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:
ontinuous leakage paths after an explosion of combustible gas mixtures. The areas of concern are (1) process streams where water decomposition gases (hydrogen and oxygen) exist in a BWR, (2) cover gas streams where air in-leakage can occur in a 11.3-27 Revision 4 – January 2016 PWR, and (3) areas where there is a possibility of liquid hydrocarbons and ozone collecting in a cryogenic distillation system. 6. The GRS design, system layout, equipment design, method of operation, and provisions to reduce leakage and to facilitate operations and maintenance are compared to RG 1.143 and 4.21 for gaseous wastes produced during normal operation and AOOs, including adverse vacuum conditions. Special design features provided to control leakage from system components and/or topical reports on system designs will be evaluated on a case-by-case basis. The applicant’s design is compared to RG 1.143, as acceptable guidance related to seismic, safety, and quality group classifications and quality assurance provisions for SSCs systems of the GWMS in treating gaseous wastes and effluents produced during normal operation and AOOs. RG 1.143 provides guidance in assigning safety classifications to structures and radioactive waste management systems in protecting SSCs against natural phenomena and man-induced hazards. For unmitigated releases of radioactive materials, the acceptance criterion of RG 1.143 is 1 mSv (100 mrem) for members of the public assumed to be located at or beyond the restricted area or in unrestricted areas (whichever is most limiting). For unmitigated radiation exposures to site personnel, the acceptance criterion is 5 rem (50 mSv) for a plant worker assumed to be located in the restricted area. In classifying system components, the radioactivity inventories of components are compared to the acceptance criteria in determining the appropriate safety classification. In addition, RG 1.206, Part I, C.I.3, Sections 3.2.1 and 3.2.2, and SRP Section 3.8.4, identify