ENS 43430
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ENS Event | |
|---|---|
11:35 Jun 19, 2007 | |
| Title | Tech Spec Required Shutdown Due to Instrument Line Steam Leak |
| Event Description | During performance of a plant shut down personnel entered the Drywell to investigate a steam leak. At 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br />, personnel identified steam leaking from a flexible hose instrument line (approximately 1" diameter) that is welded to an elbow tap on the C Main Steam line and concluded that the leak constitutes pressure boundary leakage. This required entry into TS 3.4.5, Condition C. This requires that the unit be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, which is a TS required shutdown.
The station has determined that this event is reportable under the provisions of: 10 CFR 50.72 (b)(2)(i) for the plant shutdown required by Technical Specifications, as a 4-hour notification; 10 CFR 50.72 (b)(3)(ii)(A) as an event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded, as an 8-hour notification. The NRC resident inspector has been notified. The leaking line goes to a steam line flow instrument. The leak indication was first noticed yesterday and the licensee decided to shutdown to investigate before the leak was verified by the drywell entry. |
| Where | |
|---|---|
Clinton  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 | |
| Time - Person (Reporting Time:+-0.43 h-0.0179 days <br />-0.00256 weeks <br />-5.89014e-4 months <br />) | |
| Opened: | Ron Frantz 11:09 Jun 19, 2007 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Jun 19, 2007 |
| 43430 - NRC Website
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Clinton with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 533032018-03-30T18:05:00030 March 2018 18:05:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Primary Containment Declared Inoperable Due to Both Airlock Doors Open Simultaneously ENS 527502017-05-12T05:45:00012 May 2017 05:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Main Steam Isolation Valves Exceeded Primary Containment Local Leak Rate Acceptance Criteria ENS 519392016-05-17T14:45:00017 May 2016 14:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant Leakage with the Reactor in Cold Shutdown ENS 456762010-02-03T17:00:0003 February 2010 17:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Feedwater Check Valve Leak Rate Exceeded Technical Specification Requirement ENS 453902009-09-29T23:50:00029 September 2009 23:50:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Unidentified Leakage from Rcs ENS 434302007-06-19T11:35:00019 June 2007 11:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Tech Spec Required Shutdown Due to Instrument Line Steam Leak 2018-03-30T18:05:00 | |
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