ENS 40216
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ENS Event | |
|---|---|
22:15 Oct 2, 2003 | |
| Title | Rcs Boundary Leakage Due To Small Crack On Drain Line Welded Cap |
| Event Description | Safety injection tank (SIT) isolation valve (2CV-5043-2) has a drain pipe under the valve body with a welded cap. The welded cap has a small crack with boric acid residue. The welded cap does not have any threads and is considered RCS boundary leakage. There is a check valve between the reactor coolant system (RCS) and the SIT Outlet valve. The crack will be repair welded prior to coming out of the 2R16 outage.
The Licensee has notified the NRC Resident Inspector.
This report is being made to retract a notification made at 1715 CDT on 10/02/03 (EN# 40216.) The notification documented the identification of a small amount of boric acid residue on a drain line attached to a Safety Injection Tank isolation valve (2CV-5034-2). The report stated that the indication was within the Reactor Coolant System boundary. However, subsequent review of the condition determined that the indication was not within the Reactor Coolant System boundary since it was isolated from the Reactor Coolant System by an operable check valve. Therefore, the condition did not represent a serious degradation of a principal safety barrier. Note; The drain line is 3/4 inch diameter stainless steel. The licensee notified the NRC Resident Inspector. Notified Claude Johnson - R4DO. |
| Where | |
|---|---|
Arkansas Nuclear  Arkansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-1.72 h-0.0717 days <br />-0.0102 weeks <br />-0.00236 months <br />) | |
| Opened: | Chuck Olson 20:32 Oct 2, 2003 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Dec 1, 2003 |
| 40216 - NRC Website
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WEEKMONTHYEARENS 534562024-05-20T20:53:00020 May 2024 20:53:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Identified While Shutdown ENS 555062021-10-04T19:33:0004 October 2021 19:33:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Reactor Vessel Head Penetration ENS 457972010-03-27T20:31:00027 March 2010 20:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potentially Degraded Pressurizer Level Tap Identified ENS 414732005-03-09T11:37:0009 March 2005 11:37:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressurizer Heater Sleeve Leakage ENS 407212004-04-30T19:38:00030 April 2004 19:38:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded "on 4/30/2004, During Refueling Outage 1 R18, Ultrasonic Testing of the Reactor Vessel Head Identified Two Axial Indications on Control Rod Drive Mechanism, Nozzle 61. the Indications Were Located on the Outside Diameter of the Nozzle on the Lower Hillside. One of the Flaws Was at the Toe of the Fillet Weld and Extended Below the Fillet Weld Cap. the Second Flaw Extended the Full Length of the Weld and Just Below the Toe of the Fillet Weld. ENS 402162003-10-02T22:15:0002 October 2003 22:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Boundary Leakage Due to Small Crack on Drain Line Welded Cap 2024-05-20T20:53:00 | |
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