Letter Sequence Meeting |
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EPID:L-2017-LRM-0066, Slides - January 11, 2018, Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit 1 Application of Leak Before Break on U1 RCS Auxiliary Lines (Open) |
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MONTHYEARML18018B1392018-01-11011 January 2018
Slides - January 11, 2018, Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit 1 Application of Leak Before Break on U1 RCS Auxiliary Lines
Project stage: Request
ML18018B1382018-01-22022 January 2018
Summary of Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit No. 1
Project stage: Meeting
2018-01-11
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0.C. 20555-0001 January 22, 2018 LICENSEE: Indiana Michigan Power Company, LLC FACILITY: Donald C. Cook Nuclear Plant, Unit No. 1
SUBJECT:
SUMMARY
OF JANUARY 11, 2018, MEETING WITH INDIANA MICHIGAN POWER COMPANY REGARDING DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 (EPID L-2017-LRM-0066)
On January 11, 2018, a Category I public meeting was held between the U.S. Nuclear Regulatory Commission (NRG) 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 license amendment request (LAR) for Donald C. Cook Nuclear Plant (CNP), Unit No. 1. The licensee intends to submit a request to implement the leak-before-break (LBB) methodology for the Unit No. 1 reactor coolant system (RCS) auxiliary lines. The meeting notice and agenda, dated December 19, 2017, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML17353A702. A list of attendees is provided as Enclosure 1. The meeting handouts can be found at ADAMS Accession No. ML18018B139.
The licensee presented a historical overview of LBB, and the site-specific LBB methodology for RCS main loop piping for CNP, Unit No. 1. The licensee specified the RCS auxiliary lines the LAR would consider. This includes the 8" and 14" residual heat removal lines, the 1O" accumulator lines, and the 6", 8", and 1O" safety injection lines. The licensee also discussed the various reasons for submitting this proposed LAR. The NRG staff notes the following as a result of the licensee's presentation:
- The LAR should describe how the proposed piping meets all the requirements of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," Section 3.6.3, Revision 1, "Leak-Before-Break Evaluation Procedures" (ADAMS Accession No. ML063600396}.
- The LAR should also describe there is not an active degradation mechanism present.
- The licensee does not anticipate the proposed LAR changing any previous updated final safety analysis chapter 15 accident analysis.
- The licensee does not anticipate the proposed LAR changing any leakage detection system capabilities.
The licensee indicated that it would submit the LAR in February 2018, and request NRG approval by December 2018.
The public was invited to listen to the meeting and was given an opportunity to communicate with the NRC after the business portion, but before the meeting was adjourned. Members of the public were present and provided comments to the NRC staff.
Please direct any inquiries to me at 301-415-1530, or Jennivine.Rankin@nrc.gov.
Sincerely,
. ~
~ a n k i n , Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES JANUARY 11, 2018, PUBLIC MEETING WITH l&M DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 PLANNED LICENSE AMENDMENT REQUEST REGARDING INCORPORATION OF LEAK-BEFORE-BREAK METHODOLOGY Name Organization Jennivine Rankin NRC - CNP Project Manaqer John Tsao NRC - Senior Materials Engineer, Division of Materials and License Renewal, Piping and Head Penetrations Branch Gerard Purciarello NRC - Senior Reactor Systems Engineer, Division of Safety Systems, Balance-of-Plant Branch Robert Beaton NRC - Reactor Systems Engineer, Division of Safety Systems, Reactor Systems Branch David Alley NRC - Branch Chief, Division of Materials and License Renewal, Piping and Head Penetrations Branch Jeffrey Poehler NRC - Senior Materials Engineer, Division of Materials and License Renewal, Vessels and Internals Branch Mel Holmberq NRC - Senior Reactor Inspector, Region Ill Helen Levendosky CNP Req. Affairs Supervisor Joe Tanko CNP ReQ. Affairs - LicensinQ Coordinator Amanda Britton CNP Design Engineering - Structural Supervisor David Dolby CNP - Project Manager Pete Brusamonti Westinqhouse Project ManaQer Eric Johnson Westinghouse Engineer - Structural Design and Analysis Marv Lewis Public John Barkhamer PSEG Enclosure
ML180186138 OFFICE D0RL/LPL3/PM D0RL/LPL3/LA D0RL/LPL3/BC D0RL/LPL3/PM NAME JRankin SRohrer DWrona JRankin DATE 01/22/2018 01/22/2018 01/22/2018 01/22/2018
