ML20097E887
| ML20097E887 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/17/2020 |
| From: | Mahesh Chawla Plant Licensing Branch III |
| To: | Moul D Point Beach |
| Chawla M | |
| References | |
| EPID L-2019-LRO-0084 | |
| Download: ML20097E887 (3) | |
Text
April 17, 2020 Mr. Don Moul Vice President, Nuclear Division and Chief Nuclear Officer NextEra Energy Point Beach, LLC Mail Stop: NT3/JW 15430 Endeavor Drive Jupiter, FL 33478
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 1 - REVIEW OF THE SPRING 2019 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 38 (EPID L-2019-LRO-0084)
Dear Mr. Moul:
By letter dated October 12, 2019, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19287A002), NextEra Energy Point Beach, LLC (the licensee),
submitted information to U.S. Nuclear Regulatory Commission (NRC), summarizing the results of their steam generator tube inspections performed during the spring 2019 refueling outage at Point Beach Nuclear Plant, Unit 1.
The NRC staff has completed its review of this report and concludes that the licensee provided the information required by their technical specifications. No additional follow up is required at this time. The staffs review is enclosed.
If you have any questions concerning this matter, please contact me at (301) 415-8371 or via e-mail at Mahesh.Chawla@nrc.gov.
Sincerely,
/RA/
Mahesh Chawla, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266
Enclosure:
Staff Assessment cc: ListServ
Enclosure STAFF ASSESSMENT BY THE OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE SPRING 2019 STEAM GENERATOR TUBE INSPECTION REPORT NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-266 By letter dated October 12, 2019, (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML19287A002), NextEra Energy, Inc. (the licensee) submitted information summarizing the results of the spring 2019 steam generator (SG) tube inspections that were performed at Point Beach Nuclear Plant (Point Beach), Unit 1, during refueling outage (RFO) 38.
Point Beach, Unit 1, has two Westinghouse 44F SGs each containing 3,214 thermally-treated Alloy 600 tubes. These SGs were installed during refueling outage 11 in 1983. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches. The tubes are supported by six stainless steel tube support plates and a baffle plate. The tube support plate holes are quatrefoil shaped. 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 addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings. After reviewing the information provided by the licensee, the U.S.
Nuclear Regulatory Commission (NRC) staff has the following comments/observations:
A small grade wire was identified within the quatrefoil flow slot of the tube located at row 13, column 49 in SG A. No tube degradation was reported at the location of the foreign object and the tube was preventively plugged.
Discoloration and missing cladding in the channel head were identified by the licensee in previous inspections. The licensee inspected the channel head and divider plate assemblies during RFO 38 and stated that the cladding defect does not appear to be growing. Additionally, no evidence of rust coloration was observed in RFO 38.
A light coating of what appears to be magnetite was observed on the moisture separators with no degradation identified.
Point Beach, Unit 1, observed primary-to-secondary leakage ranging from 0.00 to 0.08 gallons per day since RFO 36. The leakage has existed for several cycles and does not appear to be increasing.
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 technical issues that warrant follow-up action currently, 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 Memorandum OFFICE DORL/LPL3/PM*
DORL/LPL3/LA*
DE/DNRL/NCSG/BC*
NAME MChawla SRohrer (R)
SBloom DATE 04/07/2020 04/07/2020 03/11/2020 OFFICE DORL/LPL3/BC*
DORL/LPL3/PM*
NAME NSalgado (RKuntz for)
MChawla DATE 04/17/2020 04/17/2020