ML103230045

Withdrawal of Relief Request RR-04-03 for the Use of ASME Code Case N-513-2

ML103230045
Person / Time
Site:	Millstone
Issue date:	11/18/2010
From:	Price J Dominion, Dominion Nuclear Connecticut
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
10-137A, FOIA/PA-2011-0115
Download: ML103230045 (2)

Text

Dominion Nuclear Connecticut, Inc .

5000 D ominion Boulevard, Glen Allen, Virginia 23060 Web Address: www.do m.com November 18, 2010 U.S. Nuclear Regulatory Commission Serial No. 10-137A Attention: Document Control Desk NSSLlMLC RO Washington , DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 WITHDRAWAL OF RELIEF REQUEST RR-04-03 FOR THE USE OF ASME CODE CASE N-513-2 In a letter dated March 30, 2010 (ADAMS Ascension No. ML100900200), Dominion Nuclear Connecticut, Inc. (DNC) submitted Relief Request RR-04-03 for the use of American Society of Mechanical Engineers (ASME) Code Case N-513-2 (Reference).

The duration of the proposed request was for the current Millstone Power Station Unit 2 (MPS2) fourth 10-year inservice inspection interval or until such time as Code Case N-513-3 was accepted for use in a later revision of Nuclear Regulatory Commission (NRC)

Regulatory Guide (RG) 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1."

In October 2010 , the NRC issued RG 1.147, Revision 16, which approved the use of ASME Code Case N-513-3. Because this code case is now endorsed by the NRC, Relief Request RR-04-03 is no longer needed. Hence, DNC hereby withdraws its request for NRC approval of Relief Request RR-04-03.

If you have any questions regarding this submittal , please contact Mr. William D.

Bartron at (860) 444-4301.

Sincerely ,

ce resident - Nuclear Engineering Attachments: None Commitments made in this letter: None

Serial No. 10-137A Docket No. 50-336 Withdrawal of Relief Request RR-04-03 Page 2 of 2

Reference:

ONC Letter 10-137, "Millstone Power Station Unit 2, Relief Requests RR-04-02 ,

Alternative VT-2 Pressure Testing Requirements for the Lower Portion of the Reactor Pressure Vessel and RR-04-03, Alternative Evaluation Criteria for Code Case N-513-2, Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping ," dated March 30,2010.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders, Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-883 Rockville, MO 20852-2738 NRC Senior Resident Inspector Millstone Power Station