ENS 43262
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ENS Event | |
|---|---|
18:41 Mar 28, 2007 | |
| Title | Hpci Inoperable Due to Surveillance Test Failure |
| Event Description | During the running of the HPCI operability, STP 3.5.1-05, the discharge relief, PSV 2302, lifted and failed to reseat. The relief valve discharges to the Torus Area floor and was captured in the floor drain sump system. The STP was aborted and the HPCI system was declared inoperable.
The licensee notified the NRC Resident Inspector.
The purpose of this notification is to retract a previous report made on 3/28/07 at 1739 (ET) (EN 43262). Notification of this issue to the NRC on 3/28/07 was initially made as a result of declaring HPCI inoperable during the running of the HPCI operability, Surveillance Test Procedure (STP) 3.5.1-05. HPCI was declared inoperable when the discharge relief, PSV 2302, lifted and failed to reseat. The relief valve discharges to the Torus Area floor and was capture in the floor drain sump system. The STP was aborted and HPCI system was declared inoperable. Since the initial report, Engineering had determined that the HPCI system was capable of performing its safety function. Engineering concluded that the stuck open HPCI discharge pressure relief valve would not have prevented HPCI from fulfilling its design function of providing adequate high pressure makeup to the reactor vessel. Existing operating procedure guidance would have ensured that HPCI injection would not have been terminated in the event it was needed under accident conditions, even with PSV2302 stuck open. Operating procedure guidance and Reactor Building floor drain sump pump capacity are adequate to prevent a flooding concern. 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 Resident Inspector was notified of this retraction by the licensee. R3DO (Richard Skokowski) notified. |
| 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:+-1.03 h-0.0429 days <br />-0.00613 weeks <br />-0.00141 months <br />) | |
| Opened: | Wayne Bentley 17:39 Mar 28, 2007 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | May 24, 2007 |
| 43262 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (98 %) |
| After | Power Operation (98 %) |
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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