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:
eactors. b. The reviewer determines the equipment, operating restrictions, and administrative procedures that are required to restrict possible control rod and bank worths, and the extent to which the alarm criterion in subsection II.3.0 of this SRP section is satisfied. If the equipment involved is subject to frequent downtime, the reviewer must determine if alternative measures should be provided or the extent of proposed outage time is acceptable. c. The reviewer will employ the same procedures as in item 5.a, above, to evaluate the scram reactivity information described in subsection I.5 of this SRP section. The scram reactivity is a property of the reactor design and is not easily changed, but if restrictions are necessary the procedures in item 5.b, above, can be followed as applicable. 6. The information presented on criticality of fuel assemblies is reviewed in the context of the applicant's physics calculations and the ability to calculate criticality of a small number of fuel assemblies. This informa- tion is related to information on fuel storage presented in SAR Section 9.1 and reviewed under SRP Sections 9.1.1 and 9.1.2. The reviewer of SRP Section 9.1 assumes that the applicant's criticality calculations have been reviewed by CPB and are acceptable. 7. The reviewer exercises professional judgment and experience to ascertain the following about the applicant's analytical methods: a. The computer codes used in the nuclear design are described in suffi- cient detail to enable the reviewer to establish that the theoretical bases, assumptions, and numerical approximations for a given code reflect the current state of the art. b. The source of the neutron cross-sections used in fast and thermal spectrum calculations is described in sufficient detail so that the reviewer can confirm that the cross-sections are comparable to those in the current ENDF/B data files (Ref. 4). If modifications and normalization of the cross-section data have been made, the bases