ENS 52591

v t e ENS Event
23:05 Mar 3, 2017
Title	Previous Overlay Repair Did Not Meet Acceptance Criteria
Event Description	On 3/3/2017 at 1705 [CST], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Liquid Penetrant (PT) examination performed on a previous overlay repair of the reactor vessel head did not meet applicable acceptance criteria. The penetration overlay weld indication will be addressed prior to returning the vessel head to service. The examination was being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1 to ensure the structural integrity of the reactor vessel head pressure boundary. Ultrasonic examinations have been performed and no ultrasonic indications were identified. This event is being reported under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.' The licensee has notified the NRC Resident Inspector.

ENS 52591 +/-
Where
Byron Illinois (NRC Region 3)
Reporting

10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
LER:	05000454/LER-2017-001 Regarding Volumetric and Surface Examinations of Reactor Pressure Vessel Head Penetration Nozzles Identify Indications Attributed to Primary Water Stress Corrosion Cracking and Minor Subsurface Void Enlargement from
Time - Person (Reporting Time:+-2.22 h-0.0925 days <br />-0.0132 weeks <br />-0.00304 months <br />)
Opened:	Brian Lewin 20:52 Mar 3, 2017
NRC Officer:	Jeff Herrera
Last Updated:	Mar 3, 2017
52591 - NRC Website Loading map...
v • d • e

v t e Emergency Notification System
Byron with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
WEEKMONTHYEAR2026-03-08T22:17:00 [Table view]
[ENS list for Byron]

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