Document: NUREG-0800
Document ID: 02c71704-7dd8-4f79-8d59-fb83d3f99ac6
Document Type: srp
Title: 3
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350154.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
Rev. 1 - July 1981 The applicant's analysis of the loss of reactor coolant flow transients should use an acceptable analytical model. The equations, sensitivity studies, and models described in References 6 through 9 are acceptable. If other ana- lytical methods are proposed by the applicant, these methods are evaluated by the staff for acceptability. For new generic methods, the reviewer requests an evaluation by CPB. The values of parameters used in the analytical model would be suitably conservative. The following values are considered acceptable for use in the model: a. The reactor is initially at rated output (licensed core thermal power) for the number of loops assumed operating, plus 2% to account for power measurement uncertainty, unless a lower power level can be justified by the applicant. The number of loops operating at the initiation of the event should correspond to the operating condition which maximizes the consequences of the event. b. Conservative scram characteristics are assumed, i.e., for a PWR maximum time delay with the most reactive rod held out of the core and for a BWR a design conservatism factor of 0.8 times the calculated negative reactivity insertion rate. c. The core burnup is selected to yield the most limiting combination of moderator temperature coefficient, void coefficient, Doppler coefficient, axial power profile, and radial power distribution. III. REVIEW PROCEDURES The procedures below are used during both the construction permit (CP) and operating license (OL) reviews. During the CP review the values of system parameters and setpoints used in the analysis will be preliminary in nature and subject to change. At the OL review state, final values should be used in the analysis, and the reviewer should compare these to-the limiting safety system settings included in the proposed technical specifications. The description of each of the loss of reactor coolant flow transients presented by the applicant in the SAR is reviewed by RSB