L-2010-067, St. Lucie, Units 1 and 2 - Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report

St. Lucie, Units 1 and 2 - Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report

ML101030176
Person / Time
Site:	Saint Lucie
Issue date:	03/30/2010
From:	Katzman E S Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2010-067
Download: ML101030176 (5)

Text

0 FIPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 March 30, 2010 L-2010-067 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report Pursuant to 10 CFR 50.46(a)(3)(ii), the nature of any change to or error discovered in the evaluation models for emergency core cooling systems (ECCS), or in the application of such models, that affect the fuel cladding temperature calculations for St. Lucie Units 1 and 2 is reported in the attachment to this letter. The estimated effect from any such change or error on the limiting ECCS analysis for each unit is also addressed.

The data interval for the report is from January 1, 2009 through December 31, 2009.Please contact us should you have any questions regarding this submittal.

Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment

-IýObg'an FPL Group company L-2010-067 Attachment Page 1 of4 St. Lucie Units I and 2 10 CFR 50.46 Annual Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 and St. Lucie Unit 2 are performed by AREVA and Westinghouse Electric Company (W), respectively.

The following information pertaining to the evaluation models for small break loss of coolant accidents (SBLOCA) and large break loss of coolant accidents (LBLOCA), and the application of such models to each St. Lucie unit, is provided pursuant to 10 CFR 50.46(a)(3)(ii).

A summary of calculated peak cladding temperature (PCT) changes is provided in Table 1. The data interval for this report is from January 1, 2009 through December 31, 2009. A discussion of the changes follows.1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA 1.1.1 No errors were found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.2. The limiting SBLOCA PCT remains at 1702 'F and is documented in Table 1.1.2 Changes to LBLOCA 1.2.1 No errors were found in the LBLOCA ECCS performance analysis since the previous report of Reference 3.2. The limiting LBLOCA PCT remains at 2079 'F and is documented in Table 1.2.0 ST. LUCIE UNIT 2 2.1 Changes to SBLOCA 2.1.1 No errors were found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.1. The limiting SBLOCA PCT remains at 19430 F and is documented in Table 1.2.2 Changes to LBLOCA 2.2.1 Re-analysis due to Radial Enrichment Zoning The St. Lucie Unit 2 LBLOCA analysis was re-analyzed to account for changes in the core parameters due to the implementation of radial enrichment zoning. The re-analysis, performed with the replacement steam generator parameters, used the same method as that of the previous analysis.

The re-analysis resulted in changing the PCT from 21307F to 2104 0 F.

L-2010-067 Attachment Page 2 of 4 2.2.2 Correction of a Steam Generator Input Error An error was identified in the calculation of the secondary side cross-sectional area for the steam generators.

The error resulted in an over-prediction of the mass and energy of the secondary side. The impact was estimated to be -4°F, resulting in a final PCT of 2100°F as documented in Table 1.

3.0 REFERENCES

3.1 FPL Letter L-2009-061, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report," March 11, 2009.3.2 FPL Letter L-2009-277, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Unit I Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report," November 30, 2009.3.3 FPL Letter L-2008-254, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Unit I Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report," December 4, 2008.

L-2010-067 Attachment Page 3 of 4 Table 1: 2009 St. Lucie Units 1 and 2 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary Evaluation Model: XN-NF-82-49(P)(A), Revision Evaluation Model PCT: 17651F 1, Supplement 1 Net PCT Effect Absolute PCT Effect A Prior 10 CFR 50.46 Changes or Error APCT -7 OF 11 OF Corrections

-Previous Years B Prior 10 CFR 50.46 Changes or Errors APCT -56 OF 72 OF*Corrections

-Year 2009 C 10 CFR 50.46 Changes in Year 2009 Since APCT 0 OF 0 OF Item B D Absolute Sum of 10 CFR 50.46 Changes APCT 83 OF The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1702OF < 2200OF changes and errors identified since this analysis Unit 1 LBLOCA Summary Evaluation Model: EMF-2087(P)(A), Revision 0 Evaluation Model PCT: 2005OF Net PCT Effect Absolute PCT Effect A Prior 10 CFR 50.46 Changes or Error APCT +54 OF 56 OF**Corrections

-Previous Years B Prior 10 CFR 50.46 Changes or Errors APCT +20 OF 20 OF*B_ Corrections

-Year 2009 C 10 CFR 50.46 Changes in Year 2009 Since APCT 0 OF 0 OF Item B F D Absolute Sum of 10 CFR 50.46 Changes APCT 76 0 F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 2079OF < 2200OF changes and errors identified since this analysis*¢Reference 3.2 contains a 30 day report related to this cumulative PCT.Reference 3.3 contains a 30 day report related to this cumulative PCT.

L-2010-067 Attachment Page 4 of 4 Unit 2 SBLOCA Summary Evaluation Model: CENPD-137, Supplement 2-P-A Evaluation Model PCT: 19431F Net PCT Effect Absolute PCT Effect A Prior 10 CFR 50.46 Changes or Error APCT 0 OF 0 OF Corrections

-Previous Years B Prior 10 CFR 50.46 Changes or Errors APCT 0 OF 0 OF Corrections

-Year 2009 C 10 CFR 50.46 Changes in Year 2009 Since APCT 0 OF 0 OF Item B D Absolute Sum of 10 CFR 50.46 Changes APCT 0 OF The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1943 0 F < 2200OF changes and errors identified since this analysis Unit 2 LBLOCA Summary Evaluation Model: CENPD-132, Supplement 4-P-A (1999 EM)Evaluation Model PCT: 2104OF Net PCT Effect Absolute PCT Effect Previous Evaluation Model PCT 2130°F A Prior 10 CFR 50.46 Changes or Error APCT 0 OF 0 OF Corrections

-Previous Years B Prior 10 CFR 50.46 Changes or Errors APCT 0 OF 0 OF Corrections

-Year 2009 C 10 CFR 50.46 Changes in Year 2009 Since APCT (see below) (see below)Item B New Evaluation Model PCT due to Re- PCT 2104 OF analysis Steam generator Input Error APCT -4 OF 4 OF D Absolute Sum of 10 CFR 50.46 Changes APCT 4 F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 2100OF < 2200OF changes and errors identified since this analysis