ENS 48036
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ENS Event | |
|---|---|
21:20 Jun 19, 2012 | |
| Title | Mode Change Required by Technical Specifications |
| Event Description | On June 19, 2012, Unit 1 was shut down due to increasing drywell unidentified leakage. At 1720 EDT on June 19, 2012, the leakage location was discovered to be a welded joint on the 'A' reactor recirculation piping where a 4 inch blank-flanged pipe for chemical decontamination connects to the 28 inch pipe. This constitutes pressure boundary leakage. The location is within the recirculation loop isolation valves on the suction side of the recirculation pump, therefore isolable from the reactor vessel. The reactor was in mode 3 at the time of discovery and LCO 3.4.4 requires entry into mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
As such, the change in modes is required by Technical Specifications, therefore reportable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> under 10CFR50.72(b)(2)(i). In addition, the pressure boundary leakage at a welded joint is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)A) and is therefore 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable as well. The licensee notified the NRC Resident Inspector. A press release is planned by the licensee. |
| Where | |
|---|---|
Susquehanna  Pennsylvania (NRC Region 1) | |
| 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:+-1.53 h-0.0638 days <br />-0.00911 weeks <br />-0.0021 months <br />) | |
| Opened: | Todd Creasy 19:48 Jun 19, 2012 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Jun 19, 2012 |
| 48036 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Hot Shutdown (0 %) |
Susquehanna with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 564342023-03-26T20:03:00026 March 2023 20:03:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Leak Rate Limits Exceeded ENS 540782019-05-22T06:56:00022 May 2019 06:56:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 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 Technical Specification Required Shutdown ENS 519872016-06-08T06:26:0008 June 2016 06:26:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovery of Unisolable Reactor Pressure Boundary Leakage ENS 519832016-06-06T09:56:0006 June 2016 09:56:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Isolable Leakage Identified from Seal Water Line Weld Inside Rcs Pressure Boundary ENS 515382015-11-13T22:45:00013 November 2015 22:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Leakage from Pump Lower Seal Weld ENS 509762015-04-11T13:58:00011 April 2015 13:58:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Drywell Leakage Point Identified ENS 506862014-12-13T22:00:00013 December 2014 22:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Reactor Coolant Pressure Boundary ENS 500612014-04-27T03:22:00027 April 2014 03:22:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Minimum Pathway Limit of Msiv Combined Leakage Exceeded During Surveillance Testing ENS 493512013-09-16T18:55:00016 September 2013 18:55:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Caused by Rhr Relief Valve Leakage ENS 485952012-12-14T18:50:00014 December 2012 18:50:00 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 Technical Specification Required Shutdown - Control Structure Chillers Inoperable ENS 480362012-06-19T21:20:00019 June 2012 21:20:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Mode Change Required by Technical Specifications ENS 478122012-04-06T21:57:0006 April 2012 21:57:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Local Leak Rate Test Results Exceed Pathway Technical Specification Limits ENS 466542011-03-04T03:59:0004 March 2011 03:59:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Techncial Specification Required Shutdown Due to Inoperable Hpci ENS 457672010-03-15T13:46:00015 March 2010 13:46:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Secondary Containment Bypass Leakage Exceeded Technical Specification Limit ENS 437222007-10-13T06:20:00013 October 2007 06:20:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Inoperable Control Rods ENS 432252007-03-09T18:45:0009 March 2007 18:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Secondary Containment Bypass Leakage Rate Exceeded ENS 424072006-03-12T07:17:00012 March 2006 07:17:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Llrt Test Identified Piping Penetration with Excessive Leakage ENS 423852006-03-04T10:17:0004 March 2006 10:17:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Control Rods Declared Inoperable During Shutdown ENS 420932005-10-29T03:32:00029 October 2005 03:32:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Inoperable Control Rods ENS 415852005-04-10T15:50:00010 April 2005 15:50:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Failed 125V Dc Battery Charger ENS 415062005-03-21T03:30:00021 March 2005 03:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Discovered During Hydro Test ENS 406052004-03-23T12:46:00023 March 2004 12:46:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Indication of Crack Failure on Rcs Pressure Boundary Penetration ENS 405662004-03-04T10:20:0004 March 2004 10:20:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcic Steam Supply Failed Llrt 2023-03-26T20:03:00 | |
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