NRC-17-0081, Supplement to Revised Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval

Supplement to Revised Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval

ML17342A978
Person / Time
Site:	Fermi
Issue date:	12/08/2017
From:	Polson K DTE Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-17-0081
Download: ML17342A978 (2)

Text

Keith J. Poison Senior Vice President and CNO DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.6515 Fax: 734.586.4172 Email: keith.polson@dteenergy.com i;A DTE Energy-December 8, 2017 NRC-17-0081 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.

20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Supplement to Revised Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval

References:

1)

DTE Electric Letter to NRC, "Submittal of Revised Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval," NRC-17-0062, dated September 26, 2017 (ML17270A036)

In Reference 1, DTE Electric Company (DTE) submitted relief request RR-A37, Revision 1, for the third 10-year interval of the Fermi 2 Inservice Inspection (IS I)

Program. The subject revised relief request involves implementation of ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1." Code Case N-702 stipulates that VT-1 examination may be used in lieu of the volumetric examination for the Reactor Pressure Vessel (RPV) nozzle inner radius section (ASME Code, Category B-D, Item B3.100).

As a supplement to relief request RR-A37, Revision 1, DTE will utilize ASME Code Case N-648-1, "Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles,Section XI, Division 1," with associated required Regulatory Guide 1.147 conditions if VT-1 examinations are performed in lieu of volumetric examinations.

No new commitments are being made in this submittal.

USNRC NRC-17-0081 Page 2 Should you have any questions or require additional information, please contact Mr. Scott A. Maglio, Manager -Nuclear Licensing, at (734) 586-5076.

Sincerely, Keith J. Polson Senior Vice President and CNO cc: NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 5, Region III Regional Administrator, Region III Michigan Public Service Commission Regulated Energy Division (kindschl@michigan.gov)