ENS Event | |
|---|---|
05:30 Mar 9, 2007 | |
| Title | Main Steam Line Flow Instrument Line Pressure Boundary Leakage |
| Event Description | With Unit 2 in Mode 4 for a planned refueling outage, a one-inch socket weld elbow on an instrument line off the 'D' main steam line was identified as leaking water. Leakage was quantified as less than 20 drops per minute (with the main steam lines full of water).
This elbow is on a steam line flow instrument (just below its condensing chamber) and is located in the Unit 2 drywell (primary containment). This item constitutes a primary coolant boundary leak discovered while shutdown. A pressure test is planned to be performed after the repair of the instrument line elbow is completed. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Hatch  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.88 h0.0367 days <br />0.00524 weeks <br />0.00121 months <br />) | |
| Opened: | Frank Gorley 06:23 Mar 9, 2007 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Mar 9, 2007 |
| 43224 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 575672025-02-22T16:11:00022 February 2025 16:11:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 569592024-02-11T15:11:00011 February 2024 15:11:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 563422023-02-07T22:38:0007 February 2023 22:38:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 544632020-01-04T16:09:0004 January 2020 16:09:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 525672017-02-20T04:23:00020 February 2017 04:23:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Penetration Exceeded Allowable Leakage ENS 517422016-02-16T11:31:00016 February 2016 11:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Overlay Flaw Did Not Meet Acceptance Criteria ENS 487952013-02-28T16:55:00028 February 2013 16:55:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Closed Cooling Water Isolation Valve Fails Local Leak Rate Test ENS 487722013-02-20T10:28:00020 February 2013 10:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Containment Penetration Fails Local Leak-Rate Testing ENS 440382008-03-06T09:00:0006 March 2008 09:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pin Hole Leak Discovered in 1 Inch Instrument Line During Rpv Pressure Test ENS 440052008-02-23T21:00:00023 February 2008 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unacceptable Flaw in Rpv Cap-To-Pipe Weld ENS 432242007-03-09T05:30:0009 March 2007 05:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Main Steam Line Flow Instrument Line Pressure Boundary Leakage ENS 423722006-02-23T23:50:00023 February 2006 23:50:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Shroud Tie Rods 2025-02-22T16:11:00 | |