Semantic search
| Start date | Reporting criterion | Title | Event description | System | LER | |
|---|---|---|---|---|---|---|
| ENS 46379 | 29 October 2010 21:21:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Degraded Condition - 71% Through Wall Indication on Reactor Recirc Nozzle | Information from a Phased Array UT (Ultrasonic Testing) examination of RRA-F002A indicates that a linear indication 6.5" long and a maximum depth of 71 % through wall extent (ID (Inner Diameter) connected) exists. The Phased Array UT examination of RRA-F002A was performed as part of scheduled outage activities. TRM (Technical Requirements Manual) LCO (Limiting Condition for Operation) 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping. This event is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)(A) based on the fact that the indications result in a material defect 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. | 05000331/LER-2010-004 | |
| ENS 43172 | 19 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 | 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) | ||
| ENS 43118 | 24 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 | During a RFO-20 pre-outage inspection of HPCl Injection Line Pipe Support EBB-5-SR-9, it was noted that one of the two pipe clamp bolts (i.e. stud, nuts, and spacer) was missing. This rendered HPCl and Primary Containment inoperable. Technical Specifications 3.5.1 Condition F for HPCl inoperable, and 3.6.1.1 Condition A for Primary Containment inoperable, were entered. Since Primary Containment operability was not restored within one hour, Technical Specification 3.6.1.1 Condition B to be in Mode 3 in 12 hours and Mode 4 in 36 hours was entered. At 1649 the pipe clamp was restored, HPCl and Primary Containment were declared operable, and Technical Specifications 3.5.1 Condition F and 3.6.1.1 Conditions A and B were exited. This event is reportable as an 8 hour event under 10 CFR 50.72(b)(3)(ii)(A), Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded and 10CFR 50.72(b)(3)(v)(D), Any event or condition that alone at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (D) Mitigate the consequences of an accident. The licensee notified the NRC Resident Inspector. | High Pressure Coolant Injection Primary containment |