AEP-NRC-2018-73, Supplement to Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination

Supplement to Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination

ML18277A153
Person / Time
Site:	Cook
Issue date:	10/02/2018
From:	Lies Q Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML18277A182	List: AEP-NRC-2018-73, Supplement to Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination
References
AEP-NRC-2018-73
Download: ML18277A153 (2)

Text

Indiana Michigan Power Company Nuclear Generation Group INDIJINA One Cook Place MICHIGAN Bridgman, Ml 49106 POWER aep.com October 2, 2018 AEP-NRC-2018-73 10 CFR 50.55a Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Supplement to Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination

Reference:

1. Letter from Q. S. Lies, Indiana Michigan Power Company, to U. S. Nuclear Regulatory Commission, "Donald C. Cook Nuclear Plant Units 1 and 2, Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination," dated June 14, 2018, Agencywide Documents Access and Management System Accession No. ML18169A148.

By Reference 1, Indiana Michigan Power Company (l&M), the licensee for Donald C. Cook Nuclear Plant Units 1 and 2, submitted a request for Nuclear Regulatory Commission (NRC) review and approval of a proposed alternative to the examination requirements *of American Society of Mechanical Engineers, Section XI, Examination Category B-G-1, Item Number B6.40, Threads in

• Flange.

By Enclosure to Reference 1, I&M previously provided an evaluation of the proposed alternative. The evaluation used as a reference, documents a 2017 Technical Report, No. 3002010354, issued by the Electric Power Research Institute (EPRI).

In order to facilitate NRC review of Reference 1, EPRI Technical Report No. 3002010354, Reactor Pressure Vessel (RPV) Threads in Flange Examination Requirements, is provided as an enclosure to this letter.

U. S Nuclear Regulatory Commission AEP-NRC-2018-73 Page 2 There are no new regulatory commitments made in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.

Sincerely, Ql~l~

Site Vice President BMC/mll

Enclosure:

1. EPRI Technical Report No. 3002010354, Reactor Pressure Vessel (RPV) Threads in Flange Examination Requirements c: R. J. Ancona - MPSC A. W. Dietrich, NRG, Washington D.C.

MDEQ - RMD/RPS NRG Resident Inspector K. S. West- NRG Region Ill A. J. Williamson - Ft. Wayne AEP, w/o enclosure