Document: NUREG-0800
Document ID: ddaa3c7d-ce79-4a3f-aaae-4e4436ab7bc1
Document Type: srp
Title: NUCLEAR DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740003.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.3
CFR Part: 
CFR Title: 

Content:
pressure. B. Providing suitable alarms and/or control room indications for these monitored variables. 4. The applicant has met the requirements for GDC 26 with respect to provision of two independent RCSs of different designs by: A. Having a system that can reliably control anticipated operational occurrences. B. Having a system that can hold the core subcritical under cold conditions. C. Having a system that can control planned, normal power changes. 5. The applicant has met the requirements of GDC 27 with respect to RCSs that have a combined capability in conjunction with poison addition by the emergency core cooling system of reliably controlling reactivity changes under postulated accident conditions by: 4.3-19 Revision 3 - March 2007 A. Providing a movable control rod system and a liquid poison system. B. Performing calculations to demonstrate that the core has sufficient shutdown margin with the highest worth stuck rod. 6. The applicant has met the requirements of GDC 28 with respect to postulated reactivity accidents by (reviewed by the organization responsible for the review/assessment of nuclear design under SRP Sections 15.4.8 or 15.4.9): A. Meeting the regulatory position in Regulatory Guide 1.77 for PWRs. B. Meeting the fuel enthalpy limit criteria in SRP Section 4.2, Appendix B, “Interim Acceptance Criteria and Guidance for the Reactivity Initiated Accidents.” C. Meeting the criteria on the capability to cool the core. D. Using calculational methods that have been found acceptable for reactivity insertion accidents. 7. The applicant has met the requirements of GDC 10, 20, and 25 with respect to specified acceptable fuel design limits by providing analyses demonstrating: A. That normal operation, including the effects of anticipated operational occurrences, have met fuel design criteria. B. That the automatic initiation of the RCS assures that fuel design criteria are not exceeded as a result of anticipated operational occurrences and assures the