Preclosure Criticality Safety Analysis
| Attachment | Size |
|---|---|
| PRECLOSURE CRITICALITY SAFETY ANALYSIS.pdf (8.23 MB) | 8.23 MB |
The means to prevent and control criticality must be addressed as part of the Preclosure Safety Analysis (PCSA) required for compliance with 10 CFR Part 63 [DIRS 180319], where the preclosure period covers the time prior to permanent closure activities. This technical report presents the nuclear criticality safety evaluation that documents the achievement of this objective.
This report is the primary preclosure criticality safety reference for the License Application and it is structured as described below to allow for direct correlation with the content in the License Application.
Section 2.1 presents the preclosure criticality safety regulatory requirements and the project criteria applied to address those requirements
Section 2.2 describes the analysis process implemented to comply with the project criteria
Section 2.3 presents the detailed criticality safety analysis including a summary of the waste forms and their packaging (Section 2.3.1), a discussion of criticality control parameters (Section 2.3.2), and the criticality safety evaluation for each of the seven facilities in which fissile material could be present (Initial Handling Facility (IHF), Receipt Facility (RF), Canister Receipt and Closure Facility (CRCF), Wet Handling Facility (WHF), Intrasite Operations including Aging Facility, Low-Level Waste Facility, and Subsurface Facility (Sections 2.3.3 through 2.3.9)
Section2.3.10 defines the Criteria to Establish Subcriticality and provides the justification of the administrative margin to ensure subcriticality
Section 2.3.11 presents the evaluation of the need for a criticality accident alarm system (CAAS)
Section 2.3.12 discusses offsite operations and their impact on preclosure criticality safety
