ML11199A004

Response to NRC Request for Additional Information Regarding Relief Request 3-ISI-26

ML11199A004
Person / Time
Site:	Browns Ferry
Issue date:	07/14/2011
From:	Krich R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11199A004 (7)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing July 14, 2011 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

Response to NRC Request for Additional Information Regarding Relief Request 3-ISI-26

References:

1. NRC letter to TVA, "Browns Ferry Nuclear Plant, Unit 3 - Request for Additional Information Regarding Relief from Weld Examination Coverage Requirements, Request for Relief 3-1SI-26 (TAC No.

ME5914)," dated June 10, 2011

2. TVA letter to NRC, "American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-1SI-26," dated March 21, 2011 On March 21, 2011, the Tennessee Valley Authority (TVA) submitted a Request for Relief 3-ISI-26 for Browns Ferry Nuclear Plant, Unit 3(Reference 2). On June 10, 2011, the NRC transmitted a Request for Additional Information (RAI) (Reference 1).

The Enclosures to this letter provide the TVA's response to the RAI and supporting information. The due date for this response is July 15, 2011.

printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 July 14, 2011 There are no new regulatory commitments contained in this letter. Please direct any questions concerning this matter to Tom Matthews at (423) 751-2687.

Respectfully, R. M. Krich

Enclosures:

1. TVA Responses to NRC Request for Additional Information Questions

2. Reference Report R-032 cc (Enclosures):

NRC Regional Administrator- Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

ENCLOSURE I Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-1Sl-26, Updated Risk Informed Inservice Inspection Program TVA Responses to NRC Request for Additional Information Questions By letter dated March 21, 2011 (Agencywide Document Access and Management System Accession No. ML110830037), Tennessee Valley Authority, the licensee for Browns Ferry Nuclear Plant, Unit 3 (BFN-3), submitted a request for relief (RR) from American Society of Mechanical Engineers (ASME Code), Boiler and Pressure Vessel Code Section X1 requirements,in accordance with the provisions of Title 10 of the Code of FederalRegulations, Part 50, Section 50.55a, Paragraph(a)(3)(iii)*. This RR pertains to the third inservice inspection interval at BFN-3, which ends on November 18, 2015. The subject weld is a reactorpressure vessel nozzle-to-vessel (head)full penetration weld (N6A-NV).

In order to complete its review of the licensee's submittal, the U.S. Nuclear Regulatory Commission staff requires a response to the following questions:

NRC Question 1: Have any visual examinations been conducted on the associatednozzle inner radius area, such as those allowed by ASME Code Case N-648-1, 'Alternative Requirements for Inner Radius Examinations of Class I Reactor Vessel Nozzles, Section X1, Division 1"?

TVA Response: The inner radius of vessel (head) nozzle N6A (N6A-IR) was visually examined during the Unit 3 Cycle 13 (U3C13) refueling outage (March 25, 2008) that was in the first period of the third inservice inspection interval. This inspection was in accordance with ASME Code Case N-648-1. Please see Reference Report R-032 in Enclosure 2.

NRC Question 2: If any such inspections have been completed, were any indications found in the associated N6A-NV nozzle-to-vessel head weld? If so, please describe each indication in detail.

TVA Response: No indications were found when the inner radius of vessel (head) nozzle N6A (N6A-IR) was visually examined during the U3C13 refueling outage (March 25, 2008).

• Note: The NRC clarified in an e-mail to TVA, that 10 CFR 50.55a(g)(5)(iii) is the correct reference, and not 10 CFR 50.55a(a)(3)(iii), as stated in the paragraph above.

ENCLOSURE 2 Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-26, Updated Risk Informed Inservice Inspection Program Reference Report R-032

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Tgou Ferry Rd 00029 Soddy Daisy, Tn 37379 Part Nomenclature Enhanced VT-1 Illumination Cards We certify that the product mentioncd above was subject to a quality inspection and testing procedure. It meets the test specifications for this product, All measuring tools used for testing are calibrated and traceable back to NIST.

In view of the measures taken by us for the product quality assurance, we assure you of the conformity with the product data specified in the operating specification.

DATE CERTInIED; October 04, 2002 CERTIICED BY: r' TITLE: -Vi-deresident Thc following Test Equipment was used to CERTTY the <.001 Dia. Iron Wire on the VT-I Cards:

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