ENS 43128
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ENS Event | |
|---|---|
01:40 Jan 28, 2007 | |
| Title | Automatic Reactor Trip Due to Loss of Load Transient Caused by Ehc Problem |
| Event Description | On January 27, 2007 at approximately 2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br /> an automatic reactor trip occurred. The cause of the trip was Over Temperature Delta T (2/4). All systems functioned as designed. All control rods inserted on the trip. Decay heat removal is via condenser steam dump and Auxiliary Feedwater.
The initial cause of the trip appears to be from a loss of load due to a turbine electro-hydraulic system issue. This is still under investigation. RCS Temperature is 547 Degrees F and stable RCS Pressure is 2235 psig and stable Both pressurizer PORVs momentarily opened and then closed during the transient. For 8Hr Non Emergency 10 CFR 50.72(b)(3) RPS actuation occurred. Auxiliary Feed Water actuation occurred. There was no testing or maintenance in progress at the time of the transient. The licensee informed the NRC Resident Inspector. |
| Where | |
|---|---|
Ginna  New York (NRC Region 1) | |
| 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:+-1.63 h-0.0679 days <br />-0.0097 weeks <br />-0.00223 months <br />) | |
| Opened: | Kevin Mclaughlin 00:02 Jan 28, 2007 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Jan 28, 2007 |
| 43128 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Ginna with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 567902023-10-13T01:27:00013 October 2023 01:27:00
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