ENS 49977
ENS Event | |
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18:02 Mar 31, 2014 | |
Title | Unit 2 Reactor Pressure Boundary Leakage and Unit Shutdown |
Event Description | On March 31, 2014, at 1302 [CDT], with Unit 2 operating in Mode 1 (coastdown), leakage was identified from the body of a one inch isolation valve associated with a Control Rod Drive Hydraulic Control Unit (CRD HCU 18-27 insert valve 101). The leakage is several drops per minute; attempts to isolate the leak have been unsuccessful. The associated piping communicates with the reactor coolant system (through the CRD mechanism).
Technical Specification 3.4.4 (RCS Operational Leakage), Condition C, was entered at 1302 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.95411e-4 months <br />. Condition C requires the unit to be placed in Mode 3 (Hot Shutdown) in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. At 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br />, a Technical Specification required shutdown was initiated on Unit 2. The cause and resolution of the leakage are being pursued. This condition is being reported under 50.72(b)(3)(ii)(A) given the defect is associated with the primary coolant system pressure boundary. This notification is also being made in accordance with 10 CPR 50.72(b)(2)(i) given the initiation of a plant shutdown required by the plant Technical Specifications. The licensee has notified the NRC Resident Inspector. |
Where | |
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Quad Cities Illinois (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: | 05000265/LER-2014-001 |
Time - Person (Reporting Time:+0.92 h0.0383 days <br />0.00548 weeks <br />0.00126 months <br />) | |
Opened: | William Strickland 18:57 Mar 31, 2014 |
NRC Officer: | Jeff Rotton |
Last Updated: | Mar 31, 2014 |
49977 - NRC Website
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Unit 2 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (87 %) |
After | Power Operation (54 %) |
Quad Cities with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 499772014-03-31T18:02:00031 March 2014 18:02:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 2 Reactor Pressure Boundary Leakage and Unit Shutdown ENS 488532013-03-27T07:45:00027 March 2013 07:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Boundary Leakage ENS 478062012-04-04T22:16:0004 April 2012 22:16:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Identified Reactor Pressure Vessel Test Leakage ENS 477992012-04-02T19:52:0002 April 2012 19:52:00 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 Initiation of Reactor Shutdown Required by Technical Specifications (Ts) 3.8.1.F ENS 453332009-09-09T01:10:0009 September 2009 01:10:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Reactor Shutdown Required by Technical Specifications Due to an Unisolable Leak in a Core Spray Minimum Flow Line ENS 429042006-10-13T15:34:00013 October 2006 15:34:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Initiation of Reactor Shutdown Required by Technical Specification 3.1.7, Action C.1 ENS 424552006-03-31T03:00:00031 March 2006 03:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Feedwater Check Valve Leakage Above Allowable Limits ENS 422602006-01-15T17:04:00015 January 2006 17:04:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Ts Shutdown Due to Electromatic Relief Valves (Ervs) Declared Inoperable 2014-03-31T18:02:00 | |