ENS 41639: Difference between revisions
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| event date = 04/26/2005 00:02 EDT | | event date = 04/26/2005 00:02 EDT | ||
| last update date = 04/26/2005 | | last update date = 04/26/2005 | ||
| title = Automatic Reactor Trip | | title = Automatic Reactor Trip with Afw Actuation | ||
| event text = The DC Cook Unit 1 Reactor automatically tripped during normal plant startup preparations to synchronize the Main Generator with the offsite electrical GRID. Indicated Reactor power at the time of trip was 8 % power and stable. Preliminary review indicates the trip was caused by an Intermediate Range high flux reactor trip signal. The Intermediate Range High Flux Reactor trip occurred below the Reactor Protection System actuation setpoint. This is a one-out-of-two logic and the trip is active below interlock Permissive P-10 (10% reactor power). The cause of the Reactor Trip is under investigation. This event is reportable under 10CFR50.72(b)(2)(iv)(B), RPS actuation, as a four (4) hour report and under 10CFR50,72(b)(3)(iv)(A), Specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 1 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event. The DC Cook Senior Resident NRC Inspector was notified 04/26/05 at approximately 00:30 [hrs. EDT]. | | event text = The DC Cook Unit 1 Reactor automatically tripped during normal plant startup preparations to synchronize the Main Generator with the offsite electrical GRID. Indicated Reactor power at the time of trip was 8 % power and stable. Preliminary review indicates the trip was caused by an Intermediate Range high flux reactor trip signal. The Intermediate Range High Flux Reactor trip occurred below the Reactor Protection System actuation setpoint. This is a one-out-of-two logic and the trip is active below interlock Permissive P-10 (10% reactor power). The cause of the Reactor Trip is under investigation. This event is reportable under 10CFR50.72(b)(2)(iv)(B), RPS actuation, as a four (4) hour report and under 10CFR50,72(b)(3)(iv)(A), Specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 1 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event. The DC Cook Senior Resident NRC Inspector was notified 04/26/05 at approximately 00:30 [hrs. EDT]. | ||
The electrical grid is stable and Unit 1 is being supplied by offsite power. Unit 2 is not affected. All control rods fully inserted. Decay heat is being removed via steam dumps to the main condenser. | The electrical grid is stable and Unit 1 is being supplied by offsite power. Unit 2 is not affected. All control rods fully inserted. Decay heat is being removed via steam dumps to the main condenser. | ||
Latest revision as of 21:21, 1 March 2018
| Where | |
|---|---|
Cook  Michigan (NRC Region 3) | |
| 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:+-1.83 h-0.0763 days <br />-0.0109 weeks <br />-0.00251 months <br />) | |
| Opened: | Braddock D. Lewis 02:12 Apr 26, 2005 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Apr 26, 2005 |
| 41639 - NRC Website
| |
Cook with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | ||
| Automatic Reactor Trip [Table view] | ||