Document: NUREG-0800
Document ID: a2d035da-992b-42e8-894f-787a019b437d
Document Type: srp
Title: NUCLEAR DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070410.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.3
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Content:
ng the minimum required boron concentration and system flow capability relative to the size of the reactor vessel, as part of its primary review responsibility for SRP Sections 9.3.5 and 15.8.8 4. The SRXB reviews postulated fuel failures resulting from overheating of cladding, overheating of fuel pellets, excessive fuel enthalpy, pellet/cladding interaction and bursting as part of its review responsibilities in Chapter 15.9 5. The SRXB verifies compliance with requirements applicable to reactivity accidents (GDC 28) as part of its review responsibility for SRP Sections 15.4.8 and 15.4.9.10 In addition, the SRXB will coordinate with other branches' evaluations that interface with the overall review of the system as follows: 1. The Materials and Chemical Engineering Branch (EMCB) reviews the neutron induced embrittlement of the reactor vessel materials as part of its review responsibility for SRP Sections 5.3.1 and 5.3.2.11 2. The Instrumentation and Controls Branch (HICB) reviews the adequacy of proposed instrumentation to meet the requirements for maintaining the reactor operating within defined limits as part of its review responsibility for SRP Sections 7.1 through 7.6.12 3. The Plant Systems Branch (SPLB) verifies that the new fuel and spent fuel storage facilities will maintain the fuel in a subcritical array during all credible storage conditions as part of its review responsibility for SRP Sections 9.1.1 and 9.1.2.13 II. ACCEPTANCE CRITERIA The acceptance criteria in the area of nuclear design are based on meeting the relevant requirements of the General Design Criteria (GDC) 10-13, 20, and 25-28 which related to the reactor core and reactivity control systems (Ref. 1) . The relevant requirements are as follows: 14 A. GDC 10 requires that acceptable fuel design limits be specified that are not to be exceeded during normal operation, including the effects of anticipated operational occurrences. B. GDC 11 requires that in the power operating range, the prompt