Document: NUREG-0800
Document ID: 504a24fe-9056-495a-8541-0e278016ce80
Document Type: srp
Title: in that offsite AC power remains available to operate the station
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070300702.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
ystems to control reactivity changes reliably with appropriate margin for malfunctions (i.e., stuck control rods) so that under conditions of normal operation, including AOOs, SAFDLs are not exceeded. Where applicable, the reviewer examines these margins for whether thermal criteria are satisfied. GDC 26 requirements provide assurance that SAFDLs are not exceeded, ensuring an appropriate margin for malfunctions of the reactivity control system. 15.2.1-15.2.5-8 Revision 2 - March 2007 III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. The procedures are used for the design certification (DC) application review, the construction permit (CP), operating license (OL), and COL reviews. During below the CP review, the values of system parameters and setpoints in the analysis are preliminary and subject to change. At the OL or COL review stage, final values should be in the analysis, and the reviewer should compare these to the limiting safety system settings in the proposed technical specifications. 1. The SAR (or DCD) description of these transients is reviewed for the occurrences leading to the initiating event. The sequence of events from initiation until a stabilized condition is reached is reviewed for: A. The extent to which normally operating plant instrumentation and controls are assumed to function. B. The extent to which plant and reactor protection systems are required to function. C. The extent to which credit is taken for the functioning of normally operating plant systems. D. The extent to which operation of engineered safety systems is required. E. The extent to