Document: NUREG-0800
Document ID: 3b714304-f91e-4999-917a-7d27866735e3
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350117.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
med in order to account for operator delay and/or error. 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 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 RSB. Of particular importance are the reactivity coefficients and control rod worths used in the analysis, and the variation of moderator temperature, void, and Doppler coefficients of reactivity with core life. The justification provided by the applicant to show that he has selected the core burnup that yields the minimum margins is evaluated. CPB is consulted regarding 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 out- side containment) has been calculated conservatively by evaluating the applicant's methods and assumptions, by comparing with an acceptable analysis performed on another plant of similar design, or by comparing with staff calculations for typical plants done by RSB. 15.1. 5-5 Rev. 2 - July 1981 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 systems. The reviewer evaluates the following functional requirements: (1) Reactor trip signal: credit