ML101241219

Relief Request IR-3-02 Regarding Use of American Society of Mechanical Engineering Code,Section XI, 2004 Edition

ML101241219
Person / Time
Site:	Millstone
Issue date:	05/13/2010
From:	Sanders C Plant Licensing Branch 1
To:	Heacock D Dominion Nuclear Connecticut
Sandeers, Carleen, NRR/DORL, 415-1603
References
IR-3-02, TAC ME1255, FOIA/PA-2011-0115
Download: ML101241219 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 13, 2010 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 SUB..IECT: MILLSTONE POWER STATION, UNIT NO.3 - RELIEF REQUEST IR-3-02 REGARDING USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERING CODE, SECTION XI, 2004 EDITION (TAC NO. ME1255)

Dear Mr. Heacock:

By letter dated April 28, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091310666), Dominion Nuclear Connecticut, Inc. (DNC) submitted relief requests for the third 1O-year inservice inspection interval program at Millstone Power Station, Unit No.3. DNC requested the use of alternatives to certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI requirements. Specifically, relief request IR-3-02 requests relief from volumetric examination of the steam generators main steam outlet nozzles inside radius. The remaining relief requests contained in the April 28, 2009, letter were divided to be reviewed separately.

Relief request IR-3-02 was submitted under Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(g)(5)(iii), based on impracticality. As stated in the acceptance review letter dated June 25, 2009 (ADAMS Accession No. ML091750997), the NRC staff believes relief requests based on impracticality considerations should not be proposed for 10-year intervals in advance because changes that affect the ability to perform the examination, such as advancements in technology, may occur later in the interval. Therefore, relief requests of this type would be more appropriate later in the interval. As a result, the NRC staff is not reviewing relief request IR-3-02 at this time.

-2 Based on the information provided above, the NRC staff concludes its review of relief request IR-3-02 at this time. TAC Number ME1255 will be closed.

If you have any questions, please contact me at 301-415-1603.

SilJ Carleen J.

Plant Licen i g Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 cc w/encls: Distribution via Listserv

-2 Based on the above, the NRC staff concludes its review of relief request IR-3-02 at this time.

TAC Number ME1255 will be closed.

If you have any questions, please contact me at 301-415-1603.

Sincerely, IRN Carleen J. Sanders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 cc w/encls: Distribution via Listserv Distribution:

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