Document: NUREG-0800
Document ID: 47c0ffe8-0c76-4d7a-8671-f04b7c8ae803
Document Type: srp
Title: – 15.3.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070705.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
CRITERIA The RSBSRXB acceptance criteria are based on meeting the relevant requirements of the 23 following regulations: A. General Design Criterion 10 (GDC 10) (Ref. 1), as it relates to the reactor coolant 24 25 system being designed with appropriate margin to assure ensure that specified 26 acceptable fuel design limits are not exceeded during normal operations, including anticipated operational occurrences. B. General Design Criterion 15 (GDC 15) (Ref. 2), as it relates to the reactor coolant 27 28 system and its associated auxiliaries being designed with appropriate margin to assure ensure that the pressure boundary will not be breached during normal operations, including anticipated operational occurrences. C. General Design Criterion 17 (GDC 17) as it relates to providing onsite and offsite electric power systems to ensure that structures, systems, and components important to safety will function during normal operation, including anticipated operational occurrences. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to ensure that acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded during an anticipated operational occurrence.29 CD. General Design Criterion 26 (GDC 26) (Ref. 33), as it relates to the reliable control of 30 31 reactivity changes to assure ensure that specified acceptable fuel design limits are not exceeded, including anticipated operational occurrences. This is accomplished by assuring ensuring that appropriate margin for malfunctions, such as stuck rods, are accounted for. The term "moderate frequency" is used in this SRP section in the same sense as in the a descriptions of design and plant process conditions in References 11 and 12. DRAFT Rev. 2 - April 1996 15.3.1-4 The basic objectives of the review of loss of forced reactor coolant flow transients are: 1. To identify which of the transients