Document: NUREG-0800
Document ID: 45365840-b317-4094-89a8-02dbe0093404
Document Type: srp
Title: 15.3.2.-8
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550010.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
Revision 2 - March 2007 C. The extent to which credit is taken for the functioning of normally operating plant systems. D. The extent to which the operation of engineered safety systems is required. E. The extent to which operator actions are required. F. Whether the description accounts for appropriate margin for malfunctions (e.g., stuck rods). G. Whether the description accounts for instrumentation uncertainties of system and operating parameters appropriately. 2. If the SAR or DCD states that a particular loss of flow transient is not as limiting as some other similar transients, the reviewer evaluates the applicant’s justification. The reviewer confirms whether all types of flow loss transients are considered (e.g., pump trips during two-, three-, and four-loop operations). The SAR or DCD must present a quantitative analysis of the most limiting loss of flow transient. For this transient, the reactor systems reviewer, in coordination 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 loss of flow adequately. The reviewer compares the predicted variation of system parameters to various trip and system initiation setpoints and evaluates the effects of system and component single, active failures which may alter the course of the transient. For new applications, LOOP should not be considered a single failure; each loss of flow transient should be analyzed with and without a LOOP in combination with a single active failure. The instrumentation and controls review of SAR Chapter 7 or the corresponding DCD chapter confirms whether the instrumentation and control design is consistent with the requirements for safety system actions for these events. 3. The applicant’s mathematical models to evaluate core performance and to predict system pressure in the reactor coolant system and main steam lines are reviewed for whether these models have