ENS 45482
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ENS Event | |
|---|---|
01:30 Nov 7, 2009 | |
| Title | Manual Reactor Trip Due to an Unisolable Leak on the Turbine High Pressure Fluid System |
| Event Description | On November 6, 2009, at 1930 CST the reactor was manually scrammed following a manual trip of the Main Turbine due to an un-isolable leak on the Turbine High Pressure Fluid System (TGF). The RO [Reactor Operator] scrammed the reactor when [reactor vessel water] level lowered below 12 inches on the Narrow Range Instruments. All Control Rods fully inserted and a Group 2 Isolation occurred when level reached 3 inches on the Narrow Range Instruments. Reactor level lowered to approximately 22 inches on the Wide Range Instruments and was recovered in a slow and deliberate manner in order to minimize the effect on the cool down rate because of low levels of decay heat in the fuel. The Reactor Feed System was used to initially recover level. At 2043, the plant was in Mode 3 with the inboard MSIVs manually closed and level and pressure being controlled by RCIC. The MSIVs were closed to minimize the cool down rate and RCIC was started manually for level and pressure control. The Main Condenser remained available throughout the evolution and condenser vacuum is currently being maintained by the Mechanical Vacuum Pumps.
The Group 2 Isolation was verified with no discrepancies and was reset at approximately 2010. All equipment operated as expected and there were no difficulties encountered during the evolution. The TGF System has been secured and is in the process of being tagged out for repair. The licensee has notified the NRC Resident Inspector. |
| 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 | |
| Time - Person (Reporting Time:+-2.13 h-0.0888 days <br />-0.0127 weeks <br />-0.00292 months <br />) | |
| Opened: | Roy Giles 23:22 Nov 6, 2009 |
| NRC Officer: | Dong Park |
| Last Updated: | Nov 6, 2009 |
| 45482 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (20 %) |
| 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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