ENS 49416
ENS Event | |
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09:19 Oct 7, 2013 | |
Title | Potential Reactor Coolant System Pressure Boundary Leakage Identified |
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.
At approximately 2100 MST on 10/06/13, while performing planned routine visual examinations of the Unit 3 reactor vessel bottom mounted instrumentation (BMI) nozzles, a white residue was identified around the annulus region of BMI penetration number 3. The BMI visual examinations are performed using remote video and photographic equipment to meet the in-service inspection requirements of 10 CFR 50.55a(g)(6)(ii)(E) and ASME Code Case N-722-1. At this time, no other indications of leakage have been identified and inspections of the remaining BMI penetrations are ongoing. Following review of the photographic images by qualified engineering personnel, at 0219 [MST] on 10/07/13, it was determined, based on past and present photographic evidence, the white residue is most likely dry boric acid resulting from reactor coolant system pressure boundary leakage. An activity to sample and analyze the white residue is being planned and will be performed as soon as possible. This notification is being made for a degraded condition pursuant to the requirements of 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspectors have been informed of this condition. |
Where | |
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Palo Verde ![]() Arizona (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
LER: | 05000530/LER-2013-001 Regarding Leakage on Reactor Vessel Bottom-Mounted Instrumentation Nozzle 3 |
Time - Person (Reporting Time:+3.6 h0.15 days <br />0.0214 weeks <br />0.00493 months <br />) | |
Opened: | Delbert Elkinton 12:55 Oct 7, 2013 |
NRC Officer: | Dong Park |
Last Updated: | Oct 7, 2013 |
49416 - NRC Website
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Unit 3 | |
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Reactor critical | Not Critical |
Scram | No |
Before | Cold Shutdown (0 %) |
After | Cold Shutdown (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 | |