Commercial Spent Nuclear Fuel Waste Package Misload Analysis
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The purpose of this calculation is to estimate the probability of misloading a commercial spent
nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or
burnup) outside the waste package design. The waste package designs are based on the expected
commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1
and Table 1). For this calculation, a misloaded waste package is defined as a waste package that
has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package
design. An example of this type of misload is a fuel assembly designated for the 21-PWR
Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste
package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the
reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel
assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of
misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are
the only types that are evaluated in this calculation. This calculation utilizes information from
Frequency of SNF Misload for Uncanistered Fuel Waste Package (CRWMS M&O 1998) as the
starting point.
The scope of this calculation is limited to the information available. The information is based on
the whole population of fuel assemblies and the whole population of waste packages, because
there is no information about the arrival of the waste stream at this time. The scope of this
calculation deviates from that specified in Technical Work Plan for: Risk and Criticality
Department (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The
remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed
elsewhere.
The intended use of the calculation is to provide information and inputs to the Preclosure Safety
Analysis Department. Before using the results of this calculation, the reader is cautioned to
verify that the assumptions made in this calculation regarding the waste stream, the loading
process, and the staging of the spent nuclear fuel assemblies are applicable.
