ENS 43976
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ENS Event | |
|---|---|
04:07 Feb 11, 2008 | |
| Title | Manual Reactor Scram Due to Increasing Reactor Vessel Level |
| Event Description | On February 10, 2008, at approximately 2207 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.397635e-4 months <br /> CST, the 'B' Reactor Recirculation pump tripped from fast speed to off. The resultant reactor pressure vessel level swell resulted in reactor pressure vessel level being greater than 48 inches and rising. Per Clinton Power Station operating procedures, the 'A' Reactor Operator placed the mode switch to the 'shutdown' position initiating a manual reactor scram. All control rods inserted [fully]. CPS is currently stable in Mode 3.
Decay heat is being removed to the main condenser via the turbine bypass valves. Reactor level is being maintained using the motor driven reactor feedpump. No SRVs lifted during the transient. Licensee is in progress of restoring the electrical plant to a normal shutdown lineup. The licensee notified the NRC Resident Inspector.
After further analysis of the scram, it was determined that an automatic level 8, high reactor water level, scram occurred approximately one second prior to the reactor operator placing the mode switch to the 'shutdown' position. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Clinton  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-2.32 h-0.0967 days <br />-0.0138 weeks <br />-0.00318 months <br />) | |
| Opened: | Mike Reandeau 01:48 Feb 11, 2008 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Feb 13, 2008 |
| 43976 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (97 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 563282023-02-01T05:43:0001 February 2023 05:43:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Scram Due to Turbine Trip ENS 541972019-08-03T07:26:0003 August 2019 07:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge En Revision Imported Date 8/7/2019 ENS 536982018-10-28T05:00:00028 October 2018 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram During a Reactor Shutdown ENS 531102017-12-09T19:48:0009 December 2017 19:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 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)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Manual Reactor Scram Due to Loss of Division 1 Ac Power to Numerous Components ENS 528002017-06-11T03:56:00011 June 2017 03:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Feedwater Heating ENS 527772017-05-31T01:38:00031 May 2017 01:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram ENS 499582014-03-26T00:42:00026 March 2014 00:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Condenser Vacuum ENS 496322013-12-13T23:57:00013 December 2013 23:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During Feed Pump Swap ENS 496172013-12-09T02:27:0009 December 2013 02:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Manual Scram Due to Loss of Division 1 480 Vac Power Causing Loss of Instrument Air to Containment and Scram Air Header ENS 489742013-04-26T13:55:00026 April 2013 13:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Rapidly Decreasing Level in the Ehc Oil Reservoir ENS 488122013-03-07T13:56:0007 March 2013 13:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram on Generator Trip/Turbine Trip ENS 474892011-11-29T23:28:00029 November 2011 23:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit Experienced an Automatic Reactor Scram During a Planned Shutdown ENS 454332009-10-15T10:37:00015 October 2009 10:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 439762008-02-11T04:07:00011 February 2008 04:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Increasing Reactor Vessel Level ENS 428072006-08-27T22:05:00027 August 2006 22:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Reactor High Water Level ENS 424302006-03-20T10:53:00020 March 2006 10:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Main Turbine Trip Caused Reactor Scram ENS 408682004-07-13T21:10:00013 July 2004 21:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Possible Adverse Weather ENS 406042004-03-23T01:31:00023 March 2004 01:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram from 93% Power Due to Generator Trip ENS 403682003-12-02T22:58:0002 December 2003 22:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Low Reactor Water Feed Pump Suction Pressure 2023-02-01T05:43:00 | |
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