ENS 42375
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ENS Event | |
|---|---|
08:50 Feb 26, 2006 | |
| Title | Manual Reactor Scram Due to Msr High Level |
| Event Description | This report is being made pursuant to 10CFR50.72 (b) (2) (iv) (B) actuation of RPS when the reactor is critical (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report) and 10CFR50.72 (b) (3) (iv) (A) actuation of PCIS group 2 (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report).
At 0250 on 2/26/06, Central Standard Time, Cooper Nuclear Station was manually scrammed due to main turbine reheat valve remaining closed following testing concurrent with a high level in the moisture separator. Alarm card procedure for this condition required removing the turbine from service. Subsequent to the scram, reactor vessel level lowered to minus 20 inches wide range indication. This corresponds to approximately 140 inches above the top of the fuel. A primary containment isolation system (PCIS) group 2 isolation occurred as expected due to level transient. All automatic actions occurred as expected. The NRC Senior Resident Inspector has been informed of the event. The reactor scram was uncomplicated, all control rods fully inserted, and no relief or safety valves lifted. The electrical lineup is normal, and the decay heat path is to the main condenser through the turbine bypass valves. |
| Where | |
|---|---|
Cooper  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000298/LER-2006-001 |
| Time - Person (Reporting Time:+-4.3 h-0.179 days <br />-0.0256 weeks <br />-0.00589 months <br />) | |
| Opened: | Andrew Ohrablo 04:32 Feb 26, 2006 |
| NRC Officer: | Joe O'Hara |
| Last Updated: | Feb 26, 2006 |
| 42375 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (70 %) |
| After | Hot Shutdown (0 %) |
Cooper with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 562782022-12-17T05:51:00017 December 2022 05:51:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram ENS 562202022-11-13T04:19:00013 November 2022 04:19:00 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 561742022-10-22T17:58:00022 October 2022 17:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge ECCS Injection While Shutdown ENS 549762020-11-01T10:34:0001 November 2020 10:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to an Un-Isolable Leak on the Turbine High Pressure Fluid System ENS 522612016-09-25T06:03:00025 September 2016 06:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Group 1 Isolation Signal ENS 454892009-11-11T23:43:00011 November 2009 23:43:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram After a Turbine Hydraulic Fluid Leak ENS 454822009-11-07T01:30:0007 November 2009 01:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to an Unisolable Leak on the Turbine High Pressure Fluid System ENS 444022008-08-09T07:04:0009 August 2008 07:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Failure of Reheat Stop Valve to Open During Turbine Valve Testing ENS 433752007-05-19T07:12:00019 May 2007 07:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Control Rod Hcu Valve Bonnet Leak Into Reactor Building ENS 425942006-05-22T12:01:00022 May 2006 12:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram as a Mitigating Action Due to Lowering Service Air Pressure ENS 423752006-02-26T08:50:00026 February 2006 08:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Msr High Level ENS 420102005-09-23T05:40:00023 September 2005 05:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Degrading Main Condenser Vacuum ENS 416012005-04-15T09:36:00015 April 2005 09:36:00 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 Reactor Scram and Specified System Actuations ENS 403622003-11-29T04:02:00029 November 2003 04:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Scram Due to Low Reactor Water Level 2022-12-17T05:51:00 | |
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