Document: NUREG-0800
Document ID: fb2c3684-8fec-4057-868d-a766b49899b7
Document Type: srp
Title: INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350113.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
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CFR Title: 

Content:
in this chapter. This includes power levels, power distributions, doppler coefficients, moderator temperature coefficients, void coefficients, reactor kinetics parameters, and control rod worths. The CPB review includes the evaluation of possible damage to the fuel as well as the operating and uncertainty bands associated with these variables and assists RSB as requested. The review of anticipated operational occurrences and postulated accidents by RSB and CPB requires an evaluation of results, presented in the application, of analytical methods which frequently are not documented in the application. In such cases, the applicant may refer to a vendor topical report. The methods include DNB (departure from nucleate boiling) correlation development, subchannel analysis, system transient analysis, analysis of RIA (reactivity-initiated accidents), and LOCA (loss-of-coolant accident) analysis. For those cases where applicants use techniques previously considered and approved by the staff, additional review of methods may not be required. However, if new 15.0-2 Rev. 2 - July 1981 methods are involved, RSB and CPB perform a review of topical reports and other information which describe the method of analysis. Such a review generally includes vendor model description, data correlations and empirical relationships, solution techniques, summary of computer codes if involved, sample problems, experimental verification, and comparative calculations. In its review of anticipated operational occurrences and postulated accidents, RSB and CPB may perform an independent check of the results submitted by the applicant. In such cases, RSB or CPB obtains input data for use in the audit analysis which is obtained from the applicant. Upon request of RSB, the Instrumentation and Control Systems Branch provides assistance in evaluating the sequence of postulated events, protective and safeguards systems actuation and potential bypass modes, and manual control. ICSB determines whether