ENS 43172
ENS Event | |
|---|---|
06:00 Feb 19, 2007 | |
| Title | Degraded Condition - 30% Through Wall Indication on Reactor Recirc Nozzle |
| Event Description | {{#Wiki_filter:Information from a Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) indicates that a linear indication approximately 7" long (centered at the bottom of the weld) and approximately 30% through wall extent (ID connected) exists. The Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) was performed as part of scheduled outage activities.
TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping. This event is reportable under � 50.72(b)(3)(ii), 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded', when there are welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, IWB-3600, 'Analytical Evaluation of Flaws' or ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.' The licensee informed the NRC Resident Inspector.
Information from a Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) indicates that a linear indication approximately 10" long and approximately 82% through wall extent (Inner Diameter connected) exists. The Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) was performed as part of a follow-up activity for an extent of condition evaluation on RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld). TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping. Corrected error in original report due to event entry error that identified the affected nozzle as RRF-17002 vice the correct identification of RRF-F002 The licensee notified the NRC Resident Inspector. Notified R3DO (Burgess) }} |
| Where | |
|---|---|
Duane Arnold  Iowa (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+9.57 h0.399 days <br />0.057 weeks <br />0.0131 months <br />) | |
| Opened: | Ellis Vann 15:34 Feb 19, 2007 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Feb 21, 2007 |
| 43172 - NRC Website
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WEEKMONTHYEARENS 463792010-10-29T21:21:00029 October 2010 21:21:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - 71% Through Wall Indication on Reactor Recirc Nozzle ENS 431722007-02-19T06:00:00019 February 2007 06:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - 30% Through Wall Indication on Reactor Recirc Nozzle ENS 431182007-01-24T15:55:00024 January 2007 15:55:00 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 Missing Pipe Clamp Bolt Found on High Pressure Coolant Injection (Hpci) System 2010-10-29T21:21:00 | |