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:
e GWMS for design purposes. 13. 10 CFR Part 50, Appendix B, as it applies to GWMS systems and components not covered by the QA guidance of RG 1.143. 11.3-11 Revision 4 – January 2016 14. 10 CFR Part 50, Appendix I, Sections II.B, II.C, and II.D, as they relate to the numerical guidelines for design objectives and limiting conditions for operation to meet the ALARA criterion. 15. 40 CFR Part 190 (Environmental Protection Agency (EPA)) generally applicable environmental radiation standards) for nuclear power operations, as implemented under 10 CFR 20.1301(e), as it relates to limits on total annual doses from all sources of radioactivity contained in gaseous effluents and external radiation from site buildings and facilities (with single or multiple reactor units). SRP Sections 11.2, “Liquid Waste Management System,” and 11.4 evaluate source terms and doses from liquid effluents and solid wastes. SRP Section 11.5 addresses the means to demonstrate compliance with all sources of effluents. SRP Section 12.3-12.4 evaluates doses associated with external radiation from buildings and sources of radioactivity contained in systems and components, including skyshine from BWR turbine buildings. 16. 10 CFR Part 52.17(a)(1)(ii), which requires that an ESP application include the anticipated levels of radioactive effluents released in plant environs and provide a bounding assessment in demonstrating the capability to comply with the regulatory requirements of 10 CFR Part 20 and 10 CFR Part 50, Appendix I design objectives. 17. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed ITAAC that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act (AEA), and the NRC regulations. For the GWMS,