ENS 45022
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ENS Event | |
|---|---|
14:00 Apr 26, 2009 | |
| Title | Ndt Reveals Circumferential Indications on Rcs Hot Leg Drain Piping |
| Event Description | On April 26, 2009 at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> during the Beaver Valley Power Station Unit No. 1 (BVPS-1) refueling outage, ultrasonic (UT) examinations were performed on pipe base material per the Materials Reliability Project (MRP) MRP-146 recommendations. The MRP recommendations were to address industry operating experience for similar indications identified by other utilities. Two circumferential UT indications approximately 3/8 inches in length were recorded in the base material adjacent to a socket weld on the horizontal portion of line BV-1 RC-41 which is a two (2) inch drain line that connects to the 'A' Reactor Coolant System (RCS) Hot Leg. The function of this piping is to drain the applicable loop during maintenance periods. The indications are not through wall and there was no evidence of leakage. Similar 2 inch drain lines on the other loops have been inspected satisfactorily.
The plant is currently shutdown and in Mode 6. The affected RCS loop is not required to be Operable and is currently isolated and drained. Repairs are currently being planned and will be completed prior to startup. This is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
| Beaver Valley Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000334/LER-2009-004 |
| Time - Person (Reporting Time:+-0.23 h-0.00958 days <br />-0.00137 weeks <br />-3.15054e-4 months <br />) | |
| Opened: | Dan Schwer 13:46 Apr 26, 2009 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Apr 26, 2009 |
| 45022 - NRC Website
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Beaver Valley with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 571152024-05-09T12:00:0009 May 2024 12:00:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Containment Bypass Condition Due to Degraded River Water Piping ENS 564852023-04-22T23:42:00022 April 2023 23:42:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 555402021-10-22T05:04:00022 October 2021 05:04:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 546802020-04-24T05:30:00024 April 2020 05:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (Rcs) Pressure Boundary Degraded ENS 543372019-10-17T23:51:00017 October 2019 23:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 537112018-11-01T04:00:0001 November 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovery of Indications That Did Not Meet Acceptance Criteria on One Reactor Vessel Head Penetration ENS 514532015-10-05T12:15:0005 October 2015 12:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Two Reactor Vessel Head Penetrations Could Not Be Dispositioned as Acceptable ENS 500792014-05-01T20:10:0001 May 2014 20:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Reactor Vessel Head Control Rod Drive Penetration ENS 494132013-10-05T03:24:0005 October 2013 03:24:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unexpected Containment Liner Penetration Found ENS 483872012-10-06T20:35:0006 October 2012 20:35:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded One of Sixty Six Reactor Vessel Penetrations Did Not Meet Acceptance Criteria ENS 467442011-04-10T07:45:00010 April 2011 07:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip While Performing a Technical Specification Required Shutdown ENS 454632009-10-23T21:00:00023 October 2009 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Small Circumferential Indications Found on Two Reactor Vessel Head Penetrations ENS 450222009-04-26T14:00:00026 April 2009 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ndt Reveals Circumferential Indications on Rcs Hot Leg Drain Piping ENS 450152009-04-23T14:15:00023 April 2009 14:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Damaged Area in Containment Liner 2024-05-09T12:00:00 | |
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