L-2012-156, Supplemental Information for Extended Power Uprate License Amendment Request (LAR) Section 2.6.1 Primary Containment Functional Design

Supplemental Information for Extended Power Uprate License Amendment Request (LAR) Section 2.6.1 Primary Containment Functional Design

ML12102A012
Person / Time
Site:	Saint Lucie
Issue date:	04/08/2012
From:	Richard Anderson Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2012-156
Download: ML12102A012 (3)

Text

0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 FPL April 8, 2012 L-2012-156 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Plant Unit 1 Docket No. 50-335 Renewed Facility Operating License No. DPR-67 Supplemental Information for Extended Power Uprate License Amendment Request (LAR) Section 2.6.1 Primary Containment Functional Desigqn

References:

(1) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2010-259),

"License Amendment Request for Extended Power Uprate," November 22, 2010, Accession No. ML103560419.

By letter L-2010-259 dated November 22, 2010 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. DPR-67 and revise the St. Lucie Unit 1 Technical Specifications (TS). The proposed amendment will increase the unit's licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt and revise the Renewed Facility Operating License and TS to support operation at this increased core thermal power level. This represents an approximate increase of 11.85% and is therefore considered an extended power uprate (EPU).

This submittal provides supplemental information to update St. Lucie Unit 1 EPU LAR Attachment 5, Section 2.6.1 "Primary Containment Functional Design." FPL has determined that the results and conclusions reached in EPU LAR Attachment 5, Section 2.6.1 are unchanged.

This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2010-259 [Reference 1].

This submittal contains no new commitments.

In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the designated State of Florida official.

an FPL Group company Aooi

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L-2012-156 Page 2 of 2 Should you have any questions regarding this submittal, please contact Mr. Christopher Wasik, St. Lucie Extended Power Uprate LAR Project Manager, at 772-467-7138.

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

Executed on .0 - AO I Very truly yours, Richard L. Andero~n Site Vice President St. Lucie Plant Attachment (1) cc: Mr. William Passetti, Florida Department of Health

L-2012-156 Attachment 1 Page 1 of 1 Supplemental Information to EPU LAR Attachment 5, Section 2.6.1 Primary Containment Functional Design Recently, FPL identified the need to revise three input parameters used in the EPU loss of coolant accident (LOCA) containment pressure and temperature analysis for St. Lucie Unit 1. These input revisions involve the component cooling water (CCW) heat exchanger heat transfer coefficient to account for an appropriate limiting fouling factor, the minimum Intake Cooling Water (ICW) flow to the CCW heat exchanger, and the minimum CCW flow rate to the shutdown cooling heat exchanger to ensure additional conservatism is accounted for in the amount of heat remaining in containment for the purpose of this analysis.

The LOCA containment pressure and temperature analysis is described in the St. Lucie Unit 1 EPU LAR Attachment 5, Section 2.6.1, Primary Containment Functional Design, and was updated in FPL letter L-2011-516 dated December 1, 2011 (ML11340A029). In addition to the input changes described above, an offsetting change to the long-term decay heat input was also included.

The current, pre-EPU, licensing basis LOCA containment pressure and temperature analysis uses the long-term decay heat based on ANS 1971, increased by 20% as identified in UFSAR Section 6.2.1.3.2. The fission product decay heat model used for the EPU long-term LOCA containment response was revised to ANS 5.1, Decay Heat Power for Light Water Reactors, dated October 1979, plus 2 sigma and long term actinides. Use of this long-term decay heat input is consistent with the guidance described in the Standard Review Plan (SRP), NUREG-0800, Section 6.2.1. Accordingly, Section 2.6.1.2.1.1 of Attachment 5 to the St. Lucie Unit 1 EPU LAR is revised to include the following additional input and assumption difference between the current licensing basis analysis and the EPU LOCA containment response analysis:

The long-term decay heat input is based on ANS 5.1, Decay Heat Power for Light Water Reactors, dated October 1979, plus 2 sigma and long term actinides.

As a result of the changes described herein, the results of the updated LOCA containment pressure and temperature analysis are bounded by the results presented in FPL letter L-2011-516 dated December 1, 2011 (ML11340A029). The acceptance criteria for containment design integrity, including Equipment Qualification, in both the short and long-term post-LOCA transient response are met for St. Lucie Unit 1 under EPU conditions.

It is noted that the decay heat input used in the current, pre-EPU, licensing basis analysis described in UFSAR Section 6.2.1.3.2, and the EPU analysis for the short-term (blowdown, reflood and post-reflood phases) LOCA mass and energy (M&E) releases to containment continue to use the decay heat input based on ANS 1971, increased by 20%.