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:
core, and the reactor coolant pressure boundary. The PSS is relied upon to provide water and gaseous samples from the reactor coolant system and associated auxiliary systems during all normal modes of operation. Satisfying the requirements of GDC 13 for the PSS ensures that important information is provided for evaluating whether safety systems and other systems important to safety are performing their intended safety functions (i.e., reactivity control, fuel cladding integrity, maintaining reactor coolant system integrity, and maintaining containment integrity). 9.3.2-9 Revision 3 - March 2007 5. GDC 14 requires that the reactor coolant pressure boundary be designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal leakage, rapidly propagating failure, and gross rupture. The PSS is relied upon during normal operating, transient, and postulated accident conditions to provide primary and secondary water chemistry data. Verification that key chemistry parameters, such as chloride, hydrogen, and oxygen concentrations, are within prescribed limits and that impurities are properly controlled provides assurance that the many mechanisms for corrosive attack will be mitigated and will not adversely affect the reactor coolant pressure boundary. Minimizing the potential for corrosive chemical attack increases plant safety by decreasing the probability that the reactor coolant pressure boundary will be compromised because of degradation from corrosive chemical attack. 6. GDC 26 establishes requirements regarding the reliable control of the rate of reactivity changes. PWRs use the sampling systems to verify the boron concentration, necessary for the control of the rate of reactivity changes, by sampling the reactor coolant, the boric acid storage tanks, and the refueling water storage tank. BWRs use the sampling systems to verify the boron concentration in the standby liquid control system, which may be used to maintain the reactor