05000334/LER-2022-001, Manual Reactor Trip and Auxiliary Feedwater Actuation Due to Heater Drain System Valve Failure
| ML22222A122 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/10/2022 |
| From: | Grabnar J Energy Harbor Nuclear Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-22-186 LER 2022-001-00 | |
| Download: ML22222A122 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(B)(1) 10 CFR 50.73(a)(2)(iv)(B)(6) |
| 3342022001R00 - NRC Website | |
text
energy harbor John J. Grabnar Site Vice President August 10, 2022 L-22-186 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 2022-001-00 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) 2022-001-00, "Manual Reactor Trip and Auxiliary Feedwater Actuation due to Heater Drain System Valve Failure". This event is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(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 Mr. Steve Sawtschenko, Manager, Regulatory Compliance and Emergency Response, at 724-682-4284.
Sincerely, John J. Grabnar Enclosure: Beaver Valley Power Station, Unit 1 LER 2022-001-00 cc:
Mr. D. C. Lew, NRC Region I Administrator NRC Senior Resident Inspector Mr. B. Ballard, NRC Project Manager INPO Records Center (via INPO Industry Reporting and Information System)
Mr. L. Winker (BRP/DEP)
Enclosure L-22-186 Beaver Valley Power Station, Unit 1 LER 2022-001-00
Abstract
Beaver Valley Power Station, Unit 1 334 4
Manual Reactor Trip and Auxiliary Feedwater Actuation due to Heater Drain System Valve Failure 06 15 2022 2022 001 00 08 10 2022 1
100
Steve Sawtschenko, Manager, Regulatory Compliance and Emergency Response 724-682-4284 B
SN LCV M120 Y
At 0724 on June 15, 2022 while at approximately 100 percent power, the Beaver Valley Power Station, Unit No. 1 (BVPS-1) reactor was manually tripped due to lowering steam generator water levels. This was due to reduced heater drain flow from the heater drain system (HDS) to the main feedwater pumps (MFPs) when the heater drain receiver normal level control valve, LCV-1SD-106B, experienced a valve plug to stem separation. The Operators manually tripped the reactor as required per the predefined trip criteria for low steam generator water level.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(iv)(A) as an event that resulted in a manual actuation of the Reactor Protection System, 10 CFR 50.73(a)(2)(iv)(B)(1), and the automatic actuation of the Auxiliary Feedwater System, 10 CFR 50.73(a)(2)(iv)(B)(6). Corrective actions include replacing the plug, stem, and pin (trim) of LCV-1SD-106B with an enhanced design during the next refueling outage (Fall 2022).
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I ID Page of 05000-
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
CORRECTIVE ACTIONS
Completed Actions:
- 1) The level control valve, LCV-1SD-106B, was repaired with a new trim. BVPS-1 was returned to service and synchronized to the grid on June 17, 2022.
Planned Actions:
- 1) Replace the trim of LCV-1SD-106B with an enhanced design during the next refueling outage (Fall 2022). The new valve assembly will have an improved shouldered stem design, a hardened stem pin, and a hardened stainless-steel stem to resolve the potential for loosening.
- 2) Evaluate whether LCV-1SD-106B should be classified as a SPV.
PREVIOUS SIMILAR EVENTS
A review of the previous three years was performed. A previous event occurred in May 2021 when LCV-1SD-106B failed due to a plug/stem separation. The valve was repaired by replacing the stem and pin, however the existing plug was reinstalled due to parts availability. The organization did not have an adequate consequence bias for risk as it was perceived that the used plug would allow the valve to operate reliably to the next refueling outage, and that the organization could predict and control the plant should the valve exhibit degradation.
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