United States Nuclear Regulatory Commission - Protecting People and the Environment

Guidance Regarding Radiation Protection for New Reactors

The U.S. Nuclear Regulatory Commission (NRC) issues regulatory guides to describe (to licensees, applicants, and the public) methods that the staff considers acceptable for use in implementing specific parts of the agency’s regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide data that the staff needs in its review of applications for permits or licenses. Regulatory guides are not substitutes for regulations, and compliance with regulatory guides is not required.

In addition, the NRC provides guidance to licensees and applicants by issuing NUREG-series publications regarding regulatory decisions, research results, results of incident investigations, and other technical and administrative information. NUREG-series publications disseminate scientific, technical, and administrative information dealing with licensing and regulation of civilian nuclear facilities and materials. Publications in the NUREG series may neither state nor imply any regulatory requirements, since such requirements are stated only in laws, regulations, licenses (including technical specifications), or orders. In other words, the NRC staff may suggest a course of action in a NUREG-series publication, but the regulated community may use other approaches to satisfy the agency’s regulatory requirements.

For NRC guidance regarding radiation protection for new reactors, see the following topics on this page:

For guidance not listed on this page, refer to the SRPs provided on the Regulations and Standard Review Plan Concerning Radiation Protection for New Reactors.

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Regulatory Guides

See NRC Regulatory Guides for more general information.

Guide Guide Number Description
1.1 - 1.20 1.3 Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling-Water Reactors
1.4 Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors
1.7 Control of Combustible Gas Concentrations in Containment
1.8 Qualification and Training of Personnel for Nuclear Power Plants
1.11 Instrument Lines Penetrating Primary Reactor Containment
1.21 - 1.40 1.21 Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste
1.24 Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure
1.33 Quality Assurance Program Requirements (Operation)
1.41 - 1.60 1.45 Guidance on Monitoring and Responding to Reactor Coolant System Leakage
1.52 Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
1.54 Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants
1.61 - 1.80 1.68 Initial Test Programs for Water-Cooled Nuclear Power Plants
1.69 Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants
1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)
1.81 - 1.100 1.89 Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants
1.97 Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants
1.98 Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor
1.101 - 1.120 1.101 Emergency Planning and Preparedness for Nuclear Power Reactors
1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I
1.110 Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors
1.111 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors
1.112 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors
1.113 Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I
1.121 - 1.140 1.140 Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
1.141 - 1.160 1.143 Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants
1.151 Instrument Sensing Lines
1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants
1.181 - 1.200 1.183 Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
1.187 Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments
1.189 Fire Protection for Nuclear Power Plants
1.201 - 1.221 1.205 Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants
1.206 Combined License Applications for Nuclear Power Plants (LWR Edition)
1.215 Guidance for ITAAC Closure Under 10 CFR Part 52
4.1 - 4.20 4.1 Radiological Environmental Monitoring for Nuclear Power Plants
4.8 Environmental Technical Specifications for Nuclear Power Plants
4.15 Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment
4.21 - 4.22 4.21 Minimization of Contamination and Radioactive Waste Generation: Life-Cycle Planning
4.22 Decommissioning Planning During Operations
8.1 - 8.20 8.2 Guide for Administrative Practices in Radiation Monitoring
8.4 Personnel Monitoring Device—Direct-Reading Pocket Dosimeters
8.7 Instructions for Recording and Reporting Occupational Radiation Exposure Data
8.8 Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable
8.10 Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as Is Reasonably Achievable
8.13 Instruction Concerning Prenatal Radiation Exposure
8.15 Acceptable Programs for Respiratory Protection
8.19 Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants -- Design Stage Man-Rem Estimates
8.21 - 8.40 8.25 Air Sampling in the Workplace
8.27 Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants
8.28 Audible-Alarm Dosimeters
8.29 Instruction Concerning Risks from Occupational Radiation Exposure
8.34 Monitoring Criteria and Methods To Calculate Occupational Radiation Doses
8.35 Planned Special Exposures
8.36 Radiation Dose to the Embryo/Fetus
8.38 Control of Access to High and Very High Radiation Areas of Nuclear Plants
8.40 Methods for Measuring Effective Dose Equivalent from External Exposure

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NUREG-Series Publications

See NUREG-Series Publications for more general information.

Document Number Description
NUREG-0016 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors
NUREG-0017 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors: PWR-GALE Code
NUREG-0133 Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications
NUREG-0543 Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)
NUREG-0718 Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses
NUREG-0731 Guidelines for Utility Management and Technical Resources
NUREG-0737 Clarification of TMI Action Plan Requirements
NUREG-0800 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition
NUREG-0933 Resolution of Generic Safety Issues (Formerly entitled "A Prioritization of Generic Safety Issues")
NUREG-0938 Information for Establishing Bioassay Measurements and Evaluation of Tritium Exposure
NUREG-1242 NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document, Evolutionary Designs and Passive Plant Designs
NUREG-1301 Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors
NUREG-1302 Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors
NUREG-1394 Emergency Response Data System (ERDS) Implementation.
NUREG-1418 Characteristics of Low-Level Waste Disposed During 1987 Through 1989
NUREG-1430 Standard Technical Specifications - Babcock and Wilcox Plants
NUREG-1431 Standard Technical Specifications - Westinghouse Plants
NUREG-1432 Standard Technical Specifications - Combustion Engineering Plants
NUREG-1433 Standard Technical Specifications - General Electric Plants (BWR/4)
NUREG-1434 Standard Technical Specifications - General Electric Plants (BWR/6)
NUREG-1736 Consolidated Guidance: 10 CFR Part 20 - Standards for Protection Against Radiation
NUREG/BR-0204 Instructions for Completing NRC's Uniform Low-Level Radioactive Waste Manifest
NUREG/CR-0041 Manual of Respiratory Protection Against Airborne Radioactive Material
NUREG/CR-2731 An Evaluation of the Safety Aspects of the Design and Operation of Temporary/Mobile Radioactive Waste Solidification Systems
NUREG/CR-3587 Identification and Evaluation of Facilitation Techniques for Decommissioning Light Water Power Reactors
NUREG/CR-4013 LADTAP II: Technical Reference and User Guide
NUREG/CR-4062 Extended Storage of Low-Level Radioactive Wastes: Potential Problem Areas
NUREG/CR-4601 Technical Considerations Affecting Preparation of Ion-Exchange Resins for Disposal
NUREG/CR-4653 GASPAR II: Technical Reference and User Guide
NUREG/CR-6147 Characterization of Class A Low-Level Radioactive Waste 1986-1990, (seven volume report)

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Page Last Reviewed/Updated Monday, October 19, 2015