ENS 41473
ENS Event | |
|---|---|
11:37 Mar 9, 2005 | |
| Title | Pressurizer Heater Sleeve Leakage |
| Event Description | The following information was obtained from the licensee via facsimile (licensee text in quotes):
ANO (Arkansas Nuclear One) Unit 2 shutdown on 3/9/05 at approximately 0038 [CST] to begin the 2R17 refueling outage. While performing the Mode 3 Hot Shutdown Walk down on ANO Unit 2, evidence of leakage was discovered around three (3) pressurizer heater sleeves. The amount of leakage was minor since no indication of moisture was present and the build up of boric acid was minimal. Investigations are underway as to the repair of the affected nozzles. The licensee notified the NRC Resident Inspector.
The following information was obtained from the licensee via facsimile (licensee text in quotes): ANO Unit 2 shutdown on 3-9-05 at approximately 0038 to begin the 2R17 refueling outage. While performing the Mode 3 Hot Shutdown Walk down on ANO Unit 2, evidence of leakage was discovered around three (3) pressurizer Heater Sleeves. The amount of leakage was minor since no indication of moisture was present and the build up of boric acid was minimal. Investigations are underway as to the repair of the affected nozzles. Update on 3/12/2005 @ 2140: During the followup inspection performed on 3-12-2005, eight pressurizer heater nozzles had evidence of boric acid leakage at the annulus between the nozzle and pressurizer. One plug was also discovered with evidence of boric acid leakage. The nozzle at this location was plugged during the late 1980's. The reactor is presently in cold shutdown. The NRC Resident Inspector was notified.
The following information was obtained from the licensee via facsimile (licensee text in quotes): Following decontamination activities performed on 3-15-2005, 1 [one] additional pressurizer heater nozzle had evidence of leakage at the annulus between the nozzle and pressurizer. The licensee notified the NRC Resident Inspector. Notified R4 DO (T. Farnholtz) |
| Where | |
|---|---|
Arkansas Nuclear  Arkansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-2.02 h-0.0842 days <br />-0.012 weeks <br />-0.00277 months <br />) | |
| Opened: | Richard Harris 09:36 Mar 9, 2005 |
| NRC Officer: | Bill Gott |
| Last Updated: | Mar 15, 2005 |
| 41473 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
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 | |