Document: NUREG-0800
Document ID: e1c5261f-4ef6-4478-8cf0-015611057574
Document Type: srp
Title: and 9.3.2, “Process and Post-accident Sampling Systems.”  The review addresses
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A039.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
ical guidance for design objectives to meet the requirements that radiation doses from radioactive materials in effluents released to unrestricted areas be kept ALARA. Sections II.B, II.C, and II.D of Appendix I relate to the numerical guides for dose design objectives, limiting conditions for operation, and controls to meet the ALARA criterion for gaseous effluents. RG 1.109 and 1.111 provide acceptable methods in performing dose analyses that comply with the Appendix I design objectives to demonstrate that the GWMS design results in doses from releases of radioactive materials from each reactor. RG 1.110 provides an acceptable method of performing cost-benefit analysis to demonstrate that the GWMS design includes all items of reasonably demonstrated technology capable of reducing cumulative population doses from releases of radioactive materials in effluents from each reactor to ALARA levels within an 80 km (50 mile) radius of the reactor and to demonstrate compliance with the cost-benefit ratio of Section II.D of Appendix I. RG 1.140 presents methods acceptable to the staff for implementing the regulations in Appendix I to 10 CFR Part 50 by providing guidance on the design, testing, and maintenance criteria for HEPA filters and charcoal absorbers in filtration systems. Using the guidance of RG 1.109, 1.111 and 1.140 provides reasonable assurance that the requirements of Sections II.B, II.C, and II.D, of Appendix I to 10 CFR Part 50 are met with respect to exposures to radioactive materials and doses to the maximally exposed offsite individual. The criteria include dose limits from noble gases (as gamma and beta radiation air dose rates), radiation doses from carbon-14, tritium, particulates, and radioiodines, and the criterion in evaluating the results of a cost-benefit analysis in complying with ALARA provisions. 8. BTP 11-5 describes acceptable methods to evaluate doses at the EAB associated with the postulated releases of radioactive gases and radioiodines (as