Document: NUREG-0800
Document ID: 7ed8e5d3-fcfd-49cc-84ad-3b25caba06af
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550006.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
he proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 15.1.5-9 Revision 3 - March 2007 The procedures below are used during the construction permit (CP), operating license (OL), and combined license (COL) 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 or COL review stage, 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. 1. The reviewer determines the acceptability of the analytical models and assumptions, as follows: A. The values of system parameters and initial core and system conditions used as input to any analytical model are reviewed by Reactor Systems. Of particular importance are (1) the reactivity coefficients and control rod worths used in the analysis and (2) the variation of moderator temperature, void, and Doppler coefficients of reactivity with core life. The reviewer will evaluate the justification provided by the applicant to show that the core burnup yielding the minimum margins has been selected. Core Performance reviews core-related parameters such as DNB correlations and the values of the reactivity parameters used in the analysis. The reviewer confirms that the amount of secondary coolant expelled from the system (for breaks outside containment) has been calculated conservatively by evaluating the methods and assumptions, by comparing these results with those of an acceptable analysis performed on another plant of similar design, or by comparing the results with staff calculations. B. The acceptability of the methods equations, sensitivity studies, and models proposed by the applicant are evaluated. C. Analytical models should be sufficiently detailed to simulate the reactor coolant (primary), steam generator (secondary), and auxiliary