ENS 53497: Difference between revisions
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| Line 9: | Line 9: | ||
| unit = 1 | | unit = 1 | ||
| utype = GE-4, GE-4, GE-4 | | utype = GE-4, GE-4, GE-4 | ||
| cfr = 10 CFR 50.72(b)(3)(v)(D) | | cfr = , 10 CFR 50.72(b)(3)(v)(D), | ||
| emergency class = Non Emergency | | emergency class = Non Emergency | ||
| notification date = 07/09/2018 17:01 | | notification date = 07/09/2018 17:01 | ||
Revision as of 21:40, 30 October 2018
ENS Event | |
|---|---|
05:00 Jul 9, 2018 | |
| Title | High Pressure Coolant Injection System Declared Inoperable |
| Event Description | On 07/09/2018 at 1111 CDT, Browns Ferry Unit 1 Operators identified U1 High Pressure Cooling Injection system steam supply valves were isolated. After reviewing ICS [Integrated Computer System], Operations determined isolation occurred at 0958 CDT during performance of surveillance testing. The Browns Ferry Nuclear Plant Unit 1 High Pressure Coolant Injection (HPCI) system was declared inoperable at 0958 CDT due to an inadvertent isolation that occurred during testing. During performance of surveillance procedure 1-SR-3.3.6.1.2(3B) HPCI System Steam Supply Low Pressure Functional test, an erroneous signal was induced causing actuation of primary containment isolation system group IV (i.e., HPCI Isolation). Technical Specification 3.5.1, ECCS-Operating, Condition C was entered as a result of the inoperable HPCI system. This constitutes an unplanned HPCI system inoperability and requires an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(v)(D). The erroneous signal was cleared and the HPCI isolation was reset. Upon reset of the isolation signal, the HPCI system was returned to available status. The HPCI system was unavailable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 55 minutes, however the HPCI system remains inoperable.
There was no impact to the health and safety of the public or plant personnel as a result of this condition. The NRC Resident Inspector has been notified. A condition report has been entered into the Licensee's Corrective Action Program to capture this event." |
| Where | |
|---|---|
Browns Ferry  Alabama (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+12.02 h0.501 days <br />0.0715 weeks <br />0.0165 months <br />) | |
| Opened: | Anthony Alsup 17:01 Jul 9, 2018 |
| NRC Officer: | Steven Vitt |
| Last Updated: | Jul 9, 2018 |
| 53497 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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