ML14162A587

Donald C. Cook Nuclear Plant, Unit 1 - Review of the 2013 Refueling Outage Steam Generator Tube Inservice Inspection Results (TAC MF3057)

ML14162A587
Person / Time
Site:	Cook
Issue date:	06/18/2014
From:	Wengert T J Plant Licensing Branch III
To:	Weber L J Indiana & Michigan Electric Co
Thomas Wengert, NRR/DORL 415-4037
References
TAC MF3057
Download: ML14162A587 (3)

Text

REGu, _ <( 0 .... ii: !/) :: '1/. ****_. Mr. Lawrence Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 June 18, 2014

SUBJECT: DONALD C. COOK NUCLEAR PLANT, UNIT 1 -REVIEW OF THE 2013 REFUELING OUTAGE STEAM GENERATOR TUBE INSERVICE INSPECTION RESULTS (TAC NO. MF3057)

Dear Mr. Weber:

By letter dated November 11, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 13317A074), Indiana Michigan Power Company (the licensee) submitted information summarizing the results of the 2013 steam generator (SG) inspections at Donald C. Cook Nuclear Plant, Unit 1. The U.S. Nuclear Regulatory Commission (NRC) staff documented additional information concerning the 2013 steam generator inspections in a letter dated July 15, 2013 (ADAMS Accession No. ML 13189A226). The licensee provided additional information regarding the SG inspections on January 31, 2014 (ADAMS Accession No. ML 14049A445). The NRC staff has completed its review of the information provided and concludes that the licensee provided the information required by their technical specifications and no additional follow-up is required at this time. The staff's review is enclosed. Please direct any inquiries to me at 301-415-4037, or thomas.wengert@nrc.gov. Docket No. 50-315

Enclosure:

Review of the 2013 Steam Generator Tube Inspections Results cc w/encl: Distribution via Listserv

Sincerely,Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF RESULTS OF 2013 STEAM GENERATOR TUBE INSPECTIONS DONALD C. COOK NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-315 By letter dated November 11, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 13317A074), Indiana Michigan Power Company (the licensee) submitted information summarizing the results of the 2013 steam generator (SG) inspections at Donald C. Cook, Unit 1. The U.S. Nuclear Regulatory Commission (NRC) staff documented additional information concerning the 2013 SG inspections in a letter dated July 15, 2013 (ADAMS Accession No. ML 13189A226). The licensee provided additional information regarding the SG inspections on January 31, 2014 (ML 14049A445). Donald C. Cook Nuclear Plant, Unit 1 has four Model 51 R recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 3,496 thermally treated, Alloy 690 tubes that have a nominal outside diameter of 0.875 inches, and a nominal wall thickness of 0.049 inches. The tubes are supported by Type 410 stainless steel, lattice-grid tube supports, and flat fan bars. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. 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. After review of the information provided by the licensee, the NRC staff has the following comments/observations:

• The number of new fan bar wear indications this outage showed a significant decrease from the prior inspection outage.

• There was a slight increase in the number of new lattice grid wear indications this outage. Based on a review of the information provided by the licensee, the NRC staff concludes that the licensee provided the information required by its technical specifications. The SG tube inspections at Donald C. Cook Nuclear Plant, Unit 1 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 Mr. Lawrence