ENS 46238: Difference between revisions
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| event date = 09/09/2010 14:37 EDT | | event date = 09/09/2010 14:37 EDT | ||
| last update date = 09/09/2010 | | last update date = 09/09/2010 | ||
| | | title = Reactor Trip Due to Overtemperature Delta-T Signal | ||
| event text = At 1437 hours EDT on September 9, 2010, with the unit in Mode 1 at 100% power, an automatic reactor trip occurred. The reactor trip signal was based on the Overtemperature Delta-T reactor protection function. | |||
At 1437 hours EDT on September 9, 2010, with the unit in Mode 1 at 100% power, an automatic reactor trip occurred. The reactor trip signal was based on the Overtemperature Delta-T reactor protection function. | |||
During the event, the steam generator power operated relief valves (PORVs) and one pressurizer PORV briefly opened and re-closed, in response to pressure changes in the steam generators and pressurizer due to the plant transient condition. The Auxiliary Feedwater System automatically actuated, as expected, and provided feedwater to the steam generators. The main steam safety valves did not open during the event. All control rods indicated fully inserted following the reactor trip. | During the event, the steam generator power operated relief valves (PORVs) and one pressurizer PORV briefly opened and re-closed, in response to pressure changes in the steam generators and pressurizer due to the plant transient condition. The Auxiliary Feedwater System automatically actuated, as expected, and provided feedwater to the steam generators. The main steam safety valves did not open during the event. All control rods indicated fully inserted following the reactor trip. | ||
The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable. Decay heat is being removed via the condenser. The reactor is currently stable in Mode 3. | The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable. Decay heat is being removed via the condenser. The reactor is currently stable in Mode 3. | ||
There was an indication of an approximate 0.65 gpm leak to the pressurizer relief tank following the reactor trip. The isolation valve to the pressurizer PORV that opened during the reactor trip was closed and the leak indication stopped. The indicated leakage was within Technical Specification leakage rate limits. | There was an indication of an approximate 0.65 gpm leak to the pressurizer relief tank following the reactor trip. The isolation valve to the pressurizer PORV that opened during the reactor trip was closed and the leak indication stopped. The indicated leakage was within Technical Specification leakage rate limits. | ||
The cause of the reactor trip and indication of pressurizer PORV leakage is under investigation. | The cause of the reactor trip and indication of pressurizer PORV leakage is under investigation. | ||
The licensee notified the NRC Resident Inspector. | The licensee notified the NRC Resident Inspector. | ||
| URL = http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2010/20100910en.html#en46238 | | URL = http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2010/20100910en.html#en46238 | ||
Latest revision as of 00:52, 24 February 2020
| Where | |
|---|---|
Robinson  South Carolina (NRC Region 2) | |
| 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:+-0.55 h-0.0229 days <br />-0.00327 weeks <br />-7.5339e-4 months <br />) | |
| Opened: | Garrett Sanders 18:04 Sep 9, 2010 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Sep 9, 2010 |
| 46238 - NRC Website
| |
Robinson with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |