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05:00 Sep 11, 2018
On 9/10/2018, the 11 Core Spray (CSP) loop was placed in service to support quarterly surveillance testing. With the 11 CSP pump in service it was identified that the check valves isolating the 11 CSP system from the keep fill supply were leaking by. At 1129 CDT on 9/11/2018, it was identified that this leakage may have exceeded the leakage rate assumptions made in the dose analysis calculation for emergency core cooling system (ECCS) leakage outside containment following a loss of coolant accident (LOCA). Therefore, this is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition that significantly degrades plant safety and 10 CFR 50.72(b)(3)(v) for any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.
The potential ECCS leak pathway has been isolated. There is no impact to health and safety of the public.The NRC Resident Inspector has been notified.
Minnesota (NRC Region 3)
|10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition|
10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material
10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
|Time - Person (Reporting Time:+13.7 h0.571 days <br />0.0815 weeks <br />0.0188 months <br />)|
18:42 Sep 11, 2018
|NRC Officer:||Steven Vitto|
|Last Updated:||Sep 11, 2018|
|53597 - NRC Website|
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