ML12194A287

Correction to Amendment No. 213 Regarding Extended Power Uprate

ML12194A287
Person / Time
Site:	Saint Lucie
Issue date:	07/12/2012
From:	Orf T Plant Licensing Branch II
To:	Nazar M Florida Power & Light Co
Orf, T J
Shared Package
ML12194A299	List: ML12194A287
References
TAC ME5091
Download: ML12194A287 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 12, 2012 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O, Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE PLANT, UNIT 1 - CORRECTION TO AMENDMENT NO. 213 REGARDING EXTENDED POWER UPRATE (TAC NO. ME5091)

Dear Mr. Nazar:

On July 9,2012, the Nuclear Regulatory Commission issued Amendment No. 213 to Renewed Facility Operating License No. DPR-67 for the St. Lucie Plant, Unit No.1. This amendment was in response to your application dated November 22, 2010, as supplemented by letters dated February 25,2012, March 3, March 14, March 22, April 1, April 21 , May 17, May 18, May 19 (three letters), May 24, May 27, May 31 (two letters), June 16, June 22, July 5, July 8, July 22, August 5, August 8, August 12, August 18, August 25 (two letters), August 31, September 2 (two letters), September 8 (two letters), September 22, September 23, September 27, September 29, September 30, October 10, October 14, October 20, October 21, October 27, October 31 (six letters), November 1, November 23, November 29, December 1, December 2, December 14, December 27,2011, January 2,2012, January 10, January 14, January 25, February 11, February 21, February 29 (three letters), March 6 (two letters), March 8, March 15, March 16, March 22, March 26, 2012.

The amendment increased the licensed core power level for St. Lucie Unit 1 from 2070 megawatts thermal (MWt) to 3020 MWt. This represents a net increase in the core thermal power of approximately 11.85 percent, including a 10-percent power uprate and a 1.7-percent measurement uncertainty recapture, over the then current licensed thermal power level and is defined as an extended power uprate.

After issuance, it became apparent that some pages were incorrect. License page 3 had not been updated with new maximum power level and a coefficient listed in Table 5.6-1 on page 5-6g had not been replaced with a corrected version.

M. Nazar -2 The corrected pages are enclosed. We regret any inconvenience this may have caused. If you have any questions regarding this matter, please call me at (301) 415-2788.

Sincerely, Tracy J. Orf, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335

Enclosure:

Corrected Pages cc: Distribution via Listserv

-3 applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

A. Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 213 are hereby incorporated in the renewed license.

FPL shall operate the facility in accordance with the Technical Specifications.

Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.

C. Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation. FPL shall complete these activities no later than March 1,2016, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on March 28, 2003, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed license. Until that update is complete, FPL may make changes to the programs described in such supplement without prior Commission approval, provided that FPL evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

D. Sustained Core Uncovery Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery.

Renewed License No. DPR-67 Amendment No. 213

TABLE 5.6-1 Minimum Burnup as a Function of Enrichment Cooling Time Coefficients Fuel Type (Years) A B C 0 -36.6860 22.4942 -1.4413 2 0 -36.1742 16.6000 -0.8958 3 0 -34.7091 23.1361 -1.6204 0 -24.5145 21.3404 -1.2444 2.5 -26.8311 22.5246 -1.5029 5 -24.7233 20.9763 -1.3246 4

10 -23.6285 19.9541 -1.2505 15 -23.5458 20 -22.4382 0 -8.1856 2.5 -11.8506 5 -16.5196 5

10 -13.6831 16.3475 -0.5844 15 -12.5819 15.6175 -0.5656 20 -12.6469 15.4575 -0.5906 NOTES:

1. To qualify in a "fuel type," the burnup of a fuel assembly must exceed the minimum bumup "BU" calculated by inserting the "coefficients" for the associated "fuel type" and "cooling time" into the polynomial function:

BU = A + B"E + C"E 2 , where:

BU = Minimum Burnup (GWO/MTU)

E = Initial Maximum Planar Average Enrichment (weight percent uranium-235)

A, e, C = Coefficients

2. Interpolation between values of cooling time is not permitted.

ST. LUCIE - UNIT 1 5.69 Amendment No. 213

M. Nazar -2 The corrected pages are enclosed. We regret any inconvenience this may have caused. If you have any questions regarding this matter, please call me at (301) 415-2788.

Sincerely, IRA!

Tracy J. Orf, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335

Enclosure:

Corrected Pages cc: Distribution via Listserv DISTRIBUTION:

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