ML103230045: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:Dominion Nuclear Connecticut, Inc .
{{#Wiki_filter: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.
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.
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).
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|date=March 30, 2010|text=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)
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."
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.
In October 2010, the NRC issued RG 1.147, Revision 16, which approved the use of ASME Code Case N-513-3.
If you have any questions regarding this submittal , please contact Mr. William D.
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.
Bartron at (860) 444-4301.
Sincerely ,
Sincerely, ce resident - Nuclear Engineering Attachments: None Commitments made in this letter:
ce resident - Nuclear Engineering Attachments: None Commitments made in this letter: None
None


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


==Reference:==
==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.
ONC Letter 10-137, "Millstone Power Station Unit 2, Relief Requests RR-04-02 ,
cc:
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.
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}}
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}}

Latest revision as of 01:16, 14 January 2025

Withdrawal of Relief Request RR-04-03 for the Use of ASME Code Case N-513-2
ML103230045
Person / Time
Site: Millstone Dominion icon.png
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)
v • d • e


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

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