Document: NUREG-0800
Document ID: a7fafe76-5570-446b-96dd-3e53ec9bccb3
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340663.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4
CFR Part: 
CFR Title: 

Content:
ross sections. e. The geometric modeling of the reactor, support barrel, water annulus, and pressure vessel. f. Uncertainties in the calculation. 9. The adequacy of limits on power distribution during normal operation is reviewed in connection with review of the thermal-hydraulic design under SRP Section 4.4. 10. The adequacy of proposed instrumentation to meet the requirements for maintaining the reactor operating state within defined limits is reviewed under SRP Sections 7.1 through 7.6. 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) related to the reactor core and reactivity control systems (Ref. 1). The relevant requirements are as follows: 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 inherent nuclear feedback characteristics tend to compensate for a rapid increase in reactivity. C. GDC 12 requires that power oscillations which could result in conditions exceeding specified acceptable fuel design limits are not possible or can be reliably and readily detected and suppressed. D. GDC 13 requires provision of instrumentation and controls to monitor variables and systems that can affect the fission process over anticipated ranges for normal operation, anticipated operational occurrences and accident conditions, and to maintain the variables and systems within prescribed operating ranges. 4.3-4 Rev. 2 - July 1981 E. GDC 20 requires automatic initiation of the reactivity control systems tu assure that acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and to assure automatic operation of systems and components important to safety under accident conditions. F. GDC 25 requires that no single malfunction of the