L-2008-046, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report

Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report

ML080850563
Person / Time
Site:	Saint Lucie
Issue date:	03/18/2008
From:	Johnston G Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2008-046
Download: ML080850563 (3)

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0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 March 18, 2008 IFPL L-2008-046 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, 2007 through December 31, 2007.

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Site Vice Presic St. Lucie Plant GLJ/KWF Attachment an FPL Group company

St. Lucie Units 1 and 2 L-2008-046 Docket Nos. 50-335 and 50-389 Attachment 10 CFR 50.46 Annual Report Page 1 of 2 St. Lucie Units 1 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, 2007 through December 31, 2007.

1.0 ST LUCIE UNIT 1 1.1 One error was found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.1 and is described below. Table 1 summarizes the estimated impact of this error on the St. Lucie Unit 1 SBLOCA PCT. The limiting SBLOCA PCT remains at 17660 F.

Error in the SBLOCA bypass flow modeling An error in the modeling of the SBLOCA bypass flow was identified during the year 2007. The bypass flow model in the St. Lucie Unit 1 SBLOCA analysis was not consistent with the methodology guidelines. The impact of this error is estimated to be 0 'F 1.2 No errors were found in the LBLOCA ECCS performance analysis since the previous report of Reference 3.1. The limiting LBLOCA PCT remains at 2047' F.

2.0 ST. LUCIE UNIT 2 2.1 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.

2.2 No errors were found in the LBLOCA ECCS performance analysis since the previous report of Reference 3.1. The limiting LBLOCA PCT remains at 2130' F.

REFERENCES 3.1 FPL Letter L-2007-040, Gordon L. Johnston. to USNRC 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 22, 2007.

St. Lucie Units 1 and 2 L-2008-046 Docket Nos. 50-335 and 50-389 Attachment 10 CFR 50.46 Annual Report Page 2 of 2 Table 1: 2007 St. Lucie Units,1 and 2 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary PCT Year 2006 10 CFR 50.46 Annual Report (L-2007-040) 1766 OF Change from error in SBLOCA bypass flow modeling 0 OF Year 2007 10 CFR 50.46 Annual Report 1766 OF Total cumulative changb from last acceptable model (up to 12/31/07) 3 OF Unit 1 LBLOCA Summary PCT Year 2006 10 CFR 50.46 Annual Report (L-2007-040) 2047 OF Changes during 2007 0 OF Year 2007 10 CFR 50.46 Annual Report 2047 OF Total cumulative change from last acceptable model (up to 12/31/07) 44 OF Unit 2 SBLOCA Summary PCT Year 2006 10 CFR 50.46 Annual Report (L-2007-040) 1943 OF Changes during 2007 0 OF Year 2007 10 CFR 50.46 Annual Report 1943 OF Total cumulative change from last acceptable model (up to 12/31/07) 0 OF Unit 2 LBLOCA Summary PCT Year 2006 10 CFR 50.46 Annual Report (L-2007-040) 2130 OF Changes during 2007 0 OF Year 2007 10 CFR 50.46 Annual Report 2130 OF Total cumulative change from last acceptable model (up to 12/31/07) 0 OF