NL-15-1631, Response to Request for Additional Information for 2R23 Steam Generator Tube Inspection Report

Response to Request for Additional Information for 2R23 Steam Generator Tube Inspection Report

ML15240A372
Person / Time
Site:	Farley
Issue date:	08/28/2015
From:	Pierce C Southern Nuclear Company, Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-1631, TAC MF6207
Download: ML15240A372 (4)

Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 SOUTHERN * \

AUG 2 8 2015 Fax 205.992.7601 NUCLEAR A SOUTHERN COMPANY Docket Nos.: 50-364 NL-15-1631 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Unit 2 Response to Request for Additional Information for 2R23 Steam Generator Tube Inspection Report (TAC No. MF6207)

Ladies and Gentlemen:

By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML15131A333), Southern Nuclear Operating Company, Inc. (SNC) submitted a steam generator tube inspection report performed during the twenty-third refueling outage (2R23) at Joseph M.

Farley Nuclear Plant (FNP), Unit 2. The Nuclear Regulatory Commission (NRC) issued a request for additional information via a letter dated July 31, 2015 (ADAMS Accession Number ML15209A878). The enclosure to this letter contains the SNC responses to that request.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Mr. C. R. Pierce states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.

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J C .R. Pierce Regulatory Affairs Director CRP/JMC Sworn to and subscribed before me this l.. g~ day of ~ us:f= '2015.

CLsl!lhf Notary Public My commission expires: 1- 2.- Z. 0 If

U.S. Nuclear Regulatory Commission NL-15-1631 Page 2

Enclosure:

SNC Response to Request for Additional Information for FNP 2R23 Steam Generator Tube Inspection Report cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Best, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President- Farley Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J . Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. L. D. Wert, Regional Administrator (Acting)

Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley

Joseph M. Farley Nuclear Plant, Unit 2 Response to Request for Additional Information for 2R23 Steam Generator Tube Inspection Report {TAC No. MF6207)

Enclosure SNC Response to Request for Additional Information for FNP 2R23 Steam Generator Tube Inspection Report

Enclosure to NL-15-1631 SNC Response to Request for Additional Information for FNP 2R23 Steam Generator Tube Inspection Report By letter dated May 11, 2015, Southern Nuclear Operating Company, Inc. (SNC) submitted a steam generator tube inspection report performed during the twenty-third refueling outage (2R23) at Joseph M. Farley Nuclear Plant (FNP), Unit 2.

The Nuclear Regulatory Commission (NRC) issued a request for additional information via a letter dated July 31, 2015. This enclosure contains the SNC responses to that request.

NRC RAI No.1 Please discuss the results of the channel head inspections.

SNC Response to RAI No. 1 A visual inspection of the steam generator channel head bowl was performed in all steam generators during FNP 2R23. Visual inspections of the steam generator hot leg and cold leg divider plates and drain lines were performed, inclusive of the entire divider plate to channel head weld and all visible clad surfaces. No degradation was observed in the channel heads of all three steam generators.

NRC RAI No.2 With regards to the steam drum and feedring inspections, it is stated that "there were no structural anomalies." Was any degradation observed?

SNC Response to RAI No. 2 The steam drum and feedring were inspected for structural integrity, degradation, excessive deposits, flow accelerated corrosion, erosion, blockage, and overall condition. There were no structural anomalies and no degradation was observed in any of the steam drum and feed ring components.

NRC RAI No.3 Please clarify the scope of your bobbin exams and your +Point' exams of the U-bend region of rows 1 and 2. Specifically, were all tubes that were not inspected in RFO 21 inspected in RFO 23 or were 50 percent of the tubes that were not inspected in RFO 21 inspected in RFO 23?

SNC Response to RAI No. 3 All tubes that were not inspected during the twenty-first refueling outage (2R21) were inspected during 2R23 such that all tubes were inspected in the combined two inspection cycles 2R21 and 2R23.

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