Part 50.54(q) of 10 CFR required that the licensee follow and maintain in effect
emergency plans which meet the standards in
10 CFR 50.47(b). Part 50.47(b)(8) of 10 CFR required that adequate emergency facilities and equipment to support the emergency response are provided and maintained. Prairie Island Nuclear Generating Plant
Emergency Plan, Revision 36, Section 7.1.1.B required that the
TSC have a shielding and ventilation cleanup system to provide habitability under accident conditions. As reported by the licensee in
Event Notification 44057, on March 12, 2008, the licensee completed a preliminary review of a revised dose analysis for the
TSC that showed that the whole body dose acceptance criteria of
NUREG-0696 could have been exceeded during an event and compensatory measures might be required. The licensee entered the issue into its corrective action program as
CAP 01130807. By the same logic as used for another
TSC finding discussed in Section 1R15 of this report, the
TSC function was considered to be degraded for more than seven days from
time of discovery, but still functional, and the violation was determined to be of very low safety significance
