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:
le equipment, and reserve storage and treatment capacity. 3. The seismic design and the quality group and safety classifications of components used in the GWMS and structures housing the system should conform to RG 1.143. The design should include precautions to stop continuous leakage paths (i.e., to provide liquid seals downstream of rupture discs) and to prevent permanent loss of the liquid seals in the event of an explosion due to gaseous wastes 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. In addressing the regulatory positions of RG 1.143 on safety classifications of radwaste SSCs against unmitigated releases of radioactive materials or unmitigated radiation exposures to site personnel, the acceptance criteria are 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), and 5 rem (50 mSv) for a plant worker assumed to be located in the restricted area. In classifying system components, the radioactive inventories of components are compared to the criteria in determining the appropriate classification. RG 1.206, "Combined License Applications for Nuclear Power Plants (LWR Edition)," Part I, C.I.3, Sections 3.2.1 and 3.2.2, and SRP Section 3.8.4, identify applicable acceptance criteria in evaluating SSCs requiring seismic design considerations and discuss differences from the recommendations of RG 1.143. 4. The GWMS should be designed to meet the requirements of 10 CFR 20.1406. System designs should describe features that will minimize, to the extent practicable, contamination of the facility and environment; facilitate eventual decommissioning; and minimize, to the extent practicable, the generation of radioactive waste using the guidance of Interim Staff Guidance (ISG) DC/COL-ISG-06,