ML15181A249

Review of the Steam Generator Tube Inservice Inspection Report for the Spring 2014 Refueling 2014 Refueling Outage 21

ML15181A249
Person / Time
Site:	Catawba
Issue date:	07/06/2015
From:	Robert Pascarelli Plant Licensing Branch II
To:	Henderson K Duke Energy Carolinas
Miller G
References
TAC MF5459
Download: ML15181A249 (2)

Text

July 6, 2015 Mr. Kelvin Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, NC 29745

SUBJECT:

CATAWBA NUCLEAR STATION, UNIT 1 - REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE SPRING 2014 REFUELING OUTAGE 21 (TAC NO. MF5459)

Dear Mr. Henderson:

By letter dated September 25, 2014 (Agencywide Documents Access and Management System, (ADAMS) Accession No. ML14273A440), Duke Energy Carolinas, LLC (the licensee) submitted information summarizing the results of the spring 2014 Steam Generator (SG) tube inspections at the Catawba Nuclear Station, Unit No. 1. These inspections were performed during refueling outage 21. By letter dated May 15, 2015 (ADAMS Accession No. ML14273A440), Duke provided supplemental information to the report.

The NRC staff has completed its review of the information and concludes that Duke has provided the information required by the Catawba 1 Technical Specifications. No additional follow up is necessary at this time. The NRC staffs review of the SG inspection report is enclosed.

If you have any questions, please contact the Project Manager, G. Edward Miller at 301-415-2481 or via e-mail at ed.miller@nrc.gov.

Sincerely,

/RA/ Shawn Williams for Robert J. Pascarelli, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413

Enclosure:

As stated cc w/encl: Distribution via ListServ

ML14273A440), Duke provided supplemental information to the report.

The NRC staff has completed its review of the information and concludes that Duke has provided the information required by the Catawba 1 Technical Specifications. No additional follow up is necessary at this time. The NRC staffs review of the SG inspection report is enclosed.

If you have any questions, please contact the Project Manager, G. Edward Miller at 301-415-2481 or via e-mail at ed.miller@nrc.gov.

Sincerely,

/RA/ Shawn Williams for Robert J. Pascarelli, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413

Enclosure:

As stated cc w/encl: Distribution via ListServ DISTRIBUTION:

Public RidsNrrDeEgsb Resource AJohnson, NRR LPL2-1 R/F RidsRgn2MailCenter Resource GKulesa, NRR RidsNrrDorlLpl2-1 Resource KKarwoski, NRR AHuynh, NRR ADAMS Accession No.: ML15181A249 *Via SE Input OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DE/ESGB/BC NRR/DORL/LPL2-1/BC NAME GEMiller SFigueroa GKulesa (EMurphy for)* RPascarelli DATE 07/06/15 07/04/15 06/22/15 07/06/15 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RESULTS OF THE 2014 STEAM GENERATOR TUBE INSPECTIONS DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNIT 1 DOCKET NO. 50-413 By letter dated September 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14273A440), as supplemented by letter dated May 15, 2015 (ADAMS Accession No. ML15140A082), Duke Power Company, LLC (the licensee), submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections at Catawba Nuclear Station (Catawba), Unit 1. These inspections were performed during refueling outage 21.

Catawba, Unit 1 has four Babcock and Wilcox Model CFR 80 replacement SGs that were installed in 1996. Each SG has 6,633 thermally treated Alloy 690 tubes with an outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes were hydraulically expanded at each end for the full depth of the tubesheet and are supported by Type 410 stainless steel lattice grid tube supports and fan bars. The tubes in rows 1 through 27 were stress relieved after bending.

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 (e.g., tube plugging) taken in response to the inspection findings.

Based on a review of the information provided, the staff concludes that the licensee provided the information required by the Technical Specifications. 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.