Document: NUREG-0800
Document ID: 18405759-3ae6-4408-b6ab-7b3ca11fcd9f
Document Type: srp
Title: SAFE SHUTDOWN SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550085.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.4
CFR Part: 
CFR Title: 

Content:
e systems. Based on the review of the system design for conformance to the guidelines, the staff finds that there is reasonable assurance that the systems fully conform to the guidelines applicable to these systems. Therefore, the staff finds that the requirements of GDC 1 and 10 CFR 50.55a(a)(1) have been met. The non-safety portions of safe shutdown systems important to safety are appropriately isolated from safety systems, including the safety portions of the safe shutdown systems. Therefore, the staff concludes that the isolation of these systems from safety systems satisfies the requirements of 10 CFR 50.55a(h) and the requirements of GDC 24. The review included the identification of those systems and components for the safe shutdown systems that are designed to survive the effects of earthquakes, other natural phenomena, abnormal environments, and missiles. Based on the review, the staff concludes that the applicant/licensee has identified those systems and components consistent with the design bases for those systems. Sections 3.10 and 3.11 of the SER address the qualification programs to demonstrate the capability of these systems and components to survive these events. Therefore, the staff finds that the identification of these systems and components satisfies the requirements of GDC 2 and 4. 7.4-9 Revision 5 - March 2007 Based on the review, the staff concludes that the I&C have been provided to maintain variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems within prescribed operating ranges during plant shutdown. Therefore, the staff finds that the systems required for safe shutdown satisfy the requirements of GDC 13. I&C have been provided within the control room to allow actions to be taken to maintain the nuclear power unit in a safe condition during shutdown, including a shutdown following an accident. Equipment at appropriate