Document: NUREG-0800
Document ID: eb0ea00d-43e4-45d1-8a5e-4daa4263d2cf
Document Type: srp
Title: EMERGENCY CORE COOLING SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550068.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.3
CFR Part: 
CFR Title: 

Content:
to assure that they are consistent with the intent of Regulatory Guides 1.68. 21. Review of compliance of Task Action Plan items I.C.2 and I.C.6 of the NUREG-0737 requirements regarding procedures to assure that system operability status is known is performed under SRP Section 13.5.1. 22. Review of quality assurance is performed under SRP Sections 17.5. 23. Review of compliance with Task Action Plan items II.B.2 of NUREG-0737 and NUREG-0718 requirements regarding radiation and shielding design review is performed under SRP Sections 12.1 through 12.5 to assure adequate access to vital areas and protection of safety equipment. 24. Review of technical specifications is performed under SRP Section 16.0. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion (GDC) 2 as it relates to the seismic design of structures, systems, and components (SSCs) whose failure could cause an unacceptable reduction in the capability of the ECCS to perform its safety function. 2. GDC 4 as it relates to dynamic effects associated with flow instabilities and loads (e.g., water hammer). 3. GDC 5 as it relates to SSCs important to safety shall not be shared among nuclear power units unless it can be demonstrated that sharing will not impair their ability to perform their safety function. 4. GDC 17 as it relates to the design of the ECCS having sufficient capacity and capability to assure that specified acceptable fuel design limits and the design conditions of the reactor coolant pressure boundary are not exceeded during anticipated operational occurrences and that the core is cooled during accident conditions. 5. GDC 27 as it relates to the system design having the capability to assure that under postulated accident conditions and with appropriate margin for stuck rods, the