ENS 51687
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ENS Event | |
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05:25 Jan 27, 2016 | |
Title | |
Event Description | At 2325 [CST] on 01/26/2016, Unit 1 was manually tripped due to loss of Feedwater on 'C' S/G [Steam Generator]. The loss of Feedwater was a result of a failure on 'C' S/G Main Feedwater Regulating Valve that caused the valve to travel closed with no Operator action. Auxiliary Feedwater and Feedwater Isolation actuated as designed. All Control and Shutdown Rods fully inserted. Intermediate Range Nl 36 [Nuclear Instrument] failed above P10 and, as a result, Source Range Nuclear Instruments were manually energized. No primary or secondary relief valves opened. There were no electrical problems. Normal operating temperature and pressure (NOT/NOP) is 567 degrees F and 2235 psig. There were no significant TS LCOs entered.
This event was not significant to the health and safety of the public based on all safety systems performed as designed. Unit 2 was not affected. Decay heat removal is being controlled via Steam Dumps. Offsite power is in the normal electrical lineup. The NRC Resident Inspector has been notified. |
Where | |
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South Texas Texas (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:+-3.68 h-0.153 days <br />-0.0219 weeks <br />-0.00504 months <br />) | |
Opened: | Silvestre Romero Jr 01:44 Jan 27, 2016 |
NRC Officer: | Steven Vitto |
Last Updated: | Jan 27, 2016 |
51687 - NRC Website | |
Unit 1 | |
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Reactor critical | Critical |
Scram | Yes, Manual Scram |
Before | Power Operation (100 %) |
After | Hot Standby (0 %) |
South Texas with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 571242024-05-12T21:41:00012 May 2024 21:41:00
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