ENS 53042
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ENS Event | |
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09:04 Oct 30, 2017 | |
Title | Defective Weld Identified on Reactor Coolant Pump Seal Upper Root |
Event Description | During a scheduled refueling outage, an inspection of components inside containment revealed a suspected weld defect on 1CV-309B, 1P-1B RCP Labyrinth Seal 1PT-124 Upper Root.
10 CFR 50.2 (2)(i) defines the reactor coolant pressure boundary as being connected to the reactor coolant system, up to and including the outermost containment isolation valve in system piping which penetrates primary reactor containment. The weld defect is located on the transmitter side of 1CV-309B. This can be isolated from the RCS by shutting 1CV-309B and 1CV-308B, 1P-1B RCP Labyrinth Seal 1PT-124 Lower Root. Based on the definition provided in 10 CFR 50.2, the condition is considered reportable under 50.72(b)(3)(ii). Unit 1 is currently in mode 3. Repairs for the condition are being determined. The NRC Resident Inspector has been notified. |
Where | |
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Point Beach Wisconsin (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+3.73 h0.155 days <br />0.0222 weeks <br />0.00511 months <br />) | |
Opened: | Alex Rivas 12:48 Oct 30, 2017 |
NRC Officer: | Steve Sandin |
Last Updated: | Oct 30, 2017 |
53042 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Not Critical |
Scram | No |
Before | Hot Standby (0 %) |
After | Hot Standby (0 %) |
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] | |
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