ML19099A326

Summary of Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2

ML19099A326
Person / Time
Site:	Cook
Issue date:	04/16/2019
From:	Robert Kuntz Plant Licensing Branch III
To:	Gebbie J Indiana Michigan Power Co
Kuntz R, 415-3733
References
EPID L-2019-LRM-0016
Download: ML19099A326 (4)

Text

FACILITY: Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2

SUMMARY

OF APRIL 2, 2019, MEETING WITH INDIANA MICHIGAN POWER COMPANY REGARDING DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 (EPID L-2019-LRM-0016)

On April 2, 2019, a Category I public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Indiana Michigan Power Company (the licensee) via teleconference. This meeting was open to members of the public. No regulatory decisions were made at this meeting.

The purpose of the meeting was to discuss a planned relief request for Donald C. Cook Nuclear Plant (CNP), Units Nos. 1 and 2. The licensee intends to submit a request for relief from the American Society for Mechanical Engineering (ASME) Code. Specifically, the licensee plans to seek relief related to the inspection requirements related to certain pressure retaining welds in the reactor vessel. The meeting notice and agenda, dated March 21, 2019, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19080A098. A list of attendees is provided as Enclosure 1.

The licensee discussed previous relief requests granted for CNP, Units 1 and 2, that extended the inservice inspection interval for certain pressure retaining welds in the reactor vessel from 10 to 20 years (ADAMS Accession Nos. ML091260163 for CNP, Unit 2 and ML18284A310 for CNP, Unit No. 1). The granting of these extensions has resulted in the previous interval's inspections to be required at the same time as the current interval's inspections. The licensee presented a graphical representation of these requirements (ADAMS Accession No. ML19099A327). The licensee stated that the ASME Code contains a requirement that a single inspection cannot be used to fulfill multiple ASME Code required inspections. The licensee stated that they planned to submit a request for relief from this requirement so that the next ASME Code-required inspection could meet the requirements for the previously extended interval and the current interval.

The NRC staff questioned the licensee on if the relief request would be for both CNP, Unit Nos.

1 and 2. The licensee stated that it was considering applying for both CNP units. The NRC staff stated that the simplest approach would be to submit for the unit that was approaching the requirements (CNP, Unit No. 2). The licensee stated it would consider the staff's observation.

No members of the public participated in the meeting.

Please direct any inquiries to me at 301-415-3733, or Robert.Kuntz@nrc.gov.

Sincerely, Rooert F. Kuntz, enior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315 and 50-316

Enclosure:

List of Attendees cc: Listserv

LIST OF ATIENDEES

- APRIL 2, 2019, PUBLIC MEETING WITH l&M DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 PLANNED RELIEF REQUEST REGARDING REACTOR PRESSURE VESSEL WELDS Name Organization Robert Kuntz NRC David Alley NRC Simon Shenq NRC Helen Levendosky Indiana Michigan Power Company (l&M)

Joe Tanke l&M Glenn Chatterton l&M Dave Aubrey l&M Enclosure

ML19099A326 OFFICE DORL/LPL3/PM DORL/LPL3/LA DORL/LPL3/BC DORL/LPL3/PM NAME RKuntz SRohrer DWrona RKuntz DATE 4/11/19 4/10/19 4/12/19 4/16/19