ENS 48969
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ENS Event | |
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01:19 Apr 26, 2013 | |
Title | Manual Reactor Scram Following Trip of Circ Water Pumps |
Event Description | This report is being made pursuant to 10CFR50.72(b)(2)(iv)(B), RPS Actuation (scram). At 2019 CDT on April 25, 2013, LaSalle Unit 2 was manually scrammed due to a loss of Condenser Circulating Water. The Unit was manually scrammed after the condenser circulating water pumps tripped due to high level in the turbine building condenser pit. The high level in the condenser pit was caused by a leak on the upper manway of the condenser water box during a maintenance activity. MSIV's were isolated due to loss of heat sink. The safety relief valves were used in pressure control mode. Current plant status: reactor level is stable and reactor pressure is stable. The condenser water box manway leak has been isolated. The plant will remain in hot shutdown pending investigation and repairs.
Reactor Core Isolation Cooling (RCIC) is being used in the pressure control mode. The licensee has notified the NRC Resident Inspector. |
Where | |
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Lasalle Illinois (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
LER: | 05000374/LER-2013-002 |
Time - Person (Reporting Time:+-2.93 h-0.122 days <br />-0.0174 weeks <br />-0.00401 months <br />) | |
Opened: | Todd Granlund 22:23 Apr 25, 2013 |
NRC Officer: | Bill Huffman |
Last Updated: | Apr 25, 2013 |
48969 - NRC Website | |
Unit 2 | |
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Reactor critical | Critical |
Scram | Yes, Manual Scram |
Before | Power Operation (57 %) |
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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