ENS 53546
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ENS Event | |
|---|---|
05:00 Aug 10, 2018 | |
| Title | Emergency Diesel Generator Cooling Water Pumps Declared Inoperable |
| Event Description | On 8/10/2018 at 1445 [CDT] both trains of Cooling Water [Cooling Water Pumps for Emergency Diesel Generators] were declared INOPERABLE and both units entered [Technical Specification] (TS) 3.0.3 due to corroded jacket cooling water plugs for [the] 12 and 22 cooling water pump motors; therefore this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). At 1543 [CDT], 08/10/2018 the 121 Cooling Water pump was aligned to the "A" Cooling Water train and the TS 3.0.3 condition was exited for both units. [After restoring train A cooling water the site entered a seven day limiting condition for operations, TS 3.7.8 for one inoperable cooling water pump.]
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
Testing and forensic analysis performed subsequent to the notification has determined the as-found condition would not have impacted either diesel-driven pumps' ability to start, run, and meet flow/pressure requirements to perform their required safety function. Therefore, EN# 53546 is being retracted. The NRC Resident Inspector has been notified of the Event Notification retraction. Notified R3DO (Kozak). |
| Where | |
|---|---|
Prairie Island  Minnesota (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | |
| Time - Person (Reporting Time:+18.22 h0.759 days <br />0.108 weeks <br />0.025 months <br />) | |
| Opened: | Jeffrey Human 23:13 Aug 10, 2018 |
| NRC Officer: | Ossy Font |
| Last Updated: | Sep 29, 2018 |
| 53546 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Prairie Island with 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
WEEKMONTHYEARENS 555292021-10-18T00:30:00018 October 2021 00:30:00
[Table view]10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Emergency Diesel Generators Simultaneously Inoperable ENS 538532019-01-31T13:43:00031 January 2019 13:43:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident En Revision Imported Date 3/25/2019 ENS 535462018-08-10T05:00:00010 August 2018 05:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Emergency Diesel Generator Cooling Water Pumps Declared Inoperable ENS 530672017-11-12T09:03:00012 November 2017 09:03:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Containment Spray Pump Control Switches Out of Service ENS 514292015-09-28T18:27:00028 September 2015 18:27:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Unit 1 Emergency Diesel Generators Inoperable at the Same Time ENS 508262015-02-16T22:44:00016 February 2015 22:44:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Special Vent Boundary Inoperable ENS 508012015-02-10T08:50:00010 February 2015 08:50:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Voids Identified That Result in an Unanalyzed Condition ENS 504922014-09-24T20:33:00024 September 2014 20:33:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Unit 1 Train B Rvlis and Iccm Inoperable Due to Data Errors ENS 501702014-06-04T00:02:0004 June 2014 00:02:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Diesel Generators Declared Inoperable Due to Not Meeting High Energy Line Break Requirements ENS 496852013-12-31T15:33:00031 December 2013 15:33:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Removal of Multiple Steam Generator Lateral Support Shims and Bumpers ENS 486192012-12-21T15:00:00021 December 2012 15:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Unit Two Auxiliary Feedwater Pumps Declared Inoperable ENS 481862012-08-14T08:12:00014 August 2012 08:12:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Based on Both Emergency Diesels Being Declared Inoperable ENS 481222012-07-20T19:00:00020 July 2012 19:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Unit 2 Emergency Diesel Generators Inoperable Due to Missing Flood Control Barrier Seal ENS 480632012-07-02T20:51:0002 July 2012 20:51:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Both Diesel Generators Declared Inoperable ENS 473212011-10-05T12:27:0005 October 2011 12:27:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Two Loops of Reactor Coolant System (Rcs) Were Declared Inoperable ENS 470102011-06-27T18:44:00027 June 2011 18:44:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Offsite Power Sources Declared Inoperable ENS 469342011-06-07T18:49:0007 June 2011 18:49:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Emergency Diesel Generators Declared Inoperable Due to Excess Outside Ambient Air Temperature ENS 459972010-06-09T16:35:0009 June 2010 16:35:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Battery Rooms Declared Inoperable Due to Potential Flooding ENS 459372010-05-19T21:40:00019 May 2010 21:40:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Trains of Residual Heat Removal (Rhr) Inoperable ENS 458552010-04-19T03:25:00019 April 2010 03:25:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Lco 3.0.3 Entry and Loss of Safety Function Due to Loss of Turbine Building High Energy Line Break Compensatory Measure ENS 449312009-03-23T22:00:00023 March 2009 22:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for Postulated Missile Hazard That Could Disable Both Trains of Component Cooling ENS 448592009-02-17T17:00:00017 February 2009 17:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Emergency Diesel Generators Declared Inoperable After Review of Work Boundary Isolation 2021-10-18T00:30:00 | |
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