ENS 43049
ENS Event | |
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09:35 Dec 13, 2006 | |
Title | |
Event Description | A loss of instrument air caused a transient in feed system causing a lowering Hot Surge Tank Level. The Reactor was manually scrammed when Reactor Feed Booster Pumps were cavitating. Control Rod 42-55 did not insert on the initial scram. Control Rod 42-55 did insert when ARI was manually initiated.
The loss of instrument air was the result of an air line rupture, and the licensee is steaming to the condenser while maintaining vessel level with feedwater. There was no ECCS injection, and the licensee is investigating the cause of the line rupture. The licensee notified the NRC Resident Inspector.
This update is being made in accordance with 10CFR50.72(c)(2) to immediately report the results of ensuing evaluations or assessments of plant conditions, the effectiveness of response or protective measures taken, and information related to plant behavior that is not understood. On December 13, 2006, at 0549 hours0.00635 days <br />0.153 hours <br />9.077381e-4 weeks <br />2.088945e-4 months <br />, the Perry Nuclear Power Plant notified the NRC Operations Center (Event Number 43049) of a manual Reactor Protection System actuation associated with a loss of instrument air. In the initial report, it was stated that control rod 42-55 did not insert on the initial scram, but did insert when Alternate Rod Insertion was manually initiated. Subsequently, reactor engineering review of control rod performance during the event determined that the control rod scram time for control rod 4255 was satisfactory and that the problem was with the control rod indication. The plant remains stable at this time. Control rod indication has two channels. Control rod 42-55 displayed one fully inserted indication and one blinking green indication (i.e. not fully inserted). When the system was reset, all rods indicated fully inserted with a "00" position indication. The licensee notified the NRC Resident Inspector. Notified the R3DO (Lara). |
Where | |
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Perry Ohio (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
LER: | 05000440/LER-2006-005 |
Time - Person (Reporting Time:+-3.77 h-0.157 days <br />-0.0224 weeks <br />-0.00516 months <br />) | |
Opened: | Robert Kidder 05:49 Dec 13, 2006 |
NRC Officer: | Joe O'Hara |
Last Updated: | Dec 13, 2006 |
43049 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | Yes, Manual Scram |
Before | Power Operation (100 %) |
After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 566732023-08-10T04:39:00010 August 2023 04:39:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip ENS 562982023-01-05T17:42:0005 January 2023 17:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram ENS 541852019-07-27T23:29:00027 July 2019 23:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to Main Turbine Trip ENS 538962019-02-25T05:24:00025 February 2019 05:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Generator Trip ENS 517162016-02-08T20:03:0008 February 2016 20:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Following Spurious Opening of Two Safety Relief Valves ENS 516792016-01-24T02:22:00024 January 2016 02:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Ts Required Shutdown Due to Unidentified Leakage in Drywell ENS 506012014-11-07T13:47:0007 November 2014 13:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to Loss of Feedwater ENS 505512014-10-20T06:18:00020 October 2014 06:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram on Loss of Feedwater ENS 486882013-01-22T08:32:00022 January 2013 08:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Protection System Actuation ENS 477102012-03-01T05:00:0001 March 2012 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Protection System Actuation Due to Automatic Turbine Runback ENS 459182010-05-12T03:18:00012 May 2010 03:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Manual Reactor Scram Due to Loss of Control Rod Drive Charging Water Header Pumps ENS 454402009-10-16T04:48:00016 October 2009 04:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 451472009-06-21T21:50:00021 June 2009 21:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Related to a Main Turbine Trip ENS 438082007-11-28T12:32:00028 November 2007 12:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Reactor Scram and Eccs Injection ENS 433632007-05-15T04:58:00015 May 2007 04:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram During Testing ENS 430492006-12-13T09:35:00013 December 2006 09:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram - Loss of Instrument Air Resulting in Feedwater Transient and Manual Reactor Scram ENS 413102005-01-06T06:12:0006 January 2005 06:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 412902004-12-24T04:54:00024 December 2004 04:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram Following Down Shift of Both Recirc Pumps from Fast to Slow Speed 2023-08-10T04:39:00 | |