ML24215A085
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Response to SDAA Audit Question Question Number: A-4.3-3 Receipt Date: 04/10/2023 Question:
Provide the core loading and operating conditions assumed when determining control rod worths. The assumed core loading and operating conditions should include, but are not limited to, the fuel enrichment distribution in the fuel assembly (both axially and radially across each fuel assembly batch), the core power level, temperature, moderator density, soluble boron concentration, and assumed control rod insertion. The impacts of reduced uranium enrichment blankets need to be included in the calculation as well.
Response
The pertinent core operating conditions associated with the individual control rod worths are provided in Table 1. Final Safety Analysis Report Figure 4.3-2 provides the core loading pattern.
Figures 1 through 3 provide the corresponding fuel assembly radial fuel enrichment distributions on an one-eighth assembly basis. The equilibrium cycle does not assume axial blankets, so there is no axial variation of the fuel pin enrichment.
NuScale Nonproprietary NuScale Nonproprietary
((2(a),(c),ECI NuScale Nonproprietary NuScale Nonproprietary
(( }}2(a),(c),ECI NuScale Nonproprietary NuScale Nonproprietary
(( }}2(a),(c),ECI Acronyms: ARO all rods out BOC beginning of cycle EOC end of cycle GT guide tube HZP hot zero power IT instrumentation tube MOC middle of cycle PDIL power dependent insertion limits wt% weight percent No changes to the SDAA are necessary. NuScale Nonproprietary NuScale Nonproprietary}}