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:
tal body doses, and organ doses (based on International Commission on Radiation Protection (ICRP)-2, “Report of Committee II on Permissible Dose for Internal Radiation,” issued 1959 (Ref. 36)); 2. effluent discharges only (excludes direct radiation from the facility and ISFSIs); Rev. 2 of RG 1.21, Page 28 3. current annual period (excludes accumulated radioactivity from prior-year effluents); and 4. unrestricted area (excludes individuals in the restricted areas and controlled areas). When calculating air doses licensees should assure that for any location outside the site boundary doses do not exceed the 10 CFR 50 Appendix I design objectives. Calculation of air dose at the site boundary would assure the most conservative calculation of air doses for ground-level releases. This may not be true for elevated releases. Licensees should select a location that assures the most conservative calculation of air dose. 5.5 10 CFR 20.1301(a) through (c) This regulation specifies dose limits for members of the public from licensed operation of the facility. These limits apply to doses resulting from licensed and unlicensed radioactive material and from radiation sources other than background radiation (see 10 CFR 20.1001, “Purpose”). Demonstration of compliance with the limits of 40 CFR Part 190 will be considered to also demonstrate compliance with the 0.1 rem total effective dose equivalent limit of 10 CFR 20.1301(a) (Ref. 37). 5.6 10 CFR 20.1301(e) For those facilities subject to EPA’s generally applicable environmental radiation standards promulgated in 40 CFR Part 190, licensees must assess the highest cumulative (whole body and organ) doses from the uranium fuel cycle to a real individual outside the site boundary. The limits include (1) contributions from current-year effluents, (2) current-year direct radiation from the facility, and (3) accumulated radioactivity from prior-year effluents that are not already included in items 1 and 2. These requirements