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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CFR Title: 

Content:
irons for radioactivity that may be released during normal operations, anticipated operational occurrences, and postulated accidents. The process and post- accident sampling system designs provide the means for monitoring for radioactivity that may be released during normal operations, anticipated operational occurrences and postulated accidents. The process and post-accident sampling systems provide information to indicate the potential for being breached or the actual breach of the barriers to fission product release, i.e., fuel cladding, primary coolant pressure boundary, and containment. The process and post-accident sampling systems provide information regarding the release of radioactive materials which allows for early indication of the need to initiate other protective actions. Meeting the requirements of GDC 64, as it relates to the process and post-accident sampling systems, ensures that a means is provided to monitor the release of radioactive materials providing the plant operator with the indications needed to initiate actions when necessary to protect the health and safety of plant personnel and the general public. 11. TMI Action Plan Item II.B.3 of NUREG-0737 require provision of the capability to promptly obtain and analyze samples from the reactor coolant system and containment that may contain radioactive materials without exceeding specified radiation exposures. 10 CFR 50.34(f)(2)(viii) establishes equivalent requirements for those applicants subject to 10 CFR 50.34(f). Materials to be analyzed and quantified include samples that are indicators of core damage, hydrogen in the containment atmosphere, dissolved gasses, chloride, and boron concentrations. Prompt sampling and analysis of the reactor coolant system and the containment atmosphere following an accident provides important information necessary to the operators efforts to assess and control the plant during the course of an accident. Critical information regarding core damage and coolant