ENS 40556
ENS Event | |
|---|---|
07:00 Feb 29, 2004 | |
| Title | Boric Acid Residue Found on Pressurizer Heater Sleeve |
| Event Description | The following event description is based on information currently available. If through subsequent reviews of this event, additional Information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
On February 29, 2004, at approximately 05:21 Mountain Standard Time (MST) engineering personnel performing preplanned visual examinations of reactor coolant system (RCS) piping in accordance with procedure requirements discovered boric acid residue on the A03 pressurizer heater sleeve. The heater sleeve is an alloy 600 penetration. The visual observation was characterized as a small white buildup of boron residue around the heater sleeve as the sleeve enters the pressurizer bottom head. There does not appear to be residue running down the outside of the sleeve. There were no signs of dripping, spraying, puddles of liquid, or liquid running down the nozzle or pressurizer. The residue appeared dry. Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.14 permits no reactor coolant system (RCS) pressure boundary leakage and therefore, the discovery of leakage (presumed boric acid residue) from the pressurizer heater sleeve was a degradation of a principal safety barrier. Therefore, the ENS notification of this event is in accordance with 10CFR50.72(b)(3)(ii). The control room personnel entered LCO 3.4.14 Condition B and are taking action to place the plant In Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The Unit had been shutdown and was being maintained in Mode 3 while troubleshooting a turbine-generator excitation problem. At the time of discovery, the RCS was at approximately 565 degrees F and 2245 psia. An investigation of this event will be conducted in accordance with the PVNGS corrective action program. No ESF actuations occurred and none were required. There were no structures, systems, or components that were inoperable at the time of discovery that contributed to this condition. There were no failures that rendered a train of a safety system inoperable and no failures of components with multiple functions were involved. The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Palo Verde  Arizona (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000530/LER-2004-001 |
| Time - Person (Reporting Time:+4.77 h0.199 days <br />0.0284 weeks <br />0.00653 months <br />) | |
| Opened: | Steve Banks 11:46 Feb 29, 2004 |
| NRC Officer: | Bill Gott |
| Last Updated: | Feb 29, 2004 |
| 40556 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 567852023-10-09T22:07:0009 October 2023 22:07:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 523092016-10-20T01:30:00020 October 2016 01:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Safety Injection Piping Weld Flaw ENS 519102016-05-05T12:00:0005 May 2016 12:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded High Pressure Safety Injection Valve Bonnet Leakage Identified During Refueling Outage ENS 518612016-04-11T12:35:00011 April 2016 12:35:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Bounday Leakage ENS 509682015-04-08T10:30:0008 April 2015 10:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Leakage Identified ENS 494162013-10-07T09:19:0007 October 2013 09:19:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Reactor Coolant System Pressure Boundary Leakage Identified ENS 428862006-10-07T18:40:0007 October 2006 18:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Axial Indications Identified on Pressure Boundry ENS 417832005-06-17T18:00:00017 June 2005 18:00:00 10 CFR 21.21, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Degraded Condition Due to Pressurizer Heater Element Non-Conformance ENS 416292005-04-23T07:00:00023 April 2005 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovered Two Axial Indications on Inside Diameter of Reactor Vessel Head Penetration ENS 405562004-02-29T07:00:00029 February 2004 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Boric Acid Residue Found on Pressurizer Heater Sleeve ENS 405032004-02-03T22:35:0003 February 2004 22:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Rcs Pressure Boundary Leakage ENS 397142003-03-29T11:00:00029 March 2003 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 2023-10-09T22:07:00 | |