ML090080801

2008/12/02 PINGP Lr -

ML090080801
Person / Time
Site:	Prairie Island
Issue date:	12/02/2008
From:	Office of Nuclear Reactor Regulation
To:
References
Download: ML090080801 (8)

Text

PrairieIslandNPEm Resource From: Richard Plasse Sent: Tuesday, December 02, 2008 11:08 AM To: Eckholt, Gene F.

Attachments: PINGP RAI final LETTER.doc word version 1

Hearing Identifier: Prairie_Island_NonPublic Email Number: 249 Mail Envelope Properties (Richard.Plasse@nrc.gov20081202110800)

Subject:

Sent Date: 12/2/2008 11:08:00 AM Received Date: 12/2/2008 11:08:00 AM From: Richard Plasse Created By: Richard.Plasse@nrc.gov Recipients:

"Eckholt, Gene F." <Gene.Eckholt@xenuclear.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 14 12/2/2008 11:08:00 AM PINGP RAI final LETTER.doc 108026 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

December 1, 2008 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant, Units 1 and 2 Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 & 2, LICENSE RENEWAL APPLICATION (TAC NOS. MD8513 AND MD8514)

Dear Mr. Wadley:

By letter dated April 11, 2008, Nuclear Management Company, LLC, now known as Northern States Power Company, Minnesota, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) to renew the operating license for Prairie Island Nuclear Generating Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Gene Eckholt, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at Richard.Plasse@nrc.gov.

Sincerely,

/RA/

Richard Plasse, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

As stated cc w/encl: See next page

December 1, 2008 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant, Units 1 and 2 Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 & 2, LICENSE RENEWAL APPLICATION (TAC NOS. MD8513 AND MD8514)

Dear Mr. Wadley:

By letter dated April 11, 2008, Nuclear Management Company, LLC, now known as Northern States Power Company, Minnesota, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) to renew the operating license for Prairie Island Nuclear Generating Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Gene Eckholt, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at Richard.Plasse@nrc.gov.

Sincerely,

/RA/

Richard Plasse, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION: See next page ADAMS Accession Number: ML083250716 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR NAME IKing RAPlasse DWrona DATE 12/ 1/08 12/1/08 12/1/08 OFFICIAL RECORD COPY

Letter to M. Wadley from R. Plasse, dated December 1, 2008 DISTRIBUTION:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 & 2, LICENSE RENEWAL APPLICATION (TAC NOS. MD8513 AND MD8514)

HARD COPY:

DLR RF E-MAIL:

PUBLIC B. Holian / S. Lee (RidsNrrDlr)

T. Combs, OCA T. Madden, OCA R. Shane, OCA B. Keeling, OCA D. Wrona (RidsNrrDlrRebb)

R. Rikhoff (RidsNrrDlrReba)

R. Plasse T. Wengert N. Goodman R. Skokowski K. Stoedter P. Zurawski OPA (RidsOpaMail)

I. Couret, OPA V. Mitlyng B. Mizuno, OGC OGC (RidsOGCMailRoom)

DLR/REBB

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

Peter M. Glass Dennis L. Koehl Assistant General Counsel Chief Nuclear Officer Xcel Energy Services, Inc. Northern States Power Company, 414 Nicollet Mall (MP4) Minnesota Minneapolis, MN 55401 414 Nicollet Mall (MP4)

Minneapolis, MN 55401 Manager, Regulatory Affairs Prairie Island Nuclear Generating Plant Joel P. Sorenson Northern States Power Company, Director, Site Operations Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Northern States Power Company, Welch, MN 55089 Minnesota 1717 Wakonade Drive East Manager - Environmental Protection Welch, MN 55089 Division Minnesota Attorney General=s Office 445 Minnesota St., Suite 900 St. Paul, MN 55101-2127 U.S. Nuclear Regulatory Commission Resident Inspector's Office 1719 Wakonade Drive East Welch, MN 55089-9642 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 Tribal Council Prairie Island Indian Community ATTN: Environmental Department 5636 Sturgeon Lake Road Welch, MN 55089 Charles R. Bomberger Vice President Nuclear Projects 414 Nicollet Mall, (MP4)

Minneapolis, MN 55401

REQUEST FOR ADDITIONAL INFORMATION SECTION 2.4: SCOPING AND SCREENING RESULTS: CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORTS PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NOS. MD8513 & MD8514)

RAI 2.4.1-1 Due to lack of clarity in the license renewal application (LRA) Tables 2.4.1-1 and 3.5.2-1, please confirm/clarify if the Spent Fuel Pool (SFP) Divider Gates, the SFP leak-chase channels, and the fuel transfer canal upending frame are structural components in the scope of license renewal and subject to an aging management review (AMR). If yes, include their scoping, screening and AMR results, as appropriate, or clarify the location in the LRA where these components are included. If not, please provide justification for exclusion.

RAI 2.4.3-1 In Updated Final Safety Analysis Report (UFSAR) Section 12.2.6, the applicant states that in order to assure the stability and prevent toppling and over-travelling of the containment polar crane or its components, the features incorporated in its design include: (i) up-kick lugs fastened to each truck; (ii) overturning locks fastened to each truck; and (iii) positive wheel stops. Also, in UFSAR Section 12.2.9, the applicant indicates that the spent fuel pool bridge crane, auxiliary building crane and the turbine building crane are protected against tipping, derailments and uncontrolled movements by features that include: (i) crane bridge and trolley being equipped with fixed, fitted rail yokes; and (ii) positive wheel stops and bumpers. From LRA Section 2.4.3, Table 2.4.3-1 and Table 3.5.2-3, it is not clear if the above noted structural components and fasteners of the cranes are included in-scope of license renewal and subject to an AMR. Please confirm if these crane components have been screened in as items requiring an AMR. If yes, indicate where these items have been included in the LRA. If not, provide the technical bases for their exclusion.

RAI 2.4.7-1 In LRA Section 2.4.7, the system function listing under code RCV-04, Reactor Containment Vessels and their internal structures provide shielding against high energy line breaks, indicates scoping under 10 CFR 54.4(a)(2), which corresponds to all non-safety related systems, structures and components, whose failure could prevent satisfactory accomplishment of any of the functions identified in 10 CFR 54.4(a)(1). The comment under this item on LRA page 2.4-38 states that: Reactor Containment Vessels and their internal structures are designed to withstand the effects of high energy line breaks without loss of function. Reinforced concrete walls and steel structures inside each Reactor Containment Vessel shield safety related equipment from the effects of a HELB. The NRC staff finds that the above stated structures and structural components are generally safety-related and are in scope in accordance with 10 CFR 54.4(a)(1). Please address the inconsistency.

ENCLOSURE

RAI 2.4.7-2 Because of lack of clarity in LRA Tables 2.4.2-1, 2.4.7-1, 3.5.2-2, 3.5.2-7 and the corresponding LRA sections, please indicate where in the LRA are the scoping, screening and AMR results of structural supports (vertical and lateral, as appropriate) for steam generators, reactor coolant pumps and the reactor vessel included. If these structural components were inadvertently not included, please provide their scoping, screening and AMR results, otherwise justify the exclusion.

RAI 2.4.8-1 Please confirm if there are any ductbanks and manholes in the yard that are safety-related or important-to-safety or required for regulated events that may be within the scope of license renewal and subject to an AMR. If there are, please provide their scoping, screening and AMR results.

RAI 2.4.11-1 Section 1.3.2 of the UFSAR states that the plant screenhouse houses the cooling water pumps, fire pumps, circulating water pumps, trash racks and traveling screens. Due to lack of clarity in LRA Tables 2.4.11-1 and 3.5.2-11, please confirm the inclusion or exclusion of the trash racks and traveling screens as structural components within the scope of license renewal and subject to an AMR. If they were not included as an oversight, please provide a description of their scoping and AMR. If they are included elsewhere in the LRA, please indicate the location. If they are excluded from the scope of license renewal and AMR, please provide the basis for their exclusion.