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
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rator temperature in the hot standby range. d. The applicability and accuracy of experimental data from critical experiments and operating reactors used to determine or justify uncertainty allowances. Measurements during startup and during the cycle of moderator temperature coefficients and full power Doppler coefficients in the case of PWRs, and results of measurements of transients during startup in the case of boiling water reactors (BWRs), should be examined. As part of the review, comparisons are made between the values and uncertainty allowances for reactivity coefficients for the reactor under review and those for similar reactors previously reviewed and approved. Generally, many essential areas will have been covered during earlier reviews of similar reactors. The reviewer notes any differences in results for essentially identical reactors and any lack of differences for reactors with changed core characteristics, and judges the significance and validity of any differences or lack of differences. e. The range of moderator temperature coefficient (MTC) values. The MTC should be non-positive over the entire fuel cycle when the reactor is critical.24 DRAFT Rev. 3 - April 1996 4.3-12 f. The appropriateness of reactivity coefficients used in evaluating reactivity accidents reviewed under SRP Sections 15.4.8 and 15.4.9.25 4. The review procedures in the area of reactivity control requirements and control provisions are as follows: a. The reviewer determines that two independent reactivity control systems of different design are provided. b. The reviewer examines the tabulation of control requirements, the associated uncertainties, and the capability of the control systems, and determines by inspection and study of the analyses and experimental data that the values are realistic and conservative. c. The reviewer determines that one of the control systems is capable of returning the reactor to the cold shutdown condition and maintaining it in this condition, at any