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:
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 which operator actions are required. F. Appropriate margin for malfunctions (e.g., stuck rods). G. Appropriate accounting for instrumentation uncertainties of system and operating parameters. 2. If the SAR (or DCD) states that one of these transients is not as limiting as other similar transients, the reviewer evaluates the applicant’s justification. The SAR (or DCD) must present a quantitative analysis of the most limiting reduction-of-heat-removal transient. For this transient, the reactor systems reviewer, in consultation with the instrumentation and controls reviewer, reviews the timing of the initiation of protection, engineered safety, and other systems needed to limit the consequences of the transient adequately to an acceptable level. The reactor systems reviewer compares the predicted variation of system parameters with various trip and system initiation setpoints. The instrumentation and controls reviewer consults on automatic initiation, actuation delays, possible bypass modes, interlocks, and the feasibility of manual operation if the SAR (or DCD) states that operator action is needed or expected. 15.2.1-15.2.5-9 Revision 2 - March 2007 3. To the extent deemed necessary, the reviewer evaluates the effect of single active system or component failures that may affect the course of the transient. For new applications, LOOP should not be considered a single failure; each of the reduction-of-heat-removal transients should be analyzed with and without a LOOP in combination with a single active failure. This phase of the review uses the system review procedures described in the SRPs for SAR (or DCD) Chapters 5, 6, 7, and 8. 4. The applicant’s mathematical models to evaluate core performance and to predict system pressure in the reactor coolant system and main