15 ACCIDENT ANALYSIS 15.1 Conduct of Review

Safety Analysis Report (SAR) (Pacific Gas and Electric Company, 2004a). The staff also reviewed documents cited in the SAR, and other relevant publicly available information, including web sites on the Internet. The applicant evaluated off-normal events and accidents associated with the transfer of HI-STAR HB casks from the Refueling Building (RFB) to the proposed Humboldt Bay ISFSI site, lowering of the casks from the transporter to the reinforced concrete storage vault, and interim storage of the casks in the vault. HI-STAR HB cask handling activities inside the RFB fall within the scope of the 10 CFR Part 50 license, and hence, off-normal events and accidents associated with HI-STAR HB cask operations within the RFB were not addressed in this Safety Evaluation Report (SER). As discussed in Chapter 5 of this SER, the dry-cask storage system to be used at the proposed facility is the HI-STAR HB System, which is a modified version of the HI-STAR 100 cask system (Holtec International, 2002). The U.S. Nuclear Regulatory Commission has certified the HI-STAR 100 cask system for use by 10 CFR Part 50 licensees under the general license provisions of 10 CFR §72.210 (U.S. Nuclear Regulatory Commission 2001a). Thus, where applicable, the staff relied on the review carried out during the certification process of that cask system, as documented in the HI-STAR 100 Cask System SER (U.S. Nuclear Regulatory Commission, 2001b). The HI-STAR HB system consists of the MPC-HB, which is a seal-welded canister containing 80 spent nuclear fuel (SNF) assemblies; an optional damaged fuel container(s), which can be inserted into an MPC-HB and can hold an intact fuel assembly or damaged fuel; and the HI-STAR HB storage overpack (or cask). This review considered how the SAR and related documents address the regulator