ENS 49121
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ENS Event | |
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04:00 Jun 16, 2013 | |
Title | Technical Specification Shutdown Due to Small Reactor Coolant Leak on a Recirculation Flow Control Valve Vent Line |
Event Description | This event is being reported in accordance with 10 CFR 50.72(b)(2)(i) and 50.72(b)(3)(ii)(A).
On June 16, 2013 at 0200 EDT, the Perry Nuclear Power Plant commenced a controlled plant shutdown. The shutdown was due to a small leak through the base of a vent line on the 'B' Reactor Recirculation Flow Control Valve. On June 15, 2013 at 2250 EDT, the leak was identified and was subsequently determined to require a plant shutdown in accordance with Technical Specification 3.4.5, Action (C) which 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 />. The NRC Resident Inspector has been notified." The licensee will also be notifying state and local authorities. The licensee had come down in power to make a drywell entry and investigate drywell leakage indications. Steam was observed to be coming from a vent line that comes off the top of the recirc flow control valve. The licensee was unable to characterize the leak rate other than a small leak. The licensee stated that the steam appeared be coming from a weld location where the vent line comes out of the flow control valve which would classify it as pressure boundary leakage. |
Where | |
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Perry Ohio (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
LER: | 05000440/LER-2013-003 |
Time - Person (Reporting Time:+-1.3 h-0.0542 days <br />-0.00774 weeks <br />-0.00178 months <br />) | |
Opened: | Robert Kidder 02:42 Jun 16, 2013 |
NRC Officer: | Bill Huffman |
Last Updated: | Jun 16, 2013 |
49121 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (8 %) |
After | Power Operation (8 %) |
Perry with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
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 407742004-05-24T19:00:00024 May 2004 19:00:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Emergency Service Water Failure 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 | |
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