Document: NUREG-0800
Document ID: d5a274a9-ea29-4a99-9cbe-73eefa2e90f4
Document Type: srp
Title: REACTOR CORE ISOLATION COOLING SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340631.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.6
CFR Part: 
CFR Title: 

Content:
RCIC system, as part of its primary review responsibility for SRP Sections 6.2.4 and 6.2.6 to confirm that the design is compatible with the containment system and can be isolated. The Instrumentation and Control Systems Branch (ICSB), as part of its primary review responsibility for SRP Section 7.4, evaluates the adequacy of controls and instrumentation of the RCIC system with regard to the required features of automatic actuation, remote sensing and indication, and remote control. The Power Systems Branch (PSB), as part of its primary review responsibility for SRP Section 8.3, evaluates the adequacy of emergency onsite power, sufficiency of battery capacity, and the use of d-c power only. The MEB, as part of its primary review responsibility for SRP Section 3.9.3, ensures that the design and installation of the RCIC system meet applicable codes and are adequate for 5.4.6-2 Rev.-3 - April 1984 its proper functioning. The Equipment Qualification Branch (EQB) reviews RCIC system equipment to determine that it is seismically and environmentally qualified for its intended use as part of its primary review responsibility for SRP Sections 3.10 and 3.11. For those areas of review identified above as being reviewed as part of the primary review responsibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section of the corresponding primary branch. II. ACCEPTANCE CRITERIA RSB acceptance criteria are based on meeting the relevant requirements of General Design Criteria 4, 5, 29, 33, 34 and 54. Specific criteria to meet the requirements of the above GDCs are as follows: A. General Design criteria 4, as related to dynamic effects associated with flow instabilities and loads (e.g., water hammer). l B. General Design Criterion 5 as it relates to structures, systems and components important to safety not being shared among nuclear power units unless it can be demonstrated that sharing will