Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
guide structures under SRP Sections 3.6.2, 3.9.2, 3.9.3, 3.9.4, and 3.9.5. On request from the lead reviewer for this section, the reviewer of the interfacing section verifies that the core remains in a coolable geometry following a loss-of-coolant accident and that the control rods can also be inserted for breaks crediting this function. Analyses of the deformed bundle in the core should be performed to show that the acceptance criteria of 10 CFR 50.46 are met. On request, the mechanical engineering reviewer verifies that acceptable criteria have been employed in the design of the reactor coolant system and its supports to prevent failures of the reactor coolant pressure boundary and engineered safety feature equipment in the event of a LOCA. 9. Plant operating procedures are reviewed under SRP Section 13.5.2.1. On request, plant operating procedures are reviewed to verify that they include actions relative to reactor coolant pump trip following small break LOCAs that are based on plant-specific safety evaluations. 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. 10 CFR 50.46 as it relates to ECCS equipment being provided that refills the vessel in a timely manner for a loss-of-coolant accident resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary. 2. GDC 13 as to the availability of instrumentation to monitor variables and systems over their anticipated ranges to assure adequate safety, and of appropriate controls to maintain these variables and systems within prescribed operating ranges. 3. General Design Criterion (GDC) 35 as it relates to demonstrating that the ECCS would provide abundant emergency core cooling to satisfy the ECCS safety function of transferring heat from the reactor core following any loss of reactor