ENS 45434
ENS Event | |
|---|---|
16:25 Oct 15, 2009 | |
| Title | Unit Commenced Shutdown Due to Inoperable Division 2 Emergency Service Water System |
| Event Description | This event is being reported in accordance with 10CFR50.72(b)(2)(i). On October 15, 2009, at approximately 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br />, the Perry Nuclear Power Plant commenced a Technical Specification required plant shutdown.
On October 14, 2009, At 1747 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.647335e-4 months <br />, the Division 2 Emergency Service Water (ESW) system was declared inoperable and unavailable for planned work. The plant entered Technical Specification (TS) 3.7.1 Action A for one inoperable ESW Division. Other supported TSs were also entered (TS 3.8.1 for the Division 2 diesel generator, TS 3.6.1.7 for Containment Spray 'B', TS 3.6.2.3 for Suppression Pool Cooling 'B', TS 3.7.10 for Emergency Closed Cooling 'B', TS 3.5.1 for LPCI 'B' & 'C', among others). On October 15, 2009, at 0601 hours0.00696 days <br />0.167 hours <br />9.937169e-4 weeks <br />2.286805e-4 months <br />, the ESW 'B' pump was started for a planned pump run. At 0718 hours0.00831 days <br />0.199 hours <br />0.00119 weeks <br />2.73199e-4 months <br />, the ESW 'B' pump tripped for unknown reasons. The determination was made to commence a controlled plant shutdown and power reduction commenced at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br />. This decision was based on the anticipated investigation and repair time of ESW 'B' pump exceeding the TS 3.7.1 Action A 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO completion time, and therefore, Action B requires the plant to be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The TS 3.7.1 Action A 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO completion time coincides with October 17, 2009, at 1747 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.647335e-4 months <br />. Currently, the plant is expected to be in MODE 3 at approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on October 15, 2009. The NRC Resident Inspector has been notified. The State and Counties will also be notified. |
| Where | |
|---|---|
Perry  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
| LER: | 05000440/LER-2009-003 |
| Time - Person (Reporting Time:+-1.63 h-0.0679 days <br />-0.0097 weeks <br />-0.00223 months <br />) | |
| Opened: | Michael Nemcek 14:47 Oct 15, 2009 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Oct 15, 2009 |
| 45434 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (75 %) |
WEEKMONTHYEARENS 571362024-05-23T08:00:00023 May 2024 08:00:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 530002017-10-04T06:50:0004 October 2017 06:50:00 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, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Perry Commenced Technical Specification Required Shutdown 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 498042014-02-07T11:00:0007 February 2014 11:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Required by Technical Specifications Due to Containment Isolation Valve Over Leak Rate Limit ENS 491212013-06-16T04:00:00016 June 2013 04:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Shutdown Due to Small Reactor Coolant Leak on a Recirculation Flow Control Valve Vent Line ENS 473122011-10-02T05:00:0002 October 2011 05:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shutdown Required by Technical Specifications Due to Transformer Fault 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 454342009-10-15T16:25:00015 October 2009 16:25:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit Commenced Shutdown Due to Inoperable Division 2 Emergency Service Water System ENS 416572005-05-02T10:11:0002 May 2005 10:11:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown - Reactor Vessel Level Instrumentation ENS 410852004-10-02T19:00:0002 October 2004 19:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Reactor Power Being Reduced Due to Entering Ts 3.0.3 Because of Inopeable Recirc Vent System ENS 407672004-05-21T20:00:00021 May 2004 20:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown 2024-05-23T08:00:00 | |