Document: NUREG-0800
Document ID: 9697248b-d015-42be-8808-2202db24977a
Document Type: srp
Title: STANDBY LIQUID CONTROL SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070680186.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.5
CFR Part: 
CFR Title: 

Content:
with the NRC regulations. 9.3.5-5 Revision 3 - March 2007 1. Acceptance for meeting the relevant aspects of GDC 2 is based on meeting the guidance of Regulatory Guide 1.29, Position C-1. 2. Acceptance for meeting the relevant aspects of GDC 4 is embodied within SRP Section 3.9.2. 3. Acceptance for meeting the relevant aspects of GDC 5 is based on not sharing the SSCs important to safety between the units (except as identified). 4. Acceptance for meeting the relevant aspects of GDC 26 is based on the provision of two independent reactivity control systems of different design principles (control rod drive system and SLCS system). 5. Acceptance for meeting the relevant aspect of GDC 27 is based on the system having suitable redundancy in components and features to assure system safety function assuming a single failure. For some newer designs such as the ESBWR, GDC 27 is met by the provision of SLCS as part of the ECCS. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. Compliance with GDC 2 requires that nuclear power plant SSCs important to safety be designed to withstand the effects of seismic events and other natural phenomena without loss of capability to perform their safety functions. The subject SSCs are those necessary to ensure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe-shutdown condition, or (3) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guideline exposures of 10 CFR Part 100. Since the SLCS provides one means to shut down the reactor and maintain it in a safe- shutdown condition, the SLCS, and structures housing the SLCS, must be capable of withstanding the effects of natural phenomena. Based on reviewing a number of safety analysis reports (SARs)