ENS 49566
ENS Event | |
|---|---|
08:29 Nov 21, 2013 | |
| Title | Diesel Generator Inoperability |
| Event Description | Following preplanned maintenance on the inoperable 'A' Standby Diesel Generator (SBDG), the operability surveillance (STP-3.8.1-04A Slow Start from Normal Air) was in progress. While securing the 'A' SBDG, the 'B' SBDG control power failure annunciator was received.
The 'B' Standby Diesel Generator was declared inoperable and Technical Specification 3.8.1.B was entered for the 'B' SBDG. Additionally, Technical Specification 3.8.1.D was entered for two Standby Diesel Generators inoperable. Technical Specification 3.8.1.D allows 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore 1 SBDG to operable. At 0343 [CST], the 'A' SBDG was restored to operable and Technical Specification 3.8.1.D was exited. This condition is reported under 50.72(b)(3)(v)(D), any event or condition at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. The NRC Resident Inspector was informed.
The purpose of this notification is to retract a previous report made on 11/21/2013 at 1038 EST (EN 49566). Notification of the event to the NRC was initially made as a result of declaring both trains of the Emergency Diesel Generator (EDG) System inoperable due to receiving the 'B' EDG control power failure annunciator while the 'A' EDG was inoperable for pre-planned maintenance. Subsequent to the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the 'B' EDG system was capable of performing its safety function and was fully operable, but degraded during the period that the 'A' EDG was inoperable for pre-planned maintenance. The cause of the annunciator was from an open fuse in the control power circuit that affected the annunciator system logic and did not affect the actual EDG control logic. This event is not considered a Safety System Functional Failure and is not reportable to the NRC as a Licensee Event Report (LER) per 10 CFR 50.73. The NRC Senior Resident Inspector has been notified. Notified R3DO (Stone). |
| Where | |
|---|---|
Duane Arnold  Iowa (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+2.15 h0.0896 days <br />0.0128 weeks <br />0.00295 months <br />) | |
| Opened: | Steve Speirs 10:38 Nov 21, 2013 |
| NRC Officer: | Daniel Mills |
| Last Updated: | Aug 28, 2014 |
| 49566 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Duane Arnold with 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
WEEKMONTHYEARENS 528812017-08-01T14:34:0001 August 2017 14:34:00
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