ENS 50686
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ENS Event | |
|---|---|
22:00 Dec 13, 2014 | |
| Title | Degraded Reactor Coolant Pressure Boundary |
| Event Description | On 12/13/14 at 1700 [EST] hours, during a planned Unit 1 maintenance outage the licensee identified leakage from a weld on the [.75 inch] lower seal vent piping connected to the 1B reactor recirculation pump lower seal area. The location is within the reactor recirculation loop isolation valves, therefore isolable from the reactor vessel. The piping is ASME Class 2 and is a reactor coolant pressure boundary. The reactor was in mode 3 at the time of discovery. Control Room notified at 1345 [EST] on 12/16/14, that requirements for 10CFR50.72(b)(3)(ii)(A) were not met.
This event is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)(A). The unit was taken to Mode 4 and the seal vent piping repair was completed. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Susquehanna  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+67.52 h2.813 days <br />0.402 weeks <br />0.0925 months <br />) | |
| Opened: | Doug Lamarca 17:31 Dec 16, 2014 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Dec 16, 2014 |
| 50686 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
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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