Document: NUREG-0800
Document ID: c544c383-46ca-4e10-8688-4fd295af8a61
Document Type: srp
Title: provide guidance in evaluating the source terms and doses from gaseous effluents
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1304/ML13044A644.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.4
CFR Part: 
CFR Title: 

Content:
ion-exchange resins using the guidance in RGs 1.189 and 1.205 in conducting fire hazards analyses involving the presence of radioactivity in combustible or flammable materials. Using GDC 3 as guidance provides assurance that radioactive materials are protected from the effects of fires and that the function of plant systems and components will not be compromised in meeting effluent discharge concentration limits of 10 CFR Part 20 associated with releases of contaminated fire protection water and combustion gases and smoke. 4. 10 CFR Part 50, Appendix A, GDC 61, as it relates to the ability of the LWMS design to ensure adequate safety under normal and postulated accident conditions, as noted in SRP Sections 2.4.13 and 11.2 (with BTP 11-6) and analysis of RG 1.143 in assigning the safety classifications to LWMS SSCs for design purposes. 5. 40 CFR Part 190 (the U.S. Environmental Protection Agency’s (EPA)) generally applicable environmental radiation standards), as implemented under 10 CFR 20.1301(e), as it relates to limits on annual doses from all sources of radioactivity contained in liquid effluents and external radiation from site buildings and facilities (with single or multiple reactor units). The guidance has been expanded in 11.2-41 Draft Revision 5 – August 2014 evaluating compliance with the standards for sites that have site-specific information on the locations of offsite dose receptors, and those that do not. 6. 10 CFR 52.17(a)(ii), for ESP applications as relevant requirement to releases and doses under 10 CFR Part 20 and Appendix I to 10 CFR Part 50, such that the design objectives of Section II.A can be met based on anticipated levels of radioactive effluents released in plant environs. 7. Revised staff guidance presented in: DC/COL-ISG-05, Interim Staff Guidance on NUREG-0800, SRP Section 11.1, “GALE86 Code for Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents to Support Design Certification and Combined License