ML14254A204

Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application - Set 22 (TAC Nos. MF0481 and MF0482)

ML14254A204
Person / Time
Site:	Sequoyah
Issue date:	09/22/2014
From:	Sayoc E License Renewal Projects Branch 1
To:	James Shea Tennessee Valley Authority
Sayoc E, 415-4084
References
TAC MF0481, TAC MF0482
Download: ML14254A204 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 22, 2014 Mr. Joe W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority P.O. Box 2000 Soddy-Daisy, TN 37384

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 22 (TAC NOS. MF0481 AND MF0482)

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.

These requests for additional information, outlined in the enclosure were 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 301-415-4084 or by e-mail at Emmanuel.Sayoc@nrc.gov.

Sincerely,

/RA/

Emmanuel Sayoc, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328

Enclosure:

Requests for Additional Information cc w/encl: Listserv

ML14254A204 *concurred via email OFFICE LA:DLR/RPB2 PM:DLR/RPB1 BC:DLR/RPB1 PM:DLR/RPB1 NAME *IKing ESayoc YDiaz-Sanabria ESayoc DATE 9/17/14 9/17/14 9/18/14 9/18/14

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 22 (TAC NOS. MF0481 AND MF0482)

DISTRIBUTION:

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E. Keegan B. Harris (OGC)

C. Kanatas(OGC)

E. Brown J. Uribe

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION SUPPLEMENTAL REQUESTS FOR ADDITIONAL INFORMATION RAI B.1.34-9c

Background

By letter dated, August 21, 2014, the applicant provided its response to request for additional information (RAI) B.1.34-9b. In its response the applicant identified that it exceeded one of the fuel loading threshold criteria bounding assumptions made in Electric Power Research Institute (EPRI) Technical Report (TR) No. MRP-227-A (EPRI Letter No. 2013-025, dated October 14, 2013). The EPRI Material Reliability Project (MRP) states that for Westinghouse-designed reactors, the distance from the top of the active fuel to the bottom of the upper core plate (UCP) in the reactor vessel internal (RVI) upper core assembly should be greater than or equal to 12.2 inches. In its response, the applicant indicated that the active fuel to UCP distance was less than 12.2 inches for more than two effective full-power years. The applicant stated that it projected the maximum fast neutron fluence above the UCPs to be below the screening criteria for irradiation embrittlement of materials located above the UPC over 60 years of operation.

Issue In Table 3-3 of TR No. MRP-227-A, the EPRI MRP identifies that irradiation-assisted stress corrosion cracking (IASCC) and irradiation embrittlement (IE) are aging mechanisms that may occur in Westinghouse-designed UCPs. However, the applicants response to RAI B.1.34-9b does not indicate the specific values of the active fuel to UCP distance, the duration in which operations of the Sequoyah facility were out of conformance with this parameter, or the projected fluence after 60 years. Therefore, a more-detailed quantitative response is necessary to demonstrate that operations of the applicants units are still within the fuel loading and operation assumptions of TR MRP-227-A.

Request

1) Provide a brief description of the analysis and methodology used to make the determination that for materials located above the UCPs, the projected fluence after 60 years of operation will be below the threshold limit.

2) Identify the neutron fluence values that are used as the lower-bound neutron fluence thresholds for inducing IASCC and IE in materials located above the UCPs of the Sequoyah Nuclear Plant, Units 1 and 2. Provide the projected neutron fluence values for the UCPs through 60 years of licensed operation.

ENCLOSURE