L-2006-082, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors
| ML060870391 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/17/2006 |
| From: | Johnston G Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2006-082 | |
| Download: ML060870391 (3) | |
Text
I FPpL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 3X1957 March 17, 2006 L-2006-082 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, 2005 through December 31, 2005.
Please contact us should you have any questions regarding this submittal.
Very truly yours, Gordon L. Johnston)
Acting Vice Preside St. Lucie Plant GLJ'KWF Attachment fl D01 an FPL Group company
St. Lucie Units 1 and 2 Attachment Docket Nros. 50-335 and 50-389 Page 1 L-2006-082 St. Lucie Units 1 and 2 10 CFR 50.46 Annual Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit I and St. Lucie Unit 2 are performed by Framrtome ANP, Inc. (FRA-ANP) and Westinghouse Electric Company (I), 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, 2005 through December 31, 2005.
1.0 ST LUCIE UNIT 1 1.1 Nro errors were found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.1. The limiting SBLOCA PCT remains at 17660F.
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 20470F.
2.0 ST. LUCIE UNIT 2 2.1 No errors were found in the SBLOCA ECCS performance analysis since the approval of License Amendment 138. The limiting SBLOCA PCT remains at 1943TF.
2.2 No errors were found in the LBLOCA ECCS performance analysis since the approval of License Amendment 138. The limiting LBLOCA PCT remains at 21307F.
3.0 REFERENCES
3.1 FPL Letter L-2005-067, W. Jefferson, Jr. to USNRC Document Control Desk, St. Lucie Uni :s I 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 31, 2005.
St. Lucie Units 1 and 2 Docket lros. 50-335 and 50-389 L-2006-082 Attachment Page 2 Table 1: 2005 St. Lucie Units 1 and 2 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary PCT Year 2004 10 CFR 50.46 Annual Report (L-2005-067) 17660F Change during Year 2005 0F Year 2005 10 CFR 50.46 Annual Report 17660F Unit 1 LBLOCA Summary PCT Year 2004 10 CFR 50.46 Annual Report (L-2005-067) 20470F Change during Year 2005 0F Year 2005 10 CFR 50.46 Annual Report 20470F Unit 2 SBLOCA Summary PCT Year 2004 10 CFR 50.46 Annual Report (L-2005-067) 2132.60F New Evaluation Model PCT (Approved in License Amendment 138) 1943 OF Change during Year 2005 0 OF Year 2005 10 CFR 50.46 Annual Report 1943 OF Unit 2 LBLOCA Summary PCT Year 2004 10 CFR 50.46 Annual Report (L-2005-067) 21260F New Evaluation Model PCT (Approved in License Amendment 138) 2130 OF Change during Year 2005 0 OF Year 2005 10 CFR 50.46 Annual Report 21300F