ML103230045
| 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 Dominion Boulevard, Glen Allen, Virginia 23060 Web Address: www.dom.com November 18, 2010 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
NSSLlMLC Docket No.
License No.
10-137A RO 50-336 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