Document: NRC Regulatory Guide
Document ID: 377c2606-4b7c-4c7f-997d-37aed1680452
Document Type: regulatory_guide
Title: Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications + HISTORY - HISTORY 10/2018 – DG-4019 , Proposed Revision 2 11/2014 – Periodic Review of Revision 1 – Revise (Rev. 2)
Source: NRC Regulatory Guide Division 4
Source URL: https://www.nrc.gov/docs/ML1808/ML18087A169.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-4.13
CFR Part: 
CFR Title: 

Content:
ds for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190),” issued February 1980 (Ref. 15). NUREG-0543 states conditions under which conformance with 10 CFR Part 50, Appendix I, provide reasonable assurance of conformance with 40 CFR Part 190. NUREG-0543 states that, in comparing 10 CFR Part 50, Appendix I, to 40 CFR Part 190, the only potentially significant exposure pathway that is not addressed is the direct radiation pathway. NUREG-0543 indicated that, for most facilities with offsite direct radiation doses exceeding 5 mrem (0.05 mSv) per year, it is necessary to determine the magnitude and distribution of off- site direct radiation doses. Under these conditions, NUREG-0543 assumed that a reasonable assurance exists that no individual would receive a significant dose (i.e., greater than 1 mrem (0.01 mSv) per year per reactor) from radioactive liquid effluent release pathways. Therefore, only doses to individuals via airborne gaseous effluent pathways and doses resulting from direct radiation need consideration in determining compliance with EPA’s regulations in 40 CFR Part 190. After the direct radiation dose fields were characterized, the dose resulting from direct radiation was added to the doses resulting from liquid and gaseous effluents to establish compliance with 40 CFR Part 190. Since the publication of NUREG-0543 in 1980, some light-water reactors (LWRs) have begun storing substantial amounts of radioactive material outside the heavily shielded areas of the nuclear power plants (e.g., spent fuel assemblies in independent spent fuel storage installations (ISFSIs) and low-level radioactive waste, such as steam generators and reactor heads). The additional storage of this waste has the potential for increasing the direct radiation levels and dose to members of the public in the unrestricted area and the controlled area of a licensed facility. In 1991, the NRC revised 10 CFR Part 20 to include a new requirement in 10