Document: NUREG-0800
Document ID: d4d35b7c-b4e5-4cb4-8dd9-1b7edddf0ad6
Document Type: srp
Title: CHEMICAL AND VOLUME CONTROL SYSTEM (PWR) (INCLUDING BORON
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070537.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.4
CFR Part: 
CFR Title: 

Content:
ign Criterion 2 and the guidelines of Regulatory Guide 1.29 by designing safety-related portions of the system to seismic Category I requirements; (3) the requirements of General Design Criterion 5 by designing the CVCS so that components important to safety are not shared between nuclear power units unless such sharing will not significantly impair the ability of the CVCS to perform its safety 9.3.4-15 DRAFT Rev. 3 - April 1996 functions in the event of an accident in one unit and an orderly shutdown and cooldown of the remaining units; (4) the requirements of General Design Criterion 14 by maintaining reactor coolant purity and material compatibility to reduce corrosion and thus reduce the probability of abnormal leakage, rapid propagating failure, or gross rupture of the reactor coolant pressure boundary; (5) the requirements of General Design Criterion 29 as related 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; (6) the requirements of General Design Criteria 33 and 35 by designing the CVCS with the capability to supply reactor coolant makeup in the event of small breaks or leaks in the reactor coolant pressure boundary and to function as part of ECCS assuming a single failure coincident with loss of offsite power; (7) the requirements of General Design Criteria 60 and 61 with respect to confining radioactivity by venting and collecting drainage from the CVCS components through closed systems; and (8) the provisions of III.D.1.1 of NUREG-0737, equivalent to 10 68 CFR 50.34(f)(2)(xxvi) for applicants subject to 10 CFR 50.34(f), with respect to leakage detection and control in the design of CVCS systems outside containment that contain (or may contain) radioactive material following an accident (OL) or NUREG-0718 (CP) as it relates to establishing a leak reduction program ; and (9) the relevant requirements of 10 69 CFR