ML092170275

Request for Additional Information for Second 10-Year Interval Inservice Inspection Program Plan Relief Request 2-ISI-19 Revision 1

ML092170275
Person / Time
Site:	Browns Ferry
Issue date:	08/21/2009
From:	Ellen Brown Plant Licensing Branch II
To:	Swafford P Tennessee Valley Authority
Brown E, NRR/DORL, 415-2315
References
TAC ME0764
Download: ML092170275 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 21, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UI\JIT 2 - REQUEST FOR ADDITIONAL INFORMATION FOR SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST 2-ISI-19 REVISION 1 (TAC NO. ME0764)

Dear Mr. Swafford:

By letter dated March 2, 2009, the Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Browns Ferry Nuclear Plant, Unit 2.

In accordance with Title 10 of the Code of Federal Regulations, Section 50.55a(g)(5)(iii), the licensee has submitted Relief Request (RR) 2-ISI-19, Rev. 1, for certain limited Class 1 component weld examinations. The ASME Code requires that 100 percent of the examination volumes or surface areas described in ASME Code,Section XI, be performed during each interval. The licensee determined that the required examination coverage of 100 percent was impractical to obtain.

The U.S. Nuclear Regulatory Commission (NRC) staff requires additional information in order to complete its evaluation of RR 2-IS 1-19 Revision 1. A response to the enclosed Request for Additional Information is needed before the NRC staff can complete the review. This request was discussed with Mr. Dan Green of your staff on August 21,2009, and it was agreed that TVA would respond within 30 days from the date of this letter.

P. Swafford -2 If you have any questions, please contact me at (301) 415-2315.

Sincerely,

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Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260

Enclosure:

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

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 2-ISI-19, REVISION 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260

1. Page E1-7 of the submittal is the beginning of a table that summarizes several (and different) ultrasonic angles and modes of propagation that were used to interrogate various reactor pressure vessel nozzle-to-vessel welds. Provide a description of any modeling performed in support of the varied angles and modes of ultrasonic propagation that were applied.

2. The highest angle of ultrasonic examination employed is listed as 60-degrees, for both shear and refracted longitudinal waves. Based on the drawings provided for the subject welds, it appears that greater American Society of Mechanical Engineers Code volume examination coverage could be obtained if a higher probe-angle was used. Clarify why higher probe angles were not exercised to maximize coverage on these welds.

Enclosure

P. Swafford - 2 If you have any questions, please contact me at (301) 415-2315.

Sincerely, IRA SLingam fori Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-2 RlF RidsNrrDorlLpl2-2 RidsNrrPMBrownsFerry RidsAcrsAcnw_MailCenter RidsOgcRp RidsRgn2MailCenter RidsNrrDorl RidsNrrLABClayton (Hard Copy)

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