ENS 55558: Difference between revisions
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There was no impact on the health and safety of the public or plant personnel. | There was no impact on the health and safety of the public or plant personnel. | ||
The NRC Resident Inspector has been notified. | The NRC Resident Inspector has been notified. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2021/ | | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2021/20211105en.html#en55558 | ||
}}{{unit info | }}{{unit info | ||
| Unit = 2 | | Unit = 2 | ||
Latest revision as of 07:30, 5 November 2021
ENS Event | |
|---|---|
06:41 Jun 3, 2021 | |
| Title | |
| Event Description | At 0241 [EDT] on June 3, 2021, during performance of a High Pressure Coolant Injection (HPCI) Condensate Storage Tank (CST) level functional surveillance, the HPCI torus suction inboard isolation valve was slow to open during swap of suction from the CST to the Torus. On June 9, 2021, it was determined that as a result of the June 3, 2021, slow swap condition, TS 3.3.5.1 Required Action D.1 to declare HPCI inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> was applicable due to inoperable CST low level instrumentation channels. At 1817 [EDT] on June 3, 2021, HPCI suction was swapped to the torus, making TS Required Action D.1 no longer applicable. Reactor Core Isolation Cooling (RCIC) was available throughout this condition.
At 0900 [EDT] on November 3, 2021, it was determined that an NRC event report due to HPCI inoperability should have been made. This event is being reported as a late 8-hour non-emergency notification pursuant to 10CFR50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The cause of the slow valve opening was later determined to be corrosion products on contacts of a relay in the CST low level instrumentation logic. On June 4, 2021 at 1451 [EDT], the HPCI CST Level Functional Test was completed Satisfactorily, restoring HPCI Instrumentation to Operable. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Fermi  Michigan (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:+3678.95 h153.29 days <br />21.899 weeks <br />5.039 months <br />) | |
| Opened: | N. Schafer 13:38 Nov 3, 2021 |
| NRC Officer: | Michael Bloodgood |
| Last Updated: | Nov 3, 2021 |
| 55558 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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