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:
and figures of the maximum worths of individual rods or banks as a function of position for power and cycle life conditions appropriate to rod withdrawal transients and rod ejection or drop accidents. Descriptions and curves of maximum rates of reactivity increase associated with rod withdrawals, experimental confirmation of rod worths or other factors justifying the reactivity increase rates used in control rod accident analyses, and equipment, administrative procedures, and alarms which may be employed to restrict potential rod worths should be included. D. Descriptions and graphs of scram reactivity as a function of time after scram initiation and other pertinent parameters, including methods for calculating the scram reactivity. 6. The area of criticality of the reactor during refueling. Discussions and tables giving values of keff for single assemblies and groups of adjacent fuel assemblies up to the number required for criticality, assuming the assemblies are dry and also immersed in water, are reviewed. The applicant needs to describe the basis for assuming that the maximum stated keff will not be exceeded. 7. The areas concerning stability. These are: A. As per Section C.1.4.3.2.7 in RG 1.206, phenomena and reactor aspects that influence the stability of the nuclear reactor will be discussed by the applicant. B. Calculations and considerations given to xenon-induced spatial oscillations. C. Potential stability issues due to other phenomena or conditions, as presented by the applicant. D. Verification of the analytical methods for comparison with measured data. 4.3-5 Revision 3 - March 2007 8. The areas concerning analytical methods. These are: A. Descriptions of the analytical methods used in the nuclear design, including those for predicting criticality, reactivity coefficients, burnup, and stability. B. The database and/or nuclear data libraries used for neutron cross-section data and other nuclear parameters, including delayed neutron and photoneutron