter 88-14
Reliability of Ultrasonic in-S
Reliability of Ultrasonic in-Service Inspection of Welds in Reactor Internals of Boiling Water Reactors
Report to Congress on Abnormal
Report to Congress on Abnormal Occurrences
Report to Congress on the Secu
Report to Congress on the Security Inspection Program for Commercial Power Reactor and Category I Fuel Cycle Facilities : Results and Status Update
Report to Congress on the Secu
Report to Congress on the Security Inspection Program for Commercial Power Reactors and Category 1 Fuel Cycle Facilities : Results and Status Update
Resolution of Generic Safety I
Resolution of Generic Safety Issue 188
Review and Prioritization of T
Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel
Safety Evaluation Report for a
Safety Evaluation Report for an Early Site Permit (ESP) at the North Anna ESP Site
Safety Evaluation Report for the National Enrichment Facility in Lea County, New Mexico
Safety Evaluation Report Relat
Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 And 2
Safety Evaluation Report Relat
Safety Evaluation Report Related to the License Renewal of Oyster Creek Generation Staton
Safety Evaluation Report Relat
Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant
Safety Evaluation Report Relat
Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station
Safety Evaluation Report Relat
Safety Evaluation Report Related to the License Renewal of Vogtle Electric Generating Plant, Unit 1 And 2
Sensitivity Studies of the Pro
Sensitivity Studies of the Probabilistic Fracture Mechanics Model Used in FAVOR
Some Observations on Risk-Info
Some Observations on Risk-Informing Appendices a&B to 10 CFR Part 50
Spent Fuel Transportation Risk
Spent Fuel Transportation Risk Assessment
Staff Responses to Frequently
Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Plants
Standard Review Plan for Dry C
Standard Review Plan for Dry Cask Storage Systems
Standard Review Plan for Relea
Standard Review Plan for Releasing Part of a Reactor Facility or Site for Unrestricted Use Before Approval of the License Termination Plan
Standard Review Plan for Renew
Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance
Standard Review Plan for Spent
Standard Review Plan for Spent Fuel Dry Storage Facilities
Standard Review Plan for Spent
Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility
Standard Review Plan for the R
Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility
Standard Review Plan for Trans
Standard Review Plan for Transportation Packages for MOX Spent Nuclear Fuel
Standard Review Plan for Trans
Standard Review Plan for Transportation Packages for Radioactive Material
Status of the Decommissioning
Status of the Decommissioning Program, 2008 Annual Report
Technical Review of Risk-Infor
Technical Review of Risk-Informed Performance-Based Methods for Nuclear Power Plant Fire Protection Analyses
U. S. Plant Experience with Al
U. S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials
United States National Climate
United States National Climate Assessment
United States of America Fifth
United States of America Fifth National Report for the Convention on Nuclear Safety
United States of America Fourt
United States of America Fourth National Report for the Convention on Nuclear Safety
United States of America Natio
United States of America National Report for the 2012 Convention on Nuclear Safety Extraordinary Meeting
United States of America Natio
United States of America National Report for the Convention of Nuclear Safety
Verification and Validation of
Verification and Validation of Selected Fire Models for Nuclear Power Plant Application
Verification and Validation of
Verification and Validation of Selected Fire Models for Nuclear Power Plant Application : Volume 7
Verification and Validation of
Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications
United States of America Fourt
United States of America Fourth National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Knowledge Base for Post-Fire S
Knowledge Base for Post-Fire Safe-Shutdown Analysis
Fitness for Duty in the Nuclea
Fitness for Duty in the Nuclear Power Industry