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:
cid 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 subcritical under cold conditions in the event that the control rod system is inoperable. Meeting the requirements of GDC 26, as it relates to the sampling systems, ensures sampling and evaluation of boron concentrations used to control the rate of reactivity changes through the injection of borated water into the reactor coolant system, enhancing plant safety by (a) meeting the combined reactivity control system redundancy and capability requirements and (b) not exceeding acceptable fuel design limits. 7. GDC 41 requires that systems to control fission products, hydrogen, oxygen, and other substances that may be released into the reactor containment be provided as necessary to reduce the concentration and quality of fission products released to the environment following postulated accidents. This requirement is met, in part, by using the PSS to determine the chemical concentration in the containment spray chemical additive tank. Determination that the chemical additive concentration is within limits ensures that a sufficient chemical supply is available during postulated accidents to meet elemental iodine removal requirements and material compatibility requirements. In addition, the PSS is relied upon to sample and evaluate the conditions inside containment resulting from the metal-water reactions, radiolysis, and corrosion following a postulated accident. The information obtained from the process samples is used to verify the safety functions of engineered safety features, including the atmospheric cleanup systems and the containment spray system, to mitigate the consequences of postulated accidents by removing from the containment atmosphere radioactive material that may be released in an accident. Meeting the requirements of GDC 41, as it relates to the PSS,