ML23304A465

LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to SDAA Question 11.1-3, Re Information Related to Source Terms

ML23304A465
Person / Time
Site:	05200050
Issue date:	10/31/2023
From:	NuScale
To:	Office of Nuclear Reactor Regulation
Shared Package
ML23306A049	List: ML23304A397 ML23304A446 ML23304A447 ML23304A448 ML23304A449 ML23304A450 ML23304A451 ML23304A464 ML23304A465 ML23304A466 ML23304A467 ML23304A468 ML23304A469 ML23304A470 ML23304A471 ML23304A472 ML23304A473 ML23304A474 ML23304A475 ML23304A476 ML23304A477 ML23304A478 ML23304A479 ML23304A480 ML23304A482 ML23304A483 ML23304A485 ML23304A486 ML23304A487 ML23304A488 ML23304A489 ML23304A490 ML23304A492 ML23304A493 ML23304A494 ML23304A495 ML23304A496 ML23304A516 ML23304A517 ML23304A519 ML23304A521 ML23304A522 ML23304A524
References
LO-152560
Download: ML23304A465 (1)

Text

NuScale Nonproprietary Response to SDAA Audit Question Question Number: A-11.1-3 Receipt Date: 05/30/2023 Question:

NRC staff requests NuScale explain the apparent discrepancy between the full power steam flow rate found in Table 10.3-1 (8.14E5 lb/hr) and the secondary coolant flow rate found in Table 11.1-2 (6.5E5 lb/hr). Staff notes that in the previous DCD submittal these values appeared consistent with each other.

Response

Table 11.1-2 lists parameters used to calculate coolant source terms. The secondary coolant flow rate used to calculate secondary coolant source terms is based on a conservatively low secondary coolant flow rate. Table 10.3-1 lists main steam system design data. The full power main steam flow design is greater than the conservatively low flow rate used in the analysis to calculate secondary coolant source terms.

No changes to the SDAA are necessary.

NuScale Nonproprietary