ML060400438

Notice of Withdrawal of an Amendment Request

ML060400438
Person / Time
Site:	Prairie Island
Issue date:	02/16/2006
From:	Mahesh Chawla Plant Licensing Branch III-2
To:	Thomas J. Palmisano Nuclear Management Co
chawla M, NRR/DORL, 415-8371
References
TAC MC6281, TAC MC6282
Download: ML060400438 (5)

Text

February 16, 2006 Mr. Thomas J. Palmisano Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

WITHDRAWAL OF AN AMENDMENT REQUEST RE: (TAC NOS. MC6281 AND MC6282)

Dear Mr. Palmisano:

By letter to the Nuclear Regulatory Commission (NRC, Commission) dated February 28, 2005, you applied for an amendment to the Prairie Island Nuclear Generating Plant, Units 1 and 2, Facility Operating License Nos. DPR-42 and DPR-60. The proposed change would allow the use of the small-break loss-of-coolant accident (SBLOCA) methodology described in Westinghouse WCAP 10054-P-A Addendum 2 Revision 1, Addendum to the Westinghouse small-break emergency core cooling system Evaluation Model Using the NOTRUMP Code:

Safety Injection into the Broken Loop and COSI Condensation Model dated July 1997.

This revised methodology determines the core response following a SBLOCA event and would have been used to assure compliance with the post loss-of-coolant accident acceptance criteria specified in 10 CFR Part 50.46. Subsequently, by letter dated February 2, 2006, you withdrew the amendment request.

The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication.

Sincerely,

/RA/

Mahesh L. Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Notice of Withdrawal cc w/encl: See next page

February 16, 2006 Mr. Thomas J. Palmisano Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

WITHDRAWAL OF AN AMENDMENT REQUEST RE: (TAC NOS. MC6281 AND MC6282)

Dear Mr. Palmisano:

By letter to the Nuclear Regulatory Commission (NRC, Commission) dated February 28, 2005, you applied for an amendment to the Prairie Island Nuclear Generating Plant, Units 1 and 2, Facility Operating License Nos. DPR-42 and DPR-60. The proposed change would allow the use of the small-break loss-of-coolant accident (SBLOCA) methodology described in Westinghouse WCAP 10054-P-A Addendum 2 Revision 1, Addendum to the Westinghouse small-break emergency core cooling system Evaluation Model Using the NOTRUMP Code:

Safety Injection into the Broken Loop and COSI Condensation Model dated July 1997.

This revised methodology determines the core response following a SBLOCA event and would have been used to assure compliance with the post loss-of-coolant accident acceptance criteria specified in 10 CFR Part 50.46. Subsequently, by letter dated February 2, 2006, you withdrew the amendment request.

The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication.

Sincerely,

/RA/

Mahesh Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Notice of Withdrawal cc w/encl: See next page DISTRIBUTION PUBLIC LPLIII-1 R/F RidsNrrPMMChawla RidsNrrLATHarris RidsNrrDorlLple RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn3MailCenter RidsNrrDssSpwb FOrr BSingal, DORL DPR ADAMS Accession Number: ML060400438 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA SPWB:BC NRR/LPL3-1/BC (A)

NAME MChawla:RSA THarris JNakoski TKobetz (DClarke for)

DATE 2/16/06 2/16/06 2/16/06 2/16/06 OFFICIAL RECORD COPY

Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:

Jonathan Rogoff, Esquire Tribal Council Vice President, Counsel & Secretary Prairie Island Indian Community Nuclear Management Company, LLC ATTN: Environmental Department 700 First Street 5636 Sturgeon Lake Road Hudson, WI 54016 Welch, MN 55089 Manager, Regulatory Affairs Nuclear Asset Manager Prairie Island Nuclear Generating Plant Xcel Energy, Inc.

Nuclear Management Company, LLC 414 Nicollet Mall, R.S. 8 1717 Wakonade Drive East Minneapolis, MN 55401 Welch, MN 55089 Michael B. Sellman Manager - Environmental Protection Division President and Chief Executive Officer Minnesota Attorney Generals Office Nuclear Management Company, LLC 445 Minnesota St., Suite 900 700 First Street St. Paul, MN 55101-2127 Hudson, MI 54016 U.S. Nuclear Regulatory Commission Craig G. Anderson Resident Inspector's Office Senior Vice President, Group Operations 1719 Wakonade Drive East Nuclear Management Company, LLC Welch, MN 55089-9642 700 First Street Hudson, WI 54016 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198 November 2005

7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION NUCLEAR MANAGEMENT COMPANY, LLC (NMC)

DOCKET NOS. 50-282 and 50-306 NOTICE OF WITHDRAWAL OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission (the Commission) has granted the request of Nuclear Management Company, LLC (NMC) (the licensee) to withdraw its February 28, 2005, application for proposed amendment to Facility Operating License No. DPR-42 and DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, located in Goodhue County, Minnesota.

The proposed change would allow the use of the small-break loss-of-coolant accident (SBLOCA) methodology described in Westinghouse WCAP 10054-P-A Addendum 2 Revision 1, Addendum to the Westinghouse small-break emergency core cooling system Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model dated July 1997. This revised methodology determines the core response following a SBLOCA event and would have been used to assure compliance with the post loss-of-coolant accident acceptance criteria specified in 10 CFR Part 50.46.

The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the FEDERAL REGISTER on April 26, 2005 (79 FR 21459).

However, by letter dated February 2, 2006, the licensee withdrew the proposed change.

For further details with respect to this action, see the application for amendment dated February 28, 2005, and the licensee's letter dated February 2, 2006, which withdrew the application for license amendment. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, Public File Area 01

F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management Systems (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams/html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301-415-4737 or by email to pdr@nrc.gov.

Dated at Rockville, Maryland, this 16th day of February.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Mahesh Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation