ML22298A297
| ML22298A297 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/27/2022 |
| From: | Scott Wall Plant Licensing Branch III |
| To: | Coffey B Point Beach |
| Wall, S P | |
| References | |
| EPID L-2022-LRO-0058 | |
| Download: ML22298A297 (1) | |
Text
October 27, 2022 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 2 - REVIEW OF THE FALL 2021 STEAM GENERATOR TUBE INSPECTIONS REPORT (EPID L-2022-LRO-0058)
Dear Mr. Coffey:
By letter dated April 27, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22117A172), NextEra Energy Point Beach, LLC (the licensee) submitted information summarizing the results of the fall 2021 steam generator (SG) inspections for the Point Beach Nuclear Plant (PBNP), Unit 2. 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 2021 SG tube inspection for PBNP, Unit 2. 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. 50-301
Enclosure:
Review of the Fall 2021 Steam Generator Tube Inspection Report cc: Listserv
Enclosure REVIEW OF THE FALL 2021 STEAM GENERATOR TUBE INSPECTION REPORT POINT BEACH NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-301 By letter dated April 27, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22117A172), NextEra Energy Point Beach, LLC (the licensee) submitted information summarizing the results of the fall 2021 steam generator (SG) inspections for the Point Beach Nuclear Plant (PBNP), Unit 2. These inspections were performed during refueling outage (RFO) 38. This report was submitted in accordance with Technical Specification (TS) 5.6.8, Steam Generator Tube Inspection Report.
PBNB, Unit 2, has two model Delta 47F recirculating replacement SGs designed and fabricated by Westinghouse. The SGs were put into service in 1997 during refueling outage (RFO) 22 and had operated for 21.4 effective full-power years at the time of the inspection. Each SG has 3,499 thermally treated Alloy 690 tubes that have a nominal outside diameter of 0.875 inch and a nominal wall thickness of 0.050 inch. The tubes are arranged in a triangular pattern and were hydraulically expanded at each end for the full depth of the tubesheet. The tubes are supported by a flow distribution baffle, seven tube support plates (TSPs) with broached trifoil-shaped holes, and anti-vibration bars (AVBs), all fabricated from stainless steel. The U-bend region of the tubes in rows 1 through 14 received a stress relieving thermal treatment after bending. The smallest U-bend radius is 3.25 inches.
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:
The only degradation mechanisms detected were mechanical wear at AVBs and mechanical wear at TSPs. No tubes were plugged during RFO 38. Overall, no tubes are plugged in SG-A and four tubes are plugged in SG-B.
The licensees secondary-side inspections included cleanliness of the top of the tubesheet after sludge lancing, foreign object search and recovery after sludge lancing, visual inspection of upper internals components (feedwater ring and supports, moisture separator components), and ultrasonic thickness measurements at select locations on the feedwater ring in each SG. These inspections detected no thinning or other degradation.
The licensee stated that the SG inspections in RFO 38 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). The inspection included full-length bobbin probe examination of all active tubes except for the lowest radius U-bends (rows 1 and 2), which were examined with rotating probes.
Enclosure Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by PBNP, Unit 2, 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.
- via memo OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DNRL/NCSG/BC*
NAME SWall SRohrer SBloom DATE 10/25/2022 10/26/2022 09/29/2022 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME NSalgado SWall DATE 10/27/2022 10/27/2022