ENS 52275: Difference between revisions

v t e ENS Event
21:00 Oct 2, 2016
Title	Liquid Penetration Examination Results in Indications on Reactor Vessel Head Penetration
Event Description	On October 2, 2016 during the Braidwood Station Unit Refueling outage (A1R19), an in-service Liquid Penetration examination was performed on the previously repaired control rod drive mechanism (CRDM) penetration 69. During the examination on the weld build up for CRDM penetration 69, two indications were discovered. A 7/32 inch rounded indication was discovered located at 359 degrees on the reactor head portion of the weld buildup, and it is 4 inches from the transition of the head to penetration. A 1/4 inch rounded indication was also discovered located at 200 degrees at the transition of the head to penetration. 0 degrees is located at the outermost portion of the penetration on the flange side. The transition is the point where the vertical portion of the penetration meets the horizontal area of the reactor head. Rounded indications that exceed 3/16 inch are rejectable per ASME Code Case N-729-1. This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A), 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded' since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair. The NRC Resident Inspector has been informed.

ENS 52275 +/-
Where
Braidwood Illinois (NRC Region 3)
Reporting

10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
LER:	05000456/LER-2016-003
Time - Person (Reporting Time:+3.03 h0.126 days <br />0.018 weeks <br />0.00415 months <br />)
Opened:	Ron Bruck 00:02 Oct 3, 2016
NRC Officer:	Dong Park
Last Updated:	Oct 3, 2016
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v • d • e

v t e Emergency Notification System
Braidwood with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
WEEKMONTHYEAR2022-10-07T06:19:00 [Table view]
[ENS list for Braidwood]

@@ Line 16: / Line 16: @@
 | event date = 10/02/2016 16:00 CDT
 | last update date = 10/03/2016
-| title = Liquid Penetration Examination Results In Indications On Reactor Vessel Head Penetration
+| title = Liquid Penetration Examination Results in Indications on Reactor Vessel Head Penetration
 | event text = On October 2, 2016 during the Braidwood Station Unit Refueling outage (A1R19), an in-service Liquid Penetration examination was performed on the previously repaired control rod drive mechanism (CRDM) penetration 69. During the examination on the weld build up for CRDM penetration 69, two indications were discovered. A 7/32 inch rounded indication was discovered located at 359 degrees on the reactor head portion of the weld buildup, and it is 4 inches from the transition of the head to penetration.  A 1/4 inch rounded indication was also discovered located at 200 degrees at the transition of the head to penetration. 0 degrees is located at the outermost portion of the penetration on the flange side. The transition is the point where the vertical portion of the penetration meets the horizontal area of the reactor head.
 Rounded indications that exceed 3/16 inch are rejectable per ASME Code Case N-729-1.

Latest revision as of 21:44, 1 March 2018