ENS Event | |
|---|---|
07:00 Mar 26, 2020 | |
| Title | En Revision Imported Date 3/30/2020 |
| Event Description | EN Revision Text: DEGRADED CONDITION
On March 26, 2020, while McGuire Unit 2 was shut down for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with the in-service Inspection Program. Ultrasonic examinations identified a relevant indication in the Control Rod Drive Mechanism nozzle number 35 that did not meet the acceptance criteria under ASME, Section XI IWB-3600, 'Analytic Evaluation of Flaws.' Actions to address the relevant indication will be taken in accordance with the applicable codes, standards, and regulations. This event is being reported as an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). The relevant indication has no impact on the health and safety of the public or station employees. The NRC Resident Inspector has been notified.
McGuire is retracting the eight hour non-emergency notification made on March 26, 2020, at 10:45 ET (EN#54614). A subsequent evaluation determined that the suspect indication identified during ultrasonic examination of Control Rod Drive Mechanism nozzle number 35 is not service induced nor representative of primary water stress corrosion cracking (PWSCC). The indication has been classified as "non-relevant" and is not reportable as a degraded condition. The senior NRC Resident Inspection has been notified. Notified R2DO (Miller). |
| Where | |
|---|---|
Mcguire  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+3.75 h0.156 days <br />0.0223 weeks <br />0.00514 months <br />) | |
| Opened: | Jim Dain 10:45 Mar 26, 2020 |
| NRC Officer: | Ossy Font |
| Last Updated: | Mar 29, 2020 |
| 54614 - NRC Website | |
WEEKMONTHYEARENS 546142020-03-26T07:00:00026 March 2020 07:00:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded ENS 525732017-02-24T00:22:00024 February 2017 00:22:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage ENS 518172016-03-22T23:34:00022 March 2016 23:34:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Found in Reactor Coolant System Piping ENS 504972014-09-27T20:16:00027 September 2014 20:16:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Safety Injection Line Ultrasonic Test Indication ENS 499912014-04-03T05:00:0003 April 2014 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Safety Injection Line Ultrasonic Test Indication 2020-03-26T07:00:00 | |