ML15209A878

Request for Additional Information

ML15209A878
Person / Time
Site:	Farley
Issue date:	07/31/2015
From:	Shawn Williams Plant Licensing Branch II
To:	Pierce C Southern Nuclear Operating Co
williams s
References
TAC MF6207
Download: ML15209A878 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 .

Juiy 31, aJ15 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MF6207)

Dear Mr. Pierce:

By letter dated May 11, 2015, the Southern Nuclear Operating Company, Inc., (SNC) submitted a steam generator tube inspections report performed during the twenty-third refueling outage (2R23) at the Joseph M. Farley Nuclear Plant, Unit 2.

The U.S. Nuclear Regulatory Commission (NRG) staff has determined that additional information is needed as discussed in the Enclosure. We request that SNC respond within 30 days of the date of this letter. Please note that the NRG staffs review is continuing and further requests for information may be developed.

Sincerely, Shawn Williams, Project Manager Plant Licensing Branch, 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 2015 STEAM GENERATOR INSPECTIONS SOUTHERN NUCLEAR OPERATING COMPANY, INC.

DOCKET NO. 50-364 By letter dated May 11, 2015 (Agencywide Documents Access and Management System Accession No. ML15131A333), the Southern Nuclear Operating Company, lnc.,(SNC) submitted a report of a steam generator tube inspections report performed during the twenty-third refueling outage (2R23) at the Joseph M. Farley Nuclear Plant, Unit 2.

The NRC staff has reviewed the report and determined that additional information is necessary to complete the review.

RAI No. 1 Please discuss the results of the chanriel head inspections.

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?

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?

Enclosure

ML15209A878 OFFICE LPL2-1/PM LPL2-1/LA NRR/DE/ESGB/BC LPL2-1/BC LPL2-1/PM GKulesa* RPascarelli NAME SWilliams SFigueroa SWilliams

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DATE 07/30/15 07/30/15 07/28/15 07/31/15 07/31/15