Document: NUREG-0800
Document ID: 7544d2bf-daeb-45a0-a330-e11124ef4465
Document Type: srp
Title: - 15.3.4-6
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
Revision 3 - March 2007 4. The core burnup is selected to yield the most limiting combination of moderator temperature coefficient, void coefficient, Doppler coefficient, axial power profile, and radial power distribution. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: The technical rationale for application of these acceptance criteria to reviewing analyses of transients initiated by RCP rotor seizure and shaft break is discussed in the following paragraphs: 1. GDC 17 requires that onsite and offsite electrical power systems be provided to ensure that structures, systems, and components important to safety will perform their intended function. Each power system (assuming the other system is not functioning) is to provide sufficient capacity and capability to ensure that: (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences; and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents. GDC 17 is applicable to SRP Section 15.3.3-15.3.4 because this section reviews the analysis of events that are classified as abnormal operating occurrences or postulated accidents, depending on the severity of the results. Meeting the requirements of GDC 17 provides assurance that the design conditions of the reactor coolant pressure boundary are not exceeded as a result of reactor coolant pump rotor seizures and shaft breaks and that the core is cooled and containment and other vital functions are maintained. 2. Compliance with GDC 27 requires that reactivity control systems be designed to have a combined capability (in conjunction with poison added by the emergency core cooling system) of reliably controlling reactivity changes, thereby ensuring that the