Document: NUREG-0800
Document ID: 73148264-0cb4-4b1b-8586-3105a0a46c78
Document Type: srp
Title: REACTOR WATER CLEANUP SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190009.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.8
CFR Part: 
CFR Title: 

Content:
rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. Compliance with GDC 1 requires that structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. GDC 1 applies to the RWCS because the system is connected directly to the reactor coolant system and contains reactor coolant and radioactive demineralizer resins. Failure of a component of the system could result in a loss-of-coolant accident, release of reactor coolant outside the containment structure, and/or release of demineralizer resins. For this reason, the portion of the RWCS extending from the reactor vessel and 5.4.8-7 Revision 3 - March 2007 recirculation loops to the outermost drywell isolation valves should be designed to seismic Category I and Quality Group A. The remainder of the system need not be seismic Category I and should be designed to Quality Group C. The precoating unit for demineralizers need not be designed to Quality Group C and need not be seismic Category I. Meeting the requirements of GDC 1 minimizes the probability that a failure of the RWCS will occur, thus reducing the potential for a loss-of-coolant accident or release of radioactive materials outside the containment structure. 2. Compliance with GDC 2 requires that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of natural phenomena such as earthquake, tornado, hurricane, flood, tsunami, and seiche without loss of capability to perform their safety functions. GDC 2 applies to the RWCS because the system carries reactor water outside the containment structure and contains radioactive material. Failure of a system component as the result of a natural phenomenon could result in release of reactor water until the containment isolation