ENS Event | ||
|---|---|---|
14:13 Oct 3, 2020 | ||
| Title | Reactor Coolant System Pressure Boundary Leakage | |
| Event Description | During a scheduled refueling outage, a walkdown inside containment to investigate leakage revealed a pressure boundary leak upstream of 1RC-526B, HX-1B Steam Generator Channel Head Drain. This location would be considered part of the reactor coolant system as defined under 10 CFR 50.2. As such, this event is being reported pursuant to 10 CFR 50.72 (b)(3)(ii)(A). Unit 1 is currently in mode 4. Repairs for the condition are being determined.
The NRC Resident Inspector has been notified. The leak rate was determined to be 0.138 gpm. | |
| Where | |
|---|---|
Point Beach  Wisconsin (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.9 h0.0375 days <br />0.00536 weeks <br />0.00123 months <br />) | |
| Opened: | Mary Sipiorski 15:07 Oct 3, 2020 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Oct 3, 2020 |
| 54930 - NRC Website | |
WEEKMONTHYEARENS 549302020-10-03T14:13:0003 October 2020 14:13:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Reactor Coolant System Pressure Boundary Leakage ENS 530422017-10-30T09:04:00030 October 2017 09:04:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Defective Weld Identified on Reactor Coolant Pump Seal Upper Root ENS 517922016-03-15T11:49:00015 March 2016 11:49:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Identified Pressure Boundary Leakage ENS 431492007-02-06T20:15:0006 February 2007 20:15:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Control Room Emergency Filtration System Declared Inoperable ENS 407282004-05-06T15:46:0006 May 2004 15:46:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Nozzle Weld Area Flaw 2020-10-03T14:13:00 [Table view] | |