ENS 53597: Difference between revisions

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| event text = 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.  
| event text = 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 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."
The NRC Resident Inspector has been notified.
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/20180912en.html#en53597
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/20180912en.html#en53597
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Latest revision as of 00:03, 24 February 2020

ENS 53597 +/-
Where
Monticello Xcel Energy icon.png
Minnesota (NRC Region 3)
Reporting
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 />)
Opened: Rodney Coons
18:42 Sep 11, 2018
NRC Officer: Steven Vitto
Last Updated: Sep 11, 2018
53597 - NRC Website
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