Document: NRC Regulatory Guide
Document ID: 96baa826-d3bb-478b-8f38-e74500f6d433
Document Type: regulatory_guide
Title: 06/2009 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0911/ML091170109.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.21
CFR Part: 
CFR Title: 

Content:
NTRODUCTION This guide describes methods the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for use: (1) in measuring, evaluating, and reporting plant-related radioactivity (excluding background radiation) in effluents and solid radioactive waste shipments from NRC licensed facilities, (2) in assessing and reporting the public dose from facility operations, and (3) on complying with 40 CFR 190 in accordance with the requirements of 10 CFR 20.1301(e). This guide incorporates the risk-informed principles of the Reactor Oversight Process. A risk- informed, performance-based approach to regulatory decision-making combines the “risk-informed” and “performance-based” elements discussed in the staff requirements memorandum on SECY-98-144, “White Paper on Risk-Informed and Performance-Based Regulation,” dated March 1, 1999 (Ref. 1). The following regulations and design criteria establish the regulatory basis for the radiological effluent control program: 1. Title 10 of the Code of Federal Regulations (10 CFR) Section 20.1501, “Surveys” (Ref. 2), Rev. 2 of RG 1.21, Page 2 2. 10 CFR 50.36a, “Technical Specifications on Effluents from Nuclear Power Reactors” (Ref. 3), 3. 10 CFR 20.1302, “Compliance with Dose Limits for Individual Members of the Public,” 4. 10 CFR 72.44(d), “License Conditions” (Ref. 4), 5. Section IV.B of Appendix I, “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,” to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 6. General Design Criterion 60, “Control of releases of radioactive materials to the environment,” of Appendix A, “General Design Criteria for Nuclear Power Plants,” to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), “Domestic Licensing of Production