ML13294A394

Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 & 2, License Renewal Application (TAC Nos. MF0481 and MF0482) - Set 17

ML13294A394
Person / Time
Site:	Sequoyah
Issue date:	10/25/2013
From:	Richard Plasse Division of License Renewal
To:	James Shea Tennessee Valley Authority
Richard Plasse 301-415-1427
References
TAC MF0481, TAC MF0482
Download: ML13294A394 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joe W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority P.O. Box 2000 Soddy-Daisy, TN 37384 October 25, 2013

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)- SET 17

Dear Mr. Shea:

By letter dated January 7, 2013, Tennessee Valley Authority submitted an application pursuant to Title 10 of the Code of Federal Regulations (CFR) Part 54, to renew the operating license DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission staff. The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.

This request for additional information, outlined in the enclosure, was discussed with Henry Lee, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at Richard. Plasse@ nrc.gov.

Docket Nos. 50-327 and 50-328

Enclosure:

Request for Additional Information cc: Listserv Sincerely, Ric~se, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation

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Letter to J. Shea from R. Plasse dated October 25, 2013

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)- SET 17 DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRpb2 Resource RidsNrrDirRerb Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource beth.mizuno@ nrc.gov brian.harris@nrc.gov john. pelchat@ n rc.gov gena. woodruff@ nrc.gov siva.lingam@ nrc.gov wesley.deschaine@ nrc.gov galen.smith@ nrc.gov scott.shaeffer@ nrc.gov jeffrey.hamman@ nrc.gov craig.kontz@ nrc.gov caudle.julian @nrc.gov generette.lloyd@ epa.gov gmadkins@ tva.gov clwilson@tva.gov hleeO@tva.gov dllundy@tva.gov

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI B.1.23-2d (Follow-up)

Background:

By letter dated October 17, 2013, the applicant responded to request for additional information (RAI) B.1.23-2b, which addressed the applicant's operating experience regarding loss of material due to wear in thermal sleeves of control rod drive mechanism (CRDM) nozzles. In its response, the applicant revised its license renewal application (LRA) to identify loss of material and cracking as aging effects requiring management for the thermal sleeves. The applicant's response also indicates the applicant uses its lnservice Inspection Program to manage loss of material and cracking for the CRDM nozzle thermal sleeves.

The applicant further stated that in parallel with the volumetric examination or surface examination performed on the CRDM nozzles, the thermal sleeves of CRDM nozzles are examined for loss of material in accordance with Westinghouse Technical Bulletin TB-07-2. In addition, the applicant stated that the thermal sleeve examination inspects the area where the thermal sleeves penetrate underneath the reactor vessel head in the two outer most concentric rows of CRDM nozzles. The applicant also stated that areas of loss of material are identified and documented in the Corrective Action Program.

Issue:

The staff noted that the applicant's response does not address the following items which are necessary to demonstrate the adequacy of applicant's aging management for loss of material and cracking of the CRDM nozzle thermal sleeves.

Inspection methods to detect loss of material and cracking Inspection frequencies to manage loss of material and cracking Total number of thermal sleeves in the two outer most concentric rows of CRDM nozzles for each unit (as baseline information)

How the applicant's program confirms that loss of material and cracking are not occurring in thermal sleeves which are not located in the two outer most concentric rows of CRDM nozzles.

Request:

As discussed in the issue section of this RAI, identify the following items: (1) inspection methods to detect loss of material and cracking; (2) inspection frequencies to manage loss of material and cracking; (3) total number of thermal sleeves in the two outer most concentric rows of CRDM nozzles for each unit; and (4) how the applicant's program confirms that loss of material and cracking are not occurring in thermal sleeves which are not located in the two outer most concentric rows of CRDM nozzles.

In addition, justify why the applicant's inspection methods, frequencies and scopes are adequate to manage loss of material and cracking for the CRDM nozzle thermal sleeves.

ENCLOSURE