ENS 43580
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
21:00 Aug 19, 2007 | |
| Title | Plant Shutdown Due to Unisolable Reactor Coolant System Leakage |
| Event Description | On 08/18/2007 at 16:03 EDT a Planned Manual Reactor Trip was initiated on Unit 2 based on increased unidentified RCS leakage. The RCS leakage had increased over a two day period and surpassed the hard limit of 0.28 gpm established by a plant Operational Decision Making (ODM) plan. The downpower was initiated on 08/18/07 at 10:35 EDT from 100% power and proceeded in a controlled manner to 25% power. The Feedwater Control System was maintained in the automatic mode. Station Power was transferred by procedure from the Auxiliary to the Startup Transformers. The reactor was manually tripped at 16:03 EDT. Following the reactor trip, EOP-1, Standard Post Trip Actions, and EOP-2, Reactor Trip Recovery procedures were completed without contingencies and the unit was stabilized in Mode 3. Decay heat was removed by the Steam Bypass Control System (SBCS) to the condenser. The Steam Generators were fed by the MFW System and levels remained above Auxiliary Feedwater Actuation (AFAS) setpoint. There were no significant equipment failures identified post trip. The plant was cooled down and entered Mode 5 on 8/19/07 at 15:09 EDT.
On 8/19/07 at 17:00 EDT while in Mode 5, a Containment walkdown confirmed the 2B1 RCP Seal injection line to be the only active RCS leakage source. The leak is unisolable from the RCS and is located at or adjacent to a socket weld on the 3/4" Class 1 Schedule 160 seal injection line. Removal of obstructions and insulation must occur before the specific details of the leak can be identified. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(A). Additional investigation is being perform to determine the detailed configuration of the leak and the root cause. The licensee notified 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:+1.32 h0.055 days <br />0.00786 weeks <br />0.00181 months <br />) | |
| Opened: | Calvin Ward 22:19 Aug 19, 2007 |
| NRC Officer: | Jason Kozal |
| Last Updated: | Aug 19, 2007 |
| 43580 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (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 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_43580&oldid=426811"