Document: NUREG-0800
Document ID: a2d035da-992b-42e8-894f-787a019b437d
Document Type: srp
Title: NUCLEAR DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070410.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.3
CFR Part: 
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Content:
uding those for predicting criticality, reactivity coefficients, burnup, and stability. b. The data base used for neutron cross-sections and other nuclear parameters. c. Verification of the analytical methods by comparison with measured data. 8. The areas concerning pressure vessel irradiation. These are: a. Neutron flux spectrum above 1 MeV in the core, at the core boundaries, and at the inside pressure vessel wall. b. Assumptions used in the calculations; these include the power level, the use factor, the type of fuel cycle considered, and the design life of the vessel. c. Computer codes used in the analysis. d. The data base for fast neutron cross sections. e. The geometric modeling of the reactor, support barrel, water annulus, and pressure vessel. f. Uncertainties in the calculation. 9. The adequacy of limits on power distribution during normal operation is reviewed in connection with review of the thermal-hydraulic design under SRP Section 4.4.3 10. The adequacy of proposed instrumentation to meet the requirements for maintaining the reactor operating state within defined limits is reviewed under SRP Sections 7.1 through 7.6.4 Review Interfaces:5 The SRXB also performs the following reviews under the SRP sections indicated: 1. The SRXB reviews the thermal, mechanical, and materials design of the fuel system as part of its review responsibility for SRP Section 4.2.6 4.3-5 DRAFT Rev. 3 - April 1996 2. The SRXB reviews thermal margins, adequacies of power distribution limits, the effects of corrosion products (crud), and the acceptability of hydraulic loads as part of its review responsibility for SRP Section 4.4.7 3. The SRXB verifies that BWR standby liquid control systems meet reactivity control requirements for Anticipated Transients Without Scram (ATWS), including the minimum required boron concentration and system flow capability relative to the size of the reactor vessel, as part of its primary review responsibility for SRP Sections 9.3.5 and 15.8.8 4. The