Document: NUREG-0800
Document ID: c766e34e-6ea5-45e7-9123-75964d118447
Document Type: srp
Title: REACTOR CORE ISOLATION COOLING SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070540102.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.6
CFR Part: 
CFR Title: 

Content:
regarding leak detection and isolation provisions for lines passing through the primary containment. SRP Sections 6.2.4 and 6.2.6 describe other containment isolation criteria for the RCIC system. 7. The RCIC system should meet the following task action plan item recommendations of NUREG-0737 and NUREG-0718: A. Section II.K.1.22 with regard to actions, both automatic and manual, necessary for proper functioning of the auxiliary heat removal systems that are used when the main feedwater system is not operable. The regulations at 10 CFR 50.34(f)(2)(xxi) establish an equivalent requirement for those applicants subject to the requirements of 10 CFR 50.34(f). B. Section II.K.3.13 with regard to separation of the initiation levels of the HPCI and RCIC systems so that the RCIC system initiates at a higher water level than the HPCI system and so that the RCIC system initiation logic will restart the RCIC system on a low water level. The regulations at 10 CFR 50.34(f)(1)(v) establish an equivalent requirement for those applicants subject to the requirements of 10 CFR 50.34(f). C. Section II.K.3.15 with regard to preventing spurious isolation of the RCIC system from the line break detection logic. D. Section II.K.3.22 with regard to automatic switchover of the RCIC system suction from the CST to the suppression pool when the CST level is low. E. Section II.K.3.24 with regard to space cooling to ensure reliable long-term operation of the RCIC system following a complete loss of offsite power to the plant for at least 2 hours. The regulations at 10 CFR 50.34(f)(1)(ix) establish an equivalent requirement for those applicants subject to the requirements of 10 CFR 50.34(f). F. Section III.D.1.1 with regard to leakage detection and control in the design of systems outside containment that include (or might include) radioactive source term materials following an accident. The regulations at 10 CFR 50.34(f)(2)(xxvi) establish an equivalent requirement for those applicants subject to