Document: NRC Regulatory Guide
Document ID: ea8957a4-4db4-4bf0-8198-a667b7e5aa29
Document Type: regulatory_guide
Title: 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 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2111/ML21111A005.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.109
CFR Part: 
CFR Title: 

Content:
NAME MRahimi MFranovich (Greg Bowman /RA/ for) DATE 4/30/2021 5/03/2021 OFFICIAL RECORD COPY Enclosure REGULATORY GUIDE PERIODIC REVIEW Regulatory Guide Number: 1.109, Revision 1 Title: Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix I Office/division/branch: NRR/DRA/ARCB Technical Lead: Richard Clement Staff Action Decided: Revise 1. What are the known technical or regulatory issues with the current version of the Regulatory Guide (RG)? This RG, issued in 1977, provides an acceptable method to calculate radiation doses from normal routine radioactive effluents from licensed nuclear power plant operations under annual average environmental conditions. This RG also demonstrates compliance with the design objectives specified in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix I, “Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion As Low As is Reasonably Achievable (ALARA) for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.” However, as this RG has not been updated since 1977, several improvements could be made. The dose methodology and terminology used in RG 1.109, Revision 1, and the ALARA design objectives in 10 CFR Part 50, Appendix I, are based on recommendations from the International Commission on Radiological Protection (ICRP) Publication 2 (ICRP-2), “Permissible Dose for Internal Radiation,” issued in 1959. However, 10 CFR Part 20, “Standards for Protection Against Radiation,” revised in 1991, is based on ICRP-26, “The System of Dose Limitation,” issued in 1977, and the ICRP-30 series, “Limits for Intakes of Radionuclides by Workers,” issued from 1979 through 1988. The ICRP-2 dose assessment methodology is not directly comparable with ICRP-26 and ICRP-30. As such, the staff has incorporated