Document: NUREG-0800
Document ID: 2cd63ebf-9196-42c0-880d-a80500b202a4
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550005.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
ce with GDC 15 requires that the reactor coolant system and associated auxiliary, control, and protection systems be designed with sufficient margin to ensure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences. GDC 15 is applicable to this section because these overcooling events cause the reactor coolant system pressure to change in response to the drop in reactor coolant temperature. Although most of these events cause the reactor coolant pressure to decrease, some cause reactor coolant pressure to increase, depending on the worst single failure assumed. For example, for the ABWR the most severe initiating event in this group is a feedwater controller failure during maximum demand (run out of two feedwater pumps). This results in an increase in reactor pressure, but the increase is well within the ASME Code limit. Therefore, for these overcooling transients of SRP Section 15.1.1, the reactor coolant pressure needs to be analyzed to ensure that the pressure acceptance criterion is satisfied. Meeting the requirements of GDC 15 provides assurance that the design conditions of the reactor coolant pressure boundary are not exceeded for the anticipated operational occurrences evaluated in this SRP section involving excessive heat removal by the secondary system. 4. Compliance with GDC 20 requires that the reactor protection system be designed to initiate the operation of appropriate systems automatically, including the reactivity control systems, to ensure that specified acceptable fuel design limits are not exceeded during normal operation, including anticipated operational occurrences. GDC 20 is applicable to this section because the reviewer evaluates the reactor protection system that operates to shut down the reactor automatically to terminate the events (anticipated operational occurrences) analyzed in this SRP section. The events are