05000412/LER-2023-001, Indications Identified During Reactor Vessel Head Inspection
| ML23167A468 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/16/2023 |
| From: | Blair B Energy Harbor Nuclear Corp |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-23-141 LER 2023-001-00 | |
| Download: ML23167A468 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
| 4122023001R00 - NRC Website | |
text
energy harbor Barry N. Blair Site Vice President June 16, 2023 L-23-141 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 LER 2023-001-00 10 CFR 50.73 Beaver Valley Power Station P.O. Box4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Enclosed is Licensee Event Report (LER) 2023-001-00, "Indications Identified During Reactor Vessel Head Inspection." This event is being reported in accordance with 10 CFR 50. 73(a)(2)(ii)(A).
There are no regulatory commitments contained in this submittal. Any actions described in this document represent intended or planned actions and are described for information only.
If there are any questions or if additional information is required, please contact Ms. Julie Hartig, Manager (Acting), Regulatory Compliance and Emergency Response, at 724-682-4224.
Enclosure: Beaver Valley Power Station, Unit No. 2 LER 2023-001-00 cc:
NRC Region I Administrator NRC Senior Resident Inspector NRC Project Manager INPO Records Center (via INPO Industry Reporting and Information System)
BRP/DEP
Enclosure L-23-141 Beaver Valley Power Station, Unit No. 2 LER 2023-001-00
Abstract
Beaver Valley Power Station, Unit No. 2 00412 3
Indications Identified During Reactor Vessel Head Inspection 04 22 2023 2023 001 00 06 16 2023 D
000 Julie Hartig, Manager (Acting), Regulatory Compliance and Emergency Response 724-682-4224 B
On April 22, 2023, during the BVPS-2 twenty-third refueling outage (2R23), it was determined that two indications identified on the reactor pressure vessel head vent line did not meet the applicable acceptance criteria. Because the indications could not be dispositioned as acceptable per American Society of Mechanical Engineers (ASME) Code Section XI in a Reactor Coolant System pressure boundary, it was reported under Event Notification 56485 as a degraded condition per 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition, and is being reported under 10 CFR 50.73(a)(2)(ii)(A).
Primary Water Stress Corrosion Cracking (PWSCC) of the Alloy 600 penetration tube material was determined to be the cause of the identified flaws. The vent line penetration was repaired in accordance with NB-3200 of ASME Section III, ASME Code Case N-638-10, and relief request 2-TYP-4-RV-06.Page of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050
CORRECTIVE ACTIONS
Completed:
The flaws were repaired in accordance with NB-3200 of ASME Section III and ASME Code Case N-638-10 with two exceptions approved via relief request 2-TYP-4-RV-06. The repair was completed prior to startup in May 2023.
Planned:
The vent line penetration will be examined every outage as required by 10 CFR 50.55a and Code Case N-729-6.
Additional analysis for thermal stress and fatigue will be performed prior to the next refueling outage to confirm the repair meets ASME fatigue criteria for long term operation. This will be completed per corrective action CA-2023-03587-001.
PREVIOUS SIMILAR EVENTS
Similar reactor vessel head indications were found and repaired during the previous BVPS-2 refueling outages in 2021, 2020, 2018, 2014, 2012, 2009, 2008, and 2006.
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Beaver Valley Power Station, Unit No. 2 412 2023 001 00