ENS 41401
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ENS Event | |
|---|---|
21:00 Feb 10, 2005 | |
| Title | Rcs Leakage Identified During Plant Startup Walkdowns |
| Event Description | On 2/10/2005, St. Lucie Unit 2 was in Mode 3 returning from refueling outage SL2-15. At 0605 during plant startup walkdowns, 2 leaks were discovered on the instrument line to the 2B1 safety injection header. Closing the instrument root isolation valve to PT-3339 isolated one leak. The second leak was under the insulation and later upon evaluation it was concluded to be ASME section Xl RCS pressure boundary leakage based on its location between the reactor coolant system loop check valves.
The leakage source is from the 2B1 safety injection tank and not directly from the reactor coolant system because the first reactor coolant system loop check valve is maintaining pressure isolation. As a result this is not Technical Specification pressure boundary leakage. The pressure instrument root is downstream of the Safety Injection Tank (SIT) isolation valve and between the two reactor coolant system loop check valves. Isolating the SIT from the header isolated second leak. An engineering response team was formed and repairs are being planned. RCS heat removal is being accomplished via the Steam Generators and the Atmospheric Dump Valves. Feedwater is being supplied to the Steam Generator by the Auxiliary Feedwater System. Plant electrical loads are supplied from offsite sources through the Startup Transformers. The licensee informed the NRC Resident Inspector. |
| Where | |
|---|---|
Saint Lucie  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+1.93 h0.0804 days <br />0.0115 weeks <br />0.00264 months <br />) | |
| Opened: | Joong Ko 22:56 Feb 10, 2005 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Feb 10, 2005 |
| 41401 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 569122024-01-03T17:57:0003 January 2024 17:57:00
[Table view]10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Degraded / Both Trains of High Pressure Safety Injection Inoperable ENS 568932023-12-16T01:45:00016 December 2023 01:45:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Leak ENS 535982018-09-11T04:00:00011 September 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Defect on Pressurizer Interface ENS 525232017-01-31T17:00:00031 January 2017 17:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant Pressure Boundary Piping Defect ENS 503102014-07-25T15:29:00025 July 2014 15:29:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to a Safety Injection Valve Defect ENS 452002009-07-13T11:00:00013 July 2009 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Identified ENS 439412008-01-29T10:31:00029 January 2008 10:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip to Repair Rcp "2B1" Seal Package ENS 438632007-12-21T19:45:00021 December 2007 19:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Pressure Boundary Leakage on Rcp Seal Injection Line ENS 435802007-08-19T21:00:00019 August 2007 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Plant Shutdown Due to Unisolable Reactor Coolant System Leakage ENS 434102007-06-06T17:10:0006 June 2007 17:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Isolation Valves Found Misaligned ENS 414012005-02-10T21:00:00010 February 2005 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Leakage Identified During Plant Startup Walkdowns 2024-01-03T17:57:00 | |
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