Document: NUREG-0800
Document ID: faf774de-7226-41f8-ba11-7cf612907af6
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1306/ML13065A119.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
herein), and using the analysis of RG 1.143 in assigning the safety classifications to SSCs of the GWMS for design purposes, provide reasonable assurance that the necessary information is available to identify the amounts of radioactive materials contained in the GWMS and assess the radiological impacts during postulated accidents. 7. Appendix I to 10 CFR Part 50 provides numerical 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. 11.3-20 Draft Revision 4 – August 2014 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