L-2007-040, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report
| ML070890310 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/22/2007 |
| From: | Johnston G Florida Power & Light Co |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| L-2007-040 | |
| Download: ML070890310 (3) | |
Text
0 FPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 March 22, 2007 L-2007-040 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, 2006 through December 31, 2006.
Please contact us should you have any questions regarding this submittal.
V ytuyyours, Gordon L. Jo ton Site Vice Pres* e St. Lucie Plan GLJ/KWF Attachment AG02 an FPL Group company
St. Lucie Units 1 and 2 Attachment Docket Nos. 50-335 and 50-389 Page 1 L-2007-040 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 Framatome ANP, Inc. (FRA-ANP) 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, 2006 through December 31, 2006.
1.0 ST LUCIE UNIT 1 1.1 No errors were found in the SBLOCA emergency core cooling system (ECCS) performance analysis since the previous report of Reference 3.1. The limiting SBLOCA PCT remains at 17660F.
1.2 One error was found in the LBLOCA 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 LBLOCA PCT. The limiting LBLOCA PCT remains at 20470F.
Error in the steam condensation in ICECON subcode A minor error in the ICECON subcode in the AREVA LBLOCA evaluation model was identified during the year 2006. The error was an indexing error caused by faulty coding logic. In dry containments, such as PSL Unit 1, the error has no impact on the calculated PCT value (0°F change).
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 19430F.
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 21300F.
3.0 REFERENCES
3.1 FPL Letter L-2006-082, 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 17, 2006.
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2007-040 Table 1: 2006 St. Lucie Units 1 and 2 SBLOCA and LBLOCA PCT Summary Attachment Page 2 Unit 1 SBLOCA Summary PCT Year 2005 10 CFR 50.46 Annual Report (L-2006-082) 1766 OF Changes during 2006 0 OF Year 2006 10 CFR 50.46 Annual Report 1766 OF Total cumulative change from last acceptable model (up to 12/31/06) 3 OF Unit 1 LBLOCA Summary PCT Year 2005 10 CFR 50.46 Annual Report (L-2006-082) 2047 OF Change in steam condensation of ICECON subcode 0 OF Year 2006 10 CFR 50.46 Annual Report 2047 OF Total cumulative change from last acceptable model (up to 12/31/06) 44 OF Unit 2 SBLOCA Summary PCT Year 2005 10 CFR 50.46 Annual Report (L-2006-082) 1943 OF Changes during 2006 0 OF Year 2006 10 CFR 50.46 Annual Report 1943 OF Total cumulative change from last acceptable model (up to 12/31/06) 0 OF Unit 2 LBLOCA Summary Year 2005 10 CFR 50.46 Annual Report (L-2006-082)
Changes during 2006 Year 2006 10 CFR 50.46 Annual Report Total cumulative change from last acceptable model (up to 12/31/06)