Document: NUREG-0800
Document ID: f7c58873-6f34-4f88-8e26-90fc2e310d25
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070680137.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
CFR Part: 
CFR Title: 

Content:
ccidents by sampling the reactor coolant, the pressurizer tank, the steam generator blowdown, the secondary coolant condensate treatment waste, the sump inside containment, the containment atmosphere, and the gaseous radwaste storage tank for radioactivity. For BWR The staff has determined that the proposed process sampling system meets (1) the requirements of GDC 13 and 14 to monitor variables that can affect the reactor coolant pressure boundary and to assure a low probability of abnormal leakage, rapidly propagating failure, and gross rupture, respectively, by sampling the reactor coolant and the condensate for chemical impurities that can affect the reactor coolant pressure boundary; (2) the requirements of GDC 26 to maintain the reactor core subcritical under cold conditions in the event that control rod system is inoperable by sampling the standby liquid control system tank for boron concentration; and (3) the requirements of GDC 64 to monitor for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accidents by sampling the reactor coolant, the main condenser evacuation system offgas, the sump inside containment, the drywell atmosphere, and the offgas charcoal delay or decay beds for radioactivity. For both PWR and BWR The staff has further determined that the proposed process sampling system meets (1) the requirements of 10 CFR 20.1101(b) to keep radiation exposures as low as is reasonably achievable and of GDC 60 to control the release of radioactive materials to the environment by purging and draining sample streams back to the system of 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; (2) the requirements of GDC 63 to detect conditions that may result in excessive radiation levels in fuel storage and radioactive waste systems by sampling the