ENS 45010
ENS Event | |
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00:45 Apr 23, 2009 | |
Title | High Pressure Coolant Injection (Hpci) System Declared Inoperable |
Event Description | On 4/22/2009 during an inspection of the HPCI (High Pressure Coolant Injection) Suppression Pool Suction piping it was identified that the suction piping was in contact with a piping support clamp. Per the design of the support, the clamp ring to pipe clearance should be 1/2 inch. With the identified contact, the integrity of the pipe support cannot be assured during a seismic event. At the time of discovery, the HPCI suction was aligned to the Suppression Pool. Subsequently, the suction has been realigned to the Condensate Storage Tank with both Suppression Pool suction valves deenergized in the closed position. HPCI remains available with suction aligned to the Condensate Storage Tank.
Due to this, HPCI was declared INOPERABLE on 4/22/2009 at 7:45 PM (local time). This event is reportable per 10 CFR 50.72(b)(3)(v)(D) for a single train safely system potentially unable to perform its safely function of accident mitigation. The licensee entered a 14 day LCO (Limiting Condition of Operation) associated with the inoperable HPCI system. The NRC Resident Inspector has been notified.
The purpose of this notification is to retract a previous report made on 4/23/09 at 0233 (ET) (EN 45010). Notification of the event to the NRC was initially made as a result of declaring High Pressure Coolant Injection (HPCI) system inoperable when the Suppression Pool Suction piping was identified as being in contact with a piping support clamp. Per the design of the support, the clamp ring to pipe clearance should have been 1/2 inch. With the identified contact, the integrity of the pipe support could not be assured during a seismic event. Since the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the HPCI system was capable of performing its safety function. NextEra concluded that the identified configuration, while not meeting design requirements, would not prevent HPCI from performing its intended safety function. This conclusion was based on analysis that demonstrated that the piping would remain intact during a design basis accident. 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 licensee notified the NRC Resident Inspector. Notified R3DO(Lipa) |
Where | |
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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:+1.8 h0.075 days <br />0.0107 weeks <br />0.00247 months <br />) | |
Opened: | Jeffrey A. Miell 02:33 Apr 23, 2009 |
NRC Officer: | Vince Klco |
Last Updated: | Jun 18, 2009 |
45010 - NRC Website | |
Unit 1 | |
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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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