Document: NUREG-0800
Document ID: 96ddbfc8-7fd0-4a33-9fbe-144d653b6e9f
Document Type: srp
Title: REACTOR CORE ISOLATION COOLING SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070433.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.6
CFR Part: 
CFR Title: 

Content:
he review has included the applicant's proposed design criteria and design bases for the RCIC system, his analysis of the adequacy of the criteria and bases, and the conformance of the design to these criteria and bases. The staff concludes that the reactor core isolation cooling system design is acceptable and meets the requirements of General Design Criteria 4, 5, 29, 33, 34, and 54, and 10 CFR 50.63. This 111 conclusion is based on the following: 1. The applicant has met the requirements of (cite Reg.) with respect to (state limits of review) by: (Use one or more of the following as applicable) a. meeting the regulatory position in Regulatory Guide ________, b. providing and meeting an alternative method to the regulatory position in Regulatory Guide ________, that the staff has reviewed and found to be acceptable, c. meeting the regulatory position in BTP ________ DRAFT Rev. 4 - April 1996 5.4.6-14 d. The calculational method used by the applicant for (state) has been previously reviewed by the staff and found acceptable; the staff has reviewed the key parameters in this case and found them to be suitably conservative. e. The applicant has met the requirements of (industry standard - number and title) that has been reviewed by the staff and determined to be appropriate for this application. 2. Repeat the above discussion for each GDC listed. In addition, conformance with General Design Criteriona 55, 56, and 57 regarding 112 containment isolation is discussed in Section 6.2 of this report. Conformance with General Design Criteriona 2 and 4 for protection against natural phenomena, environmental hazards 113 and potential missiles is discussed in Sections 3.3 through 3.6 of this report. The RCIC and HPCS (or HPCI) systems, in conjunction with the safety/relief valves and the suppression pool cooling mode of the residual heat removal system, have been found capable of removing core decay heat following feedwater system isolation and reactor shutdown so that