ENS 53576
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ENS Event | |
|---|---|
05:00 Aug 31, 2018 | |
| Title | Manual Reactor Scram Due to Main Condenser Degradation |
| Event Description | This notification is being provided in accordance with 10 CFR 50.72(b)(2)(iv)(B).
On August 31, 2018 at 2105 CDT, Unit 2 Reactor Manual Scram signal was inserted due to Main Condenser vacuum degrading. The turbine was tripped following the scram. Main Condenser vacuum is at 6 inches of backpressure slowly improving following the scram and turbine trip. During the scram, one Control Rod (30-31) did not fully insert. Control Rod 30-31 has been manually inserted to position 00 with the first position identified as position 24. Plant is in a stable condition with reactor pressure being maintained by the Turbine Bypass valves. Reactor water level is being controlled with feedwater. Investigation into the cause of the elevated condenser in leakage is in progress. The Senior NRC Resident has been notified. |
| Where | |
|---|---|
Lasalle  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+18.43 h0.768 days <br />0.11 weeks <br />0.0252 months <br />) | |
| Opened: | Richard Calvin 23:26 Aug 31, 2018 |
| NRC Officer: | Bethany Cecere |
| Last Updated: | Aug 31, 2018 |
| 53576 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (29 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 561202022-09-26T07:38:00026 September 2022 07:38:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Reported Fire on Isophase Bus Duct ENS 535762018-08-31T05:00:00031 August 2018 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Main Condenser Degradation ENS 525642017-02-18T05:53:00018 February 2017 05:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Resulting from Feedwater Regulating Valve Failure ENS 525472017-02-14T05:09:00014 February 2017 05:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 1 Automatic Reactor Scram Due to Main Generator Trip on Differential Current ENS 525052017-01-23T14:06:00023 January 2017 14:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Stator Water Cooling Runback Signal and Turbine Bypass Valve Opening ENS 503462014-08-05T22:34:0005 August 2014 22:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 489692013-04-26T01:19:00026 April 2013 01:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Following Trip of Circ Water Pumps ENS 489392013-04-17T20:11:00017 April 2013 20:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Notification of Unusual Event Declared Due to Loss of Offsite Power from a Lightning Strike ENS 465822011-02-02T01:18:0002 February 2011 01:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram After a Main Transformer Trip ENS 452652009-08-15T21:06:00015 August 2009 21:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to a Turbine Trip ENS 450872009-05-21T21:35:00021 May 2009 21:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation (Scram) Due to a Main Power Transformer Fault ENS 423482006-02-20T06:23:00020 February 2006 06:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Site Area Emergency - Reactor Scram ENS 403572003-11-27T06:52:00027 November 2003 06:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Manually Scrammed from 23% Due to Decreasing Reactor Vessel Water Level 2022-09-26T07:38:00 | |
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