ML060310635

01/30/2006 - Summary of Telephone Conference Call Held on 01/09/2006, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Information Pertaining to the Monticello Nuclear Generating Plant License R

ML060310635
Person / Time
Site:	Monticello
Issue date:	01/30/2006
From:	Daniel Merzke NRC/NRR/ADRO/DLR
To:	Nuclear Management Co
Merzke, D., NRR/ADRO/DLR/RLRB, 415-3777
References
Download: ML060310635 (7)

Text

January 30, 2006 LICENSEE: Nuclear Management Company, LLC FACILITY: Monticello Nuclear Generating Plant

SUMMARY

OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 9, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NUCLEAR MANAGEMENT COMPANY, LLC, CONCERNING INFORMATION PERTAINING TO THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on January 9, 2006, to discuss and clarify the applicants responses to requests for additional information (RAIs) concerning the Monticello Nuclear Generating Plant license renewal application. The conference call was useful in clarifying the staffs questions. provides a listing of the conference call participants. Enclosure 2 contains a listing of the issues discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/

Daniel J. Merzke, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-263

Enclosures:

As stated cc w/encls: See next page

ML060310635 DOCUMENT NAME: E:\Filenet\ML060310635.wpd OFFICE PM:RLRB LA:RLRA BC:RLRB NAME DMerzke YEdmonds JZimmerman DATE 01/30/06 01/23/06 01/30/06

Monticello Nuclear Generating Plant cc:

Jonathan Rogoff, Esquire Commissioner Vice President, Counsel & Secretary Minnesota Department of Commerce Nuclear Management Company, LLC 85 7th Place East, Suite 500 700 First Street St. Paul, MN 55101-2198 Hudson, WI 54016 Manager - Environmental Protection U.S. Nuclear Regulatory Commission Division Resident Inspectors Office Minnesota Attorney Generals Office 2807 W. County Road 75 445 Minnesota St., Suite 900 Monticello, MN 55362 St. Paul, MN 55101-2127 Manager, Regulatory Affairs John Paul Cowan Monticello Nuclear Generating Plant Executive Vice President & Chief Nuclear Nuclear Management Company, LLC Officer 2807 West County Road 75 Nuclear Management Company, LLC Monticello, MN 55362-9637 700 First Street Hudson, WI 54016 Robert Nelson, President Minnesota Environmental Control Nuclear Asset Manager Citizens Association (MECCA) Xcel Energy, Inc.

1051 South McKnight Road 414 Nicollet Mall, R.S. 8 St. Paul, MN 55119 Minneapolis, MN 55401 Commissioner Mr. James Ross Minnesota Pollution Control Agency Nuclear Energy Institute 520 Lafayette Road 1776 I Street, NW, Suite 400 St. Paul, MN 55155-4194 Washington, DC 20006-3708 Regional Administrator, Region III Joseph Pairitz U.S. Nuclear Regulatory Commission License Renewal Project Manager 801 Warrenville Road Monticello Nuclear Generating Plant Lisle, IL 60532-4351 Nuclear Management Company, LLC 2807 West County Road 75 Commissioner Monticello, MN 55362-9637 Minnesota Department of Health 717 Delaware Street, S.E. Mr. Douglas F. Johnson Minneapolis, MN 55440 Director, Plant Life Cycle Issues Nuclear Management Company, LLC Douglas M. Gruber, Auditor/Treasurer 700 First Street Wright County Government Center Hudson, WI 54016 10 NW Second Street Buffalo, MN 55313

Monticello Nuclear Generating Plant cc:

David R. Lewis Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037-1122 Mr. George Crocker North American Water Office P.O. Box 174 Lake Elmo, MN 55042 Mr. John T. Conway Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637

Letter to Licensee Nuclear Management Co. from Daniel J. Merzke dated, January 30, 2006_______________ __________________________________________

SUMMARY

OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 9, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NUCLEAR MANAGEMENT COMPANY, LLC, CONCERNING INFORMATION PERTAINING TO THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION HARD COPY DMerzke E-MAIL JFair RWeisman AMurphy RPettis GGalletti CLi GBagchi SSmith (srs3)

SDuraiswamy YL (Renee) Li RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrl RidsOgcMailCenter RidsNrrDipm DLR Staff

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LRaghavan PTam AStone, RIII BBurgess, RIII PLougheed, RIII SRay, RIII AHodgdon MWoods OPA

LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION January 9, 2006 Participants Affiliations Daniel Merzke U.S. Nuclear Regulatory Commission (NRC)

Barry Elliot NRC Mark Hartzman NRC Joe Pairitz Nuclear Management Company, LLC (NMC)

Mike Aleksey NMC Dave Musolf NMC Enclosure 1

MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION January 9, 2006 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on January 9, 2006, to discuss and clarify the applicants responses to requests for additional information (RAIs) concerning the Monticello Nuclear Generating Plant license renewal application. The following issues were discussed during the telephone conference call:

1. In a letter dated December 16, 2005, the applicant provided a supplemental response to RAI 4.8-2. The applicant provided a proprietary report concerning the investigation of the sliding behavior of a number of alloys under dry and water-lubricated conditions. NRC staff review identified some apparent discrepancies with the data presented in the report. The staff reiterated its position that for the analysis of the stress relaxation of rim hold down bolts time-limited aging analysis (TLAA), a friction coefficient of 0.5 was unacceptably high. The NRC staff referenced Boiling Water Reactor Vessel and Internals Project-25 (BWRVIP-25) which did not include friction in an analysis acceptable to the NRC staff, and Code Case N-730, which used a friction coefficient of 0.2 in an analysis of similar materials in a different geometry. The staff requested the applicant to provide additional information on the GE testing described in the proprietary report, or provide another analysis for the TLAA.

Discussion: The applicant indicated that the question is clear. The applicant will perform an analysis of the stress relaxation in accordance with the process described in BWRVIP-25, and provide the analysis to the staff for its review.

2. In its initial response to RAI 4.2-3, dated October 28, 2005, the applicant provided a table projecting Upper Shelf Energy (USE) data through the period of extended operation. The staff noted the table was missing the data for the nozzles. The applicant referenced BWRVIP-74, which provided USE data for plates. However, the staff noted that nozzles are forged components, not plates, and requested the applicant to provide a technical basis for their position that the plates are the limiting components.

Discussion: The applicant indicated that the question is clear. The applicant will provide the USE information for the nozzles.

Enclosure 2