Division 1, 4, and 8 Regulatory Guides PotentiallySubject to Updatein Support of Options to Revise RadiationProtection Regulations and Guidance
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The U.S. Nuclear Regulatory Commission (NRC) is currently considering Options to Revise Radiation Protection Regulations and Guidance to achieve greater alignment with the 2007 Recommendations of the International Commission on Radiological Protection (ICRP Publication 103). [The NRC's Synopsis of ICRP Publication 103, which is available through the Agencywide Documents Access and Management System (ADAMS), discusses the broad implications of the new recommendations.] Specifically, the revisions proposed to achieve alignment would affect the regulatory framework provided by Title 10, Part 20, of the Code of Federal Regulations (10 CFR Part 20), "Standards for Protection Against Radiation"; 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities"; and Appendix I to 10 CFR Part 50, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low as is Reasonably Achievable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents." If the agency determines that such revisions are appropriate and scientifically justified, the staff would also update the agency's related regulatory guidance. For the specific regulatory guides that are potentially subject to update, see the following topics on this page:
Division 1 Regulatory Guides
| Guide Number |
Title |
| 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. |
| 1.23 |
Onsite Meteorological Programs. |
| 1.68 |
Initial Test Programs for Water-Cooled Nuclear Power Plants. |
| 1.70 |
Standard Format and Content Safety Analysis Reports for Nuclear Power Plants (LWR Edition). |
| 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, draft for comment, March 1976. |
| 1.111 |
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Rev. 1, draft for comment, July 1977. |
| 1.112 |
Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Nuclear Power Reactors. |
| 1.113 |
Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I. |
| 1.206 |
Combined License Applications for Nuclear Power Plants (LWR Edition). |
Division 4 Regulatory Guides
| Guide Number |
Title |
| 4.1 |
Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants. |
| 4.2 |
Preparation of Environmental Reports for Nuclear Power Stations. |
| 4.2, Supp. 1 |
Preparation of Supplemental Environmental Reports for Applications To Renew Nuclear Power Plant Operating Licenses. |
| 4.15, Rev. 2 |
Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) - Effluent Streams and the Environment, Rev. 2. |
| 4.15, Rev. 1 |
Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, Rev. 1. |
| 4.21 |
Minimization of Contamination and Radioactive Waste Generation – Life Cycle Planning, draft 2008. |
Division 8 Regulatory Guides
| Guide Number |
Title |
| 8.2 |
Guide for Administrative Practices in Radiation Monitoring |
| 8.4 |
Direct-Reading and Indirect-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 |
| 8.9 |
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 |
| 8.11 |
Applications of Bioassay for Uranium |
| 8.13 |
Instruction Concerning Prenatal Radiation Exposure |
| 8.15 |
Acceptable Programs for Respiratory Protection |
| 8.18 |
Information Relevant to Ensuring that Occupational Radiation Exposures at Medical Institutions Will Be as Low as Reasonably Achievable |
| 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 |
| 8.21 |
Health Physics Surveys for Byproduct Material at NRC-Licensed Processing and Manufacturing Plants |
| 8.22 |
Bioassay at Uranium Mills |
| 8.23 |
Radiation Safety Surveys at Medical Institutions |
| 8.24 |
Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication |
| 8.25 |
Air Sampling in the Workplace |
| 8.26 |
Applications of Bioassay for Fission and Activation Products |
| 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 |
| 8.30 |
Health Physics Surveys in Uranium Recovery Facilities |
| 8.31 |
Information Relevant to Ensuring that Occupational Radiation Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable |
| 8.32 |
Criteria for Establishing a Tritium Bioassay Program |
| 8.33 |
Quality Management Program |
| 8.34 |
Monitoring Criteria and Methods To Calculate Occupational Radiation Doses |
| 8.35 |
Planned Special Exposures |
| 8.36 |
Radiation Dose to the Embryo/Fetus |
| 8.37 |
ALARA Levels for Effluents from Materials Facilities |
| 8.38 |
Control of Access to High and Very High Radiation Areas of Nuclear Plants |
| 8.39 |
Release of Patients Administered Radioactive Materials |