Document: NUREG-1555
Document ID: 3757d214-136f-4fb0-adc6-79ede1191089
Document Type: esrp
Title: IMPACTS TO MEMBERS OF THE PUBLIC
Source: NUREG-1555
Source URL: https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1555/initial/
Revision Date: 2007-10
Chapter: 5
Section ID: 5.4.3
CFR Part: 
CFR Title: 

Content:
5.4.2), including - maximum individual doses from liquid effluents - maximum individual doses from gaseous effluents - maximum individual doses from direct radiation sources - collective doses to the population within 80 km (50 mi) of the plant - occupational collective doses. ` natural radiation doses that are generally applicable to the site (from NCRP [1987]). II. ACCEPTANCE CRITERIA Acceptance criteria for determining the radiological impacts to individuals from releases during routine operations including anticipated operational occurrences of the reactor are based on the relevant requirements of the following: • 10 CFR 50, Appendix I, with respect to radiological impacts to individuals from the radiological effluent releases from reactors • 10 CFR 20.1301 with respect to the guidelines for radiological effluent releases from reactors. Note: In accordance with the statement of considerations for 10 CFR 20 (5 CFR 23360), demonstration of compliance with the limits of 40 CFR 190 (as referenced in 10 CFR 20.1301(d)) is considered to be in compliance with the 0.1-rem limit (10 CFR 20.1301). Regulatory guides and specific criteria necessary to meet the regulations identified above are as follows: • Regulatory Guide 1.109, Rev. 1, Calculation of Annual Doses to Man from Routing Releases of Reactor Effluents for the Purpose of Evaluating Compliance with CFR 50, Appendix I (NRC 1976), with respect to determining doses to the public from reactor effluents October 1999 5.4.3-3 NUREG-1555 • NUREG-0543, Methods for Demonstrating LWR Compliance with the EPA (NRC 1980), with respect to comparing doses to 10 CFR 20.1301(d) requirements as they relate to 40 CFR 190. Technical Rationale The technical rationale for evaluating the applicant’s radiological impacts on individuals resulting from potential effluent releases from the plant is discussed in the following paragraph: The basis for determining whether an applicant’s radioactive waste management system meets