Document: NUREG-0800
Document ID: 307194c1-0b51-4a4d-bd65-440bb260c4bb
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350552.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
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Content:
ndix A to 10 CFR Part 50 to control the release of radioactive materials to the environment, by purging and draining sample streams back to the system or origin or to an appropriate radwaste treatment system, and by providing either redundant isolation valves that fail 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 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 GOC 2 in Appendix A to 10 CFR Part 50, by designing the sampling 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 regu- latory 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 guide- lines of Regulatory Guide 1.97.. In addition, the staff has determined that the proposed post-accident sampling system meets (1) the clarifications of item 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 irn liquids, following a postu- lated accident, in accordance with the guidelines of Regulatory Guide 1.97; (2) the requirements of GOC 13 and 14 in Appendix A to 10 CFR Part 50, to monitor variables which can affect the Integrity of the reactor core and the reactor coolant pressure boundary for accident conditions, and to assure a low