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:
r 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 references to the latest versions of the XOQDOQ, LADTAP II (as LADTAP), and GASPAR II (as GASPAR) computer codes in the updated NRCDose3 computer code which are reflected in a NUREG for the NRCDose3 Code User Guide and Technical Manual included in the installation program and proposes to reflect these conforming changes in the RG update for licensee and applicant use. This RG update would also incorporate references to coding corrections and published errata, non-human biota dose calculations from gaseous effluents, and new reactor licensing lessons learned. An expanded radionuclide listing with ICRP-2, ICRP-26, ICRP-30, and ICRP-72 dose factors and recent parameter values which are available for use in the NRCDose3 code would be reflected in revised RG 1.109 tables. In addition, the staff will be adding a discussion with equations to assess the recreational boating and swimming exposure pathway from liquid effluents. - 2 - 2. What is the impact on internal and external stakeholders of not updating the RG for the known issues, in terms of anticipated numbers of licensing and inspection activities over the next several years? The primary use of this RG is for reactor licensing and implementing operational programs. There is little or no impact on internal or external stakeholders of not updating RG 1.109, Revision 1, for large light-water reactors (LWRs) since the staff is not expecting any applications in the near future; instead, small modular reactor (SMR) and advanced reactor design applications are anticipated. As with large LWRs, the proposed RG update would also provide guidance to assess exposure pathway doses for SMR and advanced reactor designs. In general, the calculation models, assumptions, parameter values, and methods for assessing the exposure pathway