Document: NRC Regulatory Guide
Document ID: 6b0b3fb5-ff2d-4827-ba5b-d3630cb3303e
Document Type: regulatory_guide
Title: Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2106/ML21069A237.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.112
CFR Part: 
CFR Title: 

Content:
ORY GUIDE 1.112 DATED: DISTRIBUTION: Z. Gran, NRR K. Hsueh, NRR M. Franovich, NRR H. Karagiannis, RES ADAMS Accession No: ML21069A237 NRR-106 OFFICE NRR/DRA/ARCB NRR/DRA/ARCB: BC NRR/DRA: D NAME ZGran KHsueh MFranovich DATE 03/11/21 03/12/21 03/16/21 OFFICIAL RECORD COPY Regulatory Guide Number: 1.112, Revision 1 Title: Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Nuclear Power Reactors Office/division/branch: NRR/DRA/ARCB Technical Lead: Zachary Gran Staff Action Decided: Reviewed with issues identified for future consideration 1. What are the known technical or regulatory issues with the current version of the Regulatory Guide? This RG endorses the American National Standards Institute (ANSI)/American Nuclear Society (ANSI) ANSI/ANS-18.1-1999, “Radioactive Source Term for Normal Operation for Light Water Reactors.” In 2016, the ANSI/ANS-18.1 standard was updated with new source terms for large light water reactors (LWRs). The NRC has not yet endorsed the ANSI/ANS-18.1-2016 standard and could possibly do so in a proposed RG update following the staff’s review. In addition to the updated source terms provided in ANSI/ANS-18.1-2016, the staff expects to gain new reactor licensing lessons learned on a proposed alternate method for source term development from the small modular reactor (SMR) Design Certification Application (DCA) currently under review. This proposed alternative method is used in lieu of the NRC endorsed GALE86 code and the ANSI/ANS-18.1-1999 standard for licensing large LWRs in the United States (U.S.). Additional guidance needs to be developed by the staff which would provide the acceptance and evaluation criteria for when an alternate method is proposed by an applicant or licensee. This guidance would also be applicable to advanced reactor designs. 2. What is the impact on internal and external stakeholders of not updating the RG for the known issues, in terms of anticipated numbers