ML23009B700

Review of the Spring 2022 Steam Generator Tub Inspections Report

ML23009B700
Person / Time
Site:	Point Beach
Issue date:	01/24/2023
From:	Scott Wall Plant Licensing Branch III
To:	Coffey B Point Beach
Wall, S P
References
EPID L-2022-LRO-0138
Download: ML23009B700 (1)

Text

January 24, 2023 Mr. Bob Coffey Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.

Juno Beach, FL 33408

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNIT 1 - REVIEW OF THE SPRING 2022 STEAM GENERATOR TUBE INSPECTIONS REPORT (EPID L-2022-LRO-0138)

Dear Mr. Coffey:

By letter dated October 13, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22286A079), NextEra Energy Point Beach, LLC (the licensee) submitted information summarizing the results of the spring 2022 steam generator (SG) inspections for the Point Beach Nuclear Plant (PBNP), Unit 1. This report was submitted in accordance with Technical Specification (TS) 5.6.8, Steam Generator Tube Inspection Report.

The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the 2022 SG tube inspection for PBNP, Unit 1. Based on this review, the NRC staff concludes that the information required by TS 5.6.8 has been provided and no additional follow-up action is required at this time. A summary of the NRC staff's review is enclosed.

Please feel free to contact me at (301) 415-2855 if you have any questions or concerns.

Sincerely,

/RA/

Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266

Enclosure:

Review of the Spring 2022 Steam Generator Tube Inspection Report cc: Listserv

REVIEW OF THE SPRING 2022 STEAM GENERATOR TUBE INSPECTION REPORT POINT BEACH NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-266 By letter dated October 13, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22286A079), NextEra Energy Point Beach, LLC (the licensee) submitted information summarizing the results of the spring 2022 steam generator (SG) inspections for the Point Beach Nuclear Plant (PBNP), Unit 1. These inspections were performed during refueling outage (RFO) 40. This report was submitted in accordance with Technical Specification (TS) 5.6.8, Steam Generator Tube Inspection Report.

PBNB, Unit 1 has two Westinghouse 44F SGs each containing 3,214 thermally treated Alloy 600 tubes. These SGs were installed during RFO 11 in 1984. The tubes have a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes are supported by six stainless steel broached-hole tube support plates (TSPs) with broached, quatrefoil-shaped holes, and one drilled-hole flow distribution baffle. Two sets of anti-vibration bars provide support to the U-bend region of the tubes. The U-bend region of the tubes in rows 1 through 8 was stress relieved after bending.

The licensee provided the scope, extent, methods, and results, of their SG tube inspections, in the document 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 and comments:

No corrosion-related degradation has been observed in the PBNB, Unit 1 SGs after approximately 32.8 effective full-power years of operation. No tubes have been plugged due to wear at support structures since RFO 26 in 2001.

A total of 15 tubes, all in SG B, were plugged during RFO 40.

o Fourteen tubes in Rows 1-3 were plugged, and seven of them also stabilized, due to a foreign object (FO) on the hot leg just below the fifth TSP. One tube had eddy current indications of wear and the presence of an object. The depth of the wear was 21 percent through-wall (TW). The other thirteen tubes were plugged based on proximity to the object, and some had eddy current indications of the possible presence of an object.

o One tube was plugged due to an indication attributed to FO wear on the hot leg at the second TSP, with no object present. This was the deepest indication found, with a depth of 36 percent TW.

The licensee saw no evidence of tube fouling or blockage of TSP openings in visual examinations of the uppermost (sixth) TSP in both SGs.

Enclosure

The licensee found no degradation during visual inspection of channel head and upper internal components.

The licensee continues to observe a low level of primary-to-secondary leakage, which ranged from 0.0 to 0.17 gallons per day during the two most recent operating cycles.

The licensee stated that the SG inspections in RFO 40 will be credited as the implementation inspection in a planned license amendment request to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections (ML21099A086).

Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by PBNP, Unit 1, TS 5.6.8. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since 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.

ML23009B700 *via memo OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DNRL/NCSG/BC*

NAME SWall SRohrer SBloom DATE 01/09/2023 01/10/2023 01/06/2023 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME NSalgado SWall DATE 01/24/2023 01/24/2023