Document: NUREG-0800
Document ID: ea7ce8f5-32bf-4d8c-a653-e964bff0ef48
Document Type: srp
Title: EMERGENCY CORE COOLING SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070448.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.3
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Reactor Systems Branch (RSB SRXB ) 1 Secondary - None I. AREAS OF REVIEW The RSB SRXB reviews the information presented in the applicant's safety analysis report 2 (SAR) regarding the emergency core cooling system (ECCS). The major elements of the review are: 1. Design Bases a. The design bases for the ECCS are reviewed to assure that they satisfy applicable regulations, including the general design criteria and the amendments torequirements of 10 CFR Part 50, §50.46 regarding ECCS acceptance criteria issued by the Commission on December 28, 1973 (Ref. 1). 3 b. The design basis for the BWR automatic depressurization systems (ADS) are also reviewed for compliance with TMI Action Plan Items and associated guidance.4 2. Design The design of the ECCS is reviewed to determine that it is capable of performing all of the functions required by the design bases. DRAFT Rev. 3 - April 1996 6.3-2 3. Test Program The preoperational and initial startup test programs for the ECCS are reviewed by the Procedures and Systems Review Branch (PSRB) Quality Assurance and Maintenance Branch (HQMB) to determine if they are sufficient to confirm the performance 5 capability of the ECCS. RSB SRXB reviews the need for special design features to 6 permit the performance of adequate test programs. 4. Technical Specifications The proposed technical specifications are reviewed to assure that they are adequate in regard to limiting conditions of operation and periodic surveillance testing. Review Interfaces:7 SRXB also performs the following reviews under the SRP sections indicated:8 1. As part of its primary review responsibility for SRP Section 3.12 (proposed), the SRXB reviews the design of the ECCS for evolutionary light-water reactor designs to verify, to the extent practical, that low-pressure portions of the ECCS that interface with the RCS will withstand full RCS pressure. If designing the ECCS with an ultimate rupture strength capable of withstanding