Criticality Safety Evaluation Report for the Multi-Canister Overpack

Packaging Design Criteria for the MCO Cask

“…Mark IA fuel as two uranium enrichments, 0.95% and 1.25% 235U~ The Mark IV fuel has one enrichment, 0.95% 235U. Further details concerning the fuel criticality source term is described in HNF-SD-SNF-CSER-005, Critical@ Sajety Evaluation Report for the Multi-Canister Overpack (Kessler 2000). HNF-SD-TP-PDC-030, Rev.…”

Spent Nuclear Fuel (SNF) Project Product Specification

“…Criticality analyses (Kessler 1999) are based on loading configurations where scrap baskets are located in either the top, the bottom, or in both positions of an MCO. Thermal analyses of process steps are documented in Plys and Duncan (1998a) based on configurations where scrap baskets are located in either the top, or top and bottom positions of an MCO.…”

Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 3]

“…in cross section are loaded into the MCO using scrap baskets. HNF-SD-SNF-CSER-005, Criticality Safety Evaluation Report for Spent Nuclear Fuel Processing andstorage Facilities (Kessler 2000), allows up to two scrap baskets, one at each end of the MCO. The limits on scrap basket loading are defined in HNF-SD-SNF-CSER-010, Criticality Safely Evaluation Report for the K Basin Fuel Retrieval Subproject (Kessler and Peck 2000) In addition, no scrap basket can be loaded to a weight exceeding that of a maximum weight fuel basket.…”

“…Additional detail on the drop analyses is presented in Chapter 3.0. A loaded basket subject to criticality controls required in HNF-SD-SNF-CSER-005, (Kessler 2000), such as the Mark 1.4, must not have or be subjected to stress levels higher than HNF-SD-SNF-SAM-005 REV 2 the applicable service level requirements allowed in the Boiler and Pressure Vessel Code (ASME 1998), Subsection NG; any exceptions to this will be noted and defined; handling loads for both loaded and unloaded baskets will include a safety factor of three on material yield and five on material ultimate strength of the baskets.…”

“…A criticali9 safety value of 0.95 for &is used for the MCO design, functions, and related activities (-i n 1998). According to criticality analyses (Kessler 2000), this will be satisfied for MCOs co taining Mark IA fuel by ensuring a nominal 6.625-in.-diameter steel insert (center post) at the t ~ ongitudinal centerline of the MCO. This insert is a stainless steel bar with a 6 .…”