ENS 43225
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ENS Event | |
|---|---|
18:45 Mar 9, 2007 | |
| Title | Secondary Containment Bypass Leakage Rate Exceeded |
| Event Description | Appendix J Local Leak Rate Testing has determined that Tech Spec Acceptance Criteria for Secondary Containment Bypass Leakage has been exceeded. During the performance of SE-259-044 the combined SCBL limit of 9scfh was exceeded. Test results were within Administrative and Acceptance Criteria for the 10CFR50 Appendix J limits of 0.6La. The leakage limit is 9scfh. The identified degraded condition is reportable as a condition of the nuclear power plant, including its principle safety barriers being seriously degraded per 10CFR50.72(b)(3)(ii).
The NRC Resident Inspector was notified of this event by the licensee. |
| Where | |
|---|---|
Susquehanna  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-4.22 h-0.176 days <br />-0.0251 weeks <br />-0.00578 months <br />) | |
| Opened: | Grant Fernsler 14:32 Mar 9, 2007 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Mar 9, 2007 |
| 43225 - NRC Website
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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 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 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 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 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 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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