ML19337A170

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Review of the Spring 2019 Steam Generator Tube Inspection Report (2R26)
ML19337A170
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/12/2019
From: Shawn Williams
Plant Licensing Branch II
To: Gayheart C
Southern Nuclear Operating Co
Williams S
References
EPID L-2019-LRO-0085
Download: ML19337A170 (3)


Text

December 12, 2019 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company 3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 - REVIEW OF THE SPRING 2019 STEAM GENERATOR TUBE INSPECTION REPORT (2R26)

(EPID L-2019-LRO-0085)

Dear Ms. Gayheart:

By letter dated October 24, 2019, Southern Nuclear Operating Company (the licensee),

submitted a report summarizing the results of the steam generator tube inspections performed at Joseph M. Farley Nuclear Plant, Unit 2, during the twenty-sixth refueling outage (2R26)

The NRC staff has completed its review of the report and concludes that the licensee provided the information required by their technical specifications and that no additional follow-up is required at this time. The NRC staffs review is enclosed.

If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.

Sincerely,

/RA/

Shawn A. Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364

Enclosure:

As Stated cc: Listserv

JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 NRC STAFF REVIEW OF THE SPRING 2019 STEAM GENERATOR TUBE INSPECTION REPORT DOCKET NO. 50-364 By letter dated October 24, 2019 (Agencywide Documents Access System (ADAMS) Accession No. ML19297F823), Southern Nuclear Operating Company (the licensee), submitted a report summarizing the results of the steam generator (SG) tube inspections performed at Joseph M.

Farley Nuclear Plant (Farley), Unit 2, during the twenty-sixth refueling outage (2R26).

Farley, Unit 2, has three Westinghouse Model 54F replacement steam generators, which were installed in 2001. Each SG contains 3,592 thermally treated Alloy 690 tubes. The tubes have a nominal outside diameter of 0.875 inch and nominal wall thickness of 0.050 inch. The tubes are supported by a flow distribution baffle, tube support plates, and antivibration bars, all made from Type 405 stainless steel.

The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above.

Based on a review of the information provided, the staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes 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.

Enclosure

ML19337A170 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DNRL/NCSG/BC DORL/LPL2-1/BC MMarkley NAME SWilliams KGoldstein SBloom (MMahoney for)

DATE 12/3/19 12/10/19 12/2/19 12/12/19 OFFICE DORL/LPL2-1/PM NAME SWilliams DATE 12/12/19