Document: NUREG-0800
Document ID: 1a3364df-d783-4da3-9f56-b8a667f8cf50
Document Type: srp
Title: CHEMICAL AND VOLUME CONTROL SYSTEM (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350555.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.4
CFR Part: 
CFR Title: 

Content:
TERIA Acceptability of the CVCS and BRS design, as described in the applicant's safety analysis report (SAR), is based on specific general design criteria and the positions of regulatory guides listed below. The CMEB acceptance criteria are based on meeting the requirements of the fol- lowing regulations: A. General Design Criterion 1, as it relates to system components being as- signed quality group classifications and application of quality standards in accordance with the importance of the safety function to be performed. Acceptance is based on meeting the guidance in Regulatory Guide 1.26. B. General Design Criterion 2,. as it relates to structures housing the facil- ity and the system itself being capable of withstanding the effects of earthquakes. Acceptance is based on meeting the guidance of Regulatory Guide 1.29, Position C.1, for safety-related portions of the system and Position C.2 for nonsafety-related portions. 9.3.4-3 Rev. 2 - July 1981 C. General Design Criterion 5, it relates to shared systems and components important to safety being capable of performing required safety functions. D. General Design Criterion 14, as it relates to assuring reactor coolant pressure boundary material integrity by means of the CVCS. being capable of maintaining reactor coolant system water chemistry necessary to meet PWR reactor coolant system water chemistry technical specifications. E. General Design Criterion 29, as it relates to the reliability of the CVCS to provide negative reactivity to the reactor by supplying borated water to the reactor coolant system in the event of anticipated operational occurrences. F. General Design Criteria 33 and 35 as they relate to the CVCS capability. to supply reactor coolant makeup in the event of small breaks or leaks in the reactor coolant pressure boundary, to function as part of ECCS assum- ing a single active failure coincident with the loss of offsite power, and to meet ECCS technical specifications. G. General Design