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 |