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:
r, the sufficiency of battery capacity, the use of direct current power only to support operation of specified systems/subsystems, and the plant’s capabilities to cope with an SBO, as required by 10 CFR 50.63. 5.4.6-4 Revision 2 - March 2007 11. SRP Section 3.9.3 is used to ensure that the design and installation of the RCIC system meet applicable codes and are adequate for its proper functioning. 12. SRP Section 3.10 is used to review RCIC system equipment to verify that it is seismically qualified for its intended use. 13. SRP Section 3.11 is used reviews RCIC system equipment to confirm that it is environmentally qualified for its intended use. 14. The inservice testing of pumps and valves for the RCIC system is reviewed under SRP Section 3.9.6. 15. The CST level detection and activation of switchover of suction of the RCIC pump to the suppression pool is reviewed under SRP Section 9.2.6. 16. The RCIC pump room cooling is reviewed under Section 9.4.5. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. GDC 4, which requires, in part, that SSCs important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents. These SSCs shall be appropriately protected against dynamic effects. 2. GDC 5, which requires, in part, that structures, systems, and components important to safety shall not be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions. 3. GDC 29, which requires that the protection and reactivity control systems be designed to assure an extremely high probability of accomplishing their safety functions in the event of anticipated