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:
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Regulatory Guides
| Document Number | Description |
|---|---|
| 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 |
| 1.21 | Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants |
| 1.33 | Quality Assurance Program Requirements (Operation) |
| 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 |
| 1.69 | Concrete Radiation Shields for Nuclear Power Plants |
| 1.97 | Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants |
| 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 |
| 1.140 | Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants |
| 1.143 | Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants |
| 1.183 | Alternative Radiological Source Terms for Evaluating Design-Basis Accidents at Nuclear Power Reactors |
| 1.206 | Combined License Applications for Nuclear Power Plants |
| 4.15 | Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) — Effluent Streams and the Environment |
| 8.2 | Guide for Administrative Practices in Radiation Monitoring |
| 8.4 | Direct Reading and Indirect Reading Pocket Dosimeters |
| 8.6 | Standard Test Procedures for Geiger-Muller Counters |
| 8.8 | Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable |
| 8.9 | Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program |
| 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 |
| 8.20 | Applications of Bioassay for I-125 and I-131 |
| 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 |
| 8.32 | Criteria for Establishing a Tritium Bioassay Program |
| 8.34 | Monitoring Criteria and Methods To Calculate Occupational Radiation Doses |
| 8.35 | Planned Special Exposures |
| 8.36 | Radiation Doses to Embryo/Fetus |
| 8.38 | Control of Access to High and Very High Radiation Areas of Nuclear Plants |
NUREG-Series Publications
| Document Number | Description |
|---|---|
| 0041 | Manual of Respiratory Protection Against Airborne Radioactive Materials |
| 0737 | Clarification of TMI Action Plan Requirements |
| 1430 | Standard Technical Specifications Babcock and Wilcox Plants |
| 1431 | Standard Technical Specifications Westinghouse Plants |
| 1432 | Standard Technical Specifications Combustion Engineering Plants |
| 1433 | Standard Technical Specifications General Electric Plants, BWR/4 |
| 1434 | Standard Technical Specifications General Electric Plants, BWR/6 |
| 1736 | Consolidated Guidance: 10 CFR Part 20 — Standards for Protection Against Radiation |
