The inspectors identified a
Severity Level IV NCV of
10 CFR 72.212(b)(6), Conditions of General License Issued under 72.210, for the failure of thelicensee as of June 9, 2003, to determine whether or not reactor site parameters were enveloped by the cask design bases as considered in the
Updated Final Safety Analysis Report (
UFSAR). Specifically, the licensee failed to evaluate site-specific fire and explosion hazards that were allowed to be near the dry cask storage systems under its Administrative Control Procedure (
ACP) 1412.2, Control of Combustibles, Revision 48. The licensee documented this issue in its
CAP as CR 02228514 and CR 02228558 and took timely corrective actions.The inspectors determined that the violation was of more than minor significance using
IMC 0612, Power Reactor Inspection Reports, Appendix E, Examples of Minor Issues. Example 4k is applicable to this issue in that the lack of evaluation showing that the quantity of combustible and flammable liquids stored near the dry cask storage system were bounded by the design basis in the
UFSAR allowed for a credible unanalyzed fire and explosion scenario that could affect the important-to-safety dry cask storage system. The violation screened as a
Severity Level IV NCV. Cross-cutting aspects are not assigned to traditional enforcement violations.
