ENS 42828
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ENS Event | |
|---|---|
06:31 Sep 6, 2006 | |
| Title | |
| Event Description | Observed degrading condenser pressure. Entered abnormal procedure DB-OP-02518, High Condenser Pressure and reduced reactor power. At <280 Mwe and > 5 inches Hg (mercury) A (absolute) , manually tripped the reactor at approximately 45% power in accordance with procedure. Normal post-trip response. Condenser pressure is slowly recovering. Still trying to determine the source of the condenser air in-leakage.
Notified Ottawa County Sheriff of main steam safety / atmospheric vent valve operation at 0231 hours0.00267 days <br />0.0642 hours <br />3.819444e-4 weeks <br />8.78955e-5 months <br /> per procedure. All control rods fully inserted on the trip. Decay heat is being removed using the turbine bypass valves and the motor driven feed pump. There is no steam generator tube leakage. The atmospheric vent valves / main steam safety valves lifted for a few seconds following the trip and fully reseated after the initial lifting. Plant electrical power if from the grid backfeeding to the station. The electric grid is stable. The NRC Resident Inspector was notified of this event by the licensee. |
| Where | |
|---|---|
Davis Besse  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-0.97 h-0.0404 days <br />-0.00577 weeks <br />-0.00133 months <br />) | |
| Opened: | Randy Patrick 05:33 Sep 6, 2006 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Sep 6, 2006 |
| 42828 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 553462021-07-09T01:54:0009 July 2021 01:54:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Main Turbine Trip ENS 546112020-03-25T16:40:00025 March 2020 16:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Loss of Reactor Coolant Pumps ENS 542632019-09-07T17:09:0007 September 2019 17:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 522322016-09-10T07:43:00010 September 2016 07:43:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Unit Trip Due to Main Generator Lock-Out ENS 516962016-01-29T18:22:00029 January 2016 18:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Reactor Protection System Actuation ENS 510612015-05-09T22:55:0009 May 2015 22:55:00 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 Unusual Event Declared Due to Steam Leak in the Turbine Building ENS 491592013-06-30T01:20:00030 June 2013 01:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Reactor Coolant Pump Trip ENS 428282006-09-06T06:31:0006 September 2006 06:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip on Loss of Condenser Vacuum ENS 409212004-08-04T14:24:0004 August 2004 14:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unexpected Reactor Trip During Maintenance Activities 2021-07-09T01:54:00 | |
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