Document: NUREG-0800
Document ID: c0c5657a-82df-46c2-8cb5-fad0fd37fb58
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEMS1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070610.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
al occurrences will not result in radiation doses that exceed the limits specified in 10 CFR Part 20. In addition, meeting the requirement will help assure that the system will continue to perform its safety function(s) under postulated accident conditions.56 6. Appendix I to 10 CFR Part 50 provides numerical guidance for design objectives to meet the requirements that radiation doses due to radioactive material in effluents released to unrestricted areas be kept as low as is reasonable achievable. Section II of Appendix I relates to the numerical guides for dose design objectives and limiting conditions for operation to meet the "as low as is reasonably achievable" criterion. Regulatory Guide 1.140 presents methods acceptable to the staff for implementing the regulations in Appendix I by providing guidance on the design, testing and maintenance criteria for HEPA filters and charcoal adsorbers in filtration systems. Meeting the requirements of Sections II.B, II.C, and II.D of Appendix I to 10 CFR Part 50 provide assurance that the limits for external radiation doses to a maximally exposed offsite individual, maximum offsite air doses due to gamma radiation and beta radiation, and radiation doses due to carbon-14, tritium, particulates and iodine to a maximally exposed offsite individual due to gaseous effluents, specified in Sections II.B and II.C and the acceptance criterion for cost-benefit analysis specified in Section II.D for meeting the "as low as reasonably achievable" objective will be met.57 7. Branch Technical Position (BTP) ETSB 11-5 contains system design guidelines and failure assumptions that provide adequate and acceptable design solutions for meeting the requirements of 10 CFR Part 50, § 50.34a, and General Design Criteria 60 and 61 of Appendix A. The purpose of BTP ETSB 11-5 is to provide guidelines on postulated radioactive releases due to a GRS leak or failure. The intent is to minimize potential radiation and to minimize the radiological