The inspectors identified an
NCV of
10 CFR 72.146, Design Control, for the licensees failure to perform adequate evaluations to ensure compliance with
10 CFR 72.212(b)(3) and
10 CFR 72.122 (b)(2)(i). Specifically, the inspectors identified that the licensee failed to evaluate that the reactor site parameters including analyses of tornado effects were enveloped by the cask design basis, and perform additional analysis to ensure compliance with
10 CFR 72.122(b)(2)(i). The licensee documented the condition in
IR 1137279 and initiated a new calculation to demonstrate compliance. Because this violation was related to an
ISFSI license, it was dispositioned using the traditional enforcement process in accordance with Section 2.2 of the
Enforcement Policy. The violation was determined to be of more than minor significance because the licensee failed to have an evaluation to assure transfer cask (HI-TRAC) integrity during a tornado event and an additional calculation was required. The licensees new calculation determined that overturning and sliding of the HI-TRAC on the refuel floor would not occur during a tornado. Therefore, the violation screened as having very low safety significance (
Severity Level IV).
