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Part 50.54(q) of 10 CFR required that the 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 significanceined to be of very low safety significance  +
23:59:59, 31 March 2008  +
05000282  +  and 05000306  +
23:59:59, 31 March 2008  +
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15:35:17, 30 May 2018  +
23:59:59, 31 March 2008  +
Licensee-Identified Violation  +