ML23243A927
| ML23243A927 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/19/2023 |
| From: | V Sreenivas Plant Licensing Branch 1 |
| To: | Blair B Energy Harbor Nuclear Corp |
| Goetz S | |
| References | |
| EPID L-2023-LRO-0014 | |
| Download: ML23243A927 (1) | |
Text
September 19, 2023 Mr. Barry N. Blair Site Vice President Energy Harbor Nuclear Corp.
Beaver Valley Power Station Mail Stop P-BV-SSEB P.O. Box 4, Route 168 Shippingport, PA 15077-0004
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 1 - REVIEW OF THE FALL 2022 STEAM GENERATOR TUBE INSPECTION REPORT (EPID L-2023-LRO-0014)
Dear Mr. Grabnar:
By letter dated March 27, 2023, as supplemented by letter dated June 13, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML23087A063 and ML23164A048, respectively), Energy Harbor Nuclear Corp. submitted the Refueling Outage 22 (1R28) Steam Generator Tube Inspection 180 Day Report for Beaver Valley Power Station, Unit 1, in accordance with Technical Specification 5.6.6.1, Unit 1 SG [Steam Generator] Tube Inspection Report. The steam generator tube inspections were performed during the fall 2022 refueling outage.
The U.S. Nuclear Regulatory Commission staff has completed its review of the information provided and concludes that the licensee provided the information required by its technical specifications. The staffs review summary is enclosed.
B. Blair If you have any questions, please contact me at 301-415-2597 or by email to V.Sreenivas@nrc.gov Sincerely,
/RA/
V. Sreenivas, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
Steam Generator Tube Inspection 180 Day Report Summary cc: Listserv
Enclosure REVIEW OF THE FALL 2022 1R28 STEAM GENERATOR TUBE INSPECTION 180 DAY REPORT ENERGY HARBOR NUCLEAR CORP.
ENERGY HARBOR NUCLEAR GENERATION LLC BEAVER VALLEY POWER STATION, UNIT 1 DOCKET NO. 50-334 By letter dated March 27, 2023, as supplemented by letter dated June 13, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML23087A063 and ML23164A048, respectively), Energy Harbor Nuclear Corp. submitted the Refueling Outage 22 (1R28) Steam Generator Tube Inspection 180 Day Report for Beaver Valley Power Station, Unit 1, in accordance with Technical Specification 5.6.6.1, Unit 1 SG [Steam Generator] Tube Inspection Report. The steam generator tube inspections were performed during the fall 2022 refueling outage. Technical Specification 5.5.5.2 requires that an SG Program be established and implemented to ensure SG tube integrity is maintained.
Beaver Valley, Unit 1, is a 3-loop plant with Westinghouse Model 54F SGs. These SGs have 15.3 cumulative effective full power years of operation at the 1R28 refueling outage. Each SG contains 3,592 thermally treated Alloy 690 tubes with a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes are supported by broached stainless steel tube support plates (TSPs) and stainless steel anti-vibration bars (AVBs). The tubes were hydraulically expanded at both ends for the full depth of the tubesheet.
The U-bend region of rows 1 to 8 received a thermal stress relief prior to operation. Each feedwater spray nozzle internal to the SGs has small diameter holes that are designed to act as a loose parts strainer.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions, such as tube plugging taken in response to the inspection findings.
Based on the review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff has the following observations:
The tube degradation detected during 1R28 included wear at support structures and from foreign objects. The maximum depths of tube wear measured included: 12 percent through-wall (TW) TSP land wear, 26 percent TW TSP burr wear, 14 percent TW at AVBs, and 30 percent historical foreign object wear.
Two tubes were preventively plugged. Tube R41C52 in SG A had 12 percent TSP land wear that was extending close to a location of prior volumetric wear from a foreign object. Tube R30C59 in SG C contained a newly reported 29 percent TW foreign object wear indication.
Feedring and upper steam drum visual inspections were performed in all three SGs. The licensee concluded there are no active degradation mechanisms of the secondary side internals. These results do not change the planned inspection frequency of the steam drum components.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes that there are no current technical issues that warrant additional follow-up action. The inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
ML23243A927 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DNRL/NCSG/BC NAME VSreenivas KZeleznock SBloom DATE 08/28/2023 09/01/2023 07/19/2023 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME HGonzález VSreenivas DATE 09/19/2023 09/19/2023