Read or Download System 80+ Standard [nucl. powerplnt] Design - Final Safety Eval Rpt Vol 2 PDF
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Extra info for System 80+ Standard [nucl. powerplnt] Design - Final Safety Eval Rpt Vol 2
Sample text
In the DSER, the staff asked ABB-CE to perform a sensitivity study and demonstrate that the LBLOCA with the maximum SI flow is the limiting case for the System 80+ design. 6-1. t Because the System 80+ emergency core cooling (ECC) system has direct ECC injection into the reactor vessel downcomer, the staff reviewed the applicability of the existing ABB-CE LOCA evaluation model (EM), which was developed for plants with cold-leg injection. The LOCA EM assumes complete ECC bypass up to the end of bypass; therefore, it complies with the Appendix K requirement with regard to the blowdown phase.
24, assuring the fuel integrity throughout the event. 3, ABB-CE presents results of the LOCA analysis. 1 of this chapter: CEFLASH-4A large-break LOCA (LBLOCA) and CEFLASH-4AS small-break LOCA (SBLOCA) for the system response during the blowdown phases, STRIKIN-II for calculating the hot rod cladding temperature, HCROSS and PARCH for calculating the steam cooling heat transfer coefficient, and COMZIRC for determining the core-wide cladding oxidation. " (2) Maximu m Cladding Oxidation -- "The calculated total oxidation of the cladding shall nowhere exceed NUREG-1462 Transient and Accident Analyses o.
The FLB blowdown models resulted in high mass flow and low energy flow from the SG, thereby minimizing the ruptured SG heat removal capacity. 3-A (Amendment U), ABB-CE stated that for the FLB analysis, the heat transfer area was assumed 15-16 Transient and Accident Analyses at design value until the SO liquid inventory decreasedto 225 kg (500 Ibm). The heattransferareais then decreased to zero over the time interval for inventory to decreaseby 225 kg (500 Ibm). 2 percent of the initial inventory.
System 80+ Standard [nucl. powerplnt] Design - Final Safety Eval Rpt Vol 2
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