Document: NUREG-0800
Document ID: c37e8c68-ed08-434b-b15c-438f1915858a
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070526.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
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Content:
ail in the closed position or passive flow restrictions in the sampling lines; and (b) the requirements of GDC 63 in Appendix A to 10 CFR Part 50 , to detect conditions that may result in excessive 81 radiation levels in fuel storage and radioactive waste systems, by sampling the spent fuel pool water and the gaseous radwaste storage tank for radioactivity. The staff also has determined that the proposed process sampling and post-accident sampling systems meet the quality standards requirements of GDC 1 and the seismic requirements of GDC 2 in Appendix A to 10 CFR Part 50 , by designing the sampling 82 lines and components of the process and post-accident sampling systems to conform to the classification of the system to which each sampling line and component is connected, in accordance with the regulatory positions C.1, C.2, and C.3 of Regulatory Guide 1.26, the regulatory positions C.1, C.2, C.3, and C.4 of Regulatory Guide 1.29, and the guidelines of Regulatory Guide 1.97. In addition, the staff has determined that the proposed post-accident sampling system meets (1) the requirements of 10 CFR 50.34(f)(2)(viii) and related clarifications of 83 Iitem II.B.3 in NUREG-0737 by providing a sampling program to obtain and analyze promptly samples from the reactor coolant and the containment atmosphere, for radionuclides which may be indicators of the degree of core damage and for dissolved gases, chloride and boron concentrations in liquids, following a postulated accident, in accordance with the guidelines of Regulatory Guide 1.97; (2) the requirements of GDC 13 and 14 in Appendix A to 10 CFR Part 50 , to monitor variables which can affect the 84 integrity of the reactor core and the reactor coolant pressure boundary for accident conditions, and to assure a low probability of abnormal leakage, rapidly propagating failure, and gross rupture, respectively, by keeping the oxygen concentration in the reactor coolant below the Technical Specification limits when the