Document: NUREG-0800
Document ID: 54e3d49d-900d-4fe8-9297-2fc04501e4e0
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340664.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
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Content:
draulic design of the core meets the requirements of General Design Criterion 10, 10 CFR Part 50 and is acceptable for final design appoval. We also conclude that the reactor core has been design with appropriate margin to assure that acceptable fuel design limits are not exceeded during steady-state operation or anticipated operational occurrences and that the reactor will perform its safety functions throughout its design lifetime under all modes of oper- ation. This conclusion is based on the applicant's analyses of the core thermal-hydraulic performance which was reviewed by the staff and found to be acceptable. The applicant has committed to a preoperational and initial startup test program in accordance with Regulatory Guide 1.68 to measure and confirm the thermal-hydraulic design aspects. The staff has reviewed the applicant's preoperational and initial startup test program and has concluded that it is acceptable. We also conclude that the loose parts monitoring program is designed for compliance with the requirements of Regulatory Guide 1.133, and is, therefore, acceptable. We have reviewed the instrumentation for the detection of inadequate core cooling and concluded that it is in compliance with the acquirements of Item II.F.2 of NUREG-0737 and is acceptable. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan for using this SRP section. Except in those cases which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 2. "General Electric BWR Thermal Analysis Basis