L-2010-162, Extended Power Uprate License Amendment Request - Response to NRC Acceptance Review Questions

Extended Power Uprate License Amendment Request - Response to NRC Acceptance Review Questions

ML102160343
Person / Time
Site:	Saint Lucie
Issue date:	07/30/2010
From:	Richard Anderson Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2010-162
Download: ML102160343 (2)

Text

This letter forwards proprietary information in accordance with 10 CFR 2.390.

he balance of this letter may be L -OBJPil*L WtIhfl 34957 identified drawings in Appendix A to Attachment 4.

F=PL July 30, 2010 L-2010-162 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Plant Unit No. 1 Docket No. 50-335 Renewed License No. DPR-67 Extended Power Uprate License Amendment Request - Response to NRC Acceptance Review Questions On April 16, 2010, Florida Power and Light Company (FPL) submitted the St. Lucie Unit 1 Extended Power Uprate (EPU) License Amendment Request (LAR) via FPL letter L-2010-078 (ML101160182) for a proposed license amendment that would increase the licensed core power level from 2700 megawatts thermal (MWt) to 3020 MWt. The purpose of this letter is to respond to the supplemental information requested by the United States Nuclear Regulatory Commission's (NRC) Electrical Systems and Reactor Systems Branches by letter (ML102030096) dated July 23, 2010 as part of its acceptance review of the LAR.

The FPL response to Electrical Systems Branch (ESB) Questions 1 and 3 are provided in Attachments 1 and 2 respectively. The FPL responses to ESB Question 2 and Reactor Systems Branch Questions (RSB) 1 through 4 (formerly Questions 2 through 5) were provided to the NRC by FPL Letter L-2010-144 dated July 23, 2010. FPL is providing a revised response to RSB Question 2 (formerly RSB Question 3) in Attachment 3. The FPL responses to RSB Questions Att. 8-1 through Att. 8-9 are provided in Attachment 4.

A proprietary information affidavit is provided in Attachment 5 on behalf of Areva NP (Areva). The purpose of this affidavit is to request NRC to withhold the proprietary information contained in Appendix A to Attachment 4 of this letter pertaining to Areva drawings EMF-308, 291 R-4, "Fuel Bundle Assembly," EMF-307, 276 R-2, "Fuel Rod Assembly Depleted," and EMF-308, 681 R-0, "Hafnium Assembly" from public disclosure. The affidavit sets forth the basis for which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR § 2.390.

Correspondence with respect to the copyright or proprietary aspects of the subject Areva drawings described above and provided in Attachment 4 or the supporting Areva affidavit should be addressed to Gayle F. Elliott, Manager Product Licensing, Areva NP Inc., P.O. Box 10935, Lynchburg, VA 24506-0935.

Aoo an FPL Group company IURR,

This letter forwards proprietary information in accordance with 10 CFR 2.390.

The balance of this letter may be considered non-proprietary upon removal of the identified drawings in AppendixAto Attachment 4.

This letter contains six new Regulatory Commitments provided below and no revisions to existing Regulatory Commitments:

. FPL commits to perform a new spent fuel pool criticality analysis to replace the existing analysis of record once the draft interim staff guidance (ISG) is formally issued. This revised analysis will be submitted as a separate license amendment request (LAR) for NRC review and approval. FPL will submit this LAR.within one year of issuance of the final ISG.

° Implement administrative controls to impose a .7% burnup penalty on the average burnup of any 2 X 2 array configuration allowed by current Technical Specifications. This burnup margin will offset the two issues identified by NRC and provides additional margin.

o Implement administrative controls to maintain a SFP boron concentration limit of

> 2000 ppm which is above the current Technical Specification limit of

> 1720 ppm.

Verify the normal position of valve V1 5322 (primary makeup water hose connection to the cask storage isolation) is locked closed as part of normal operator rounds in the fuel handling building.

Verify, as part of normal operator rounds in the fuel handling building, that there are not other sources or indications of dilution to the SFP.

• Verify that the SFP boron concentration is > 2000 ppm twice every seven days.

The no significant hazards analysis submitted with FPL letter L-2010-0,78 remains bounding.

Should you have any questions regarding the information provided in this letter, please contact Mr. James Connolly, St. Lucie Extended Power Uprate Licensing Manager, at 772-429-7852.

I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.

Executed on 3. 0 - TcJ -O'go Very truly yours, Richard Anderson Site Vice President cc: Administrator, Region II, USNRC Project Manager, St. Lucie Nuclear Plant Unit No. 1, USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, USNRC Mr. William Passetti, Florida Department of Health