L-2011-090, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report
| ML110871271 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/18/2011 |
| From: | Katzman E Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2011-090 | |
| Download: ML110871271 (3) | |
Text
Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 0
March 18, 2011 F=PL L-2011-090 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re:
St. Lucie Unit 1 Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report Florida Power and Light (FPL) was informed of inaccuracies in the large and small break loss of coolant accident (LOCA) analyses. The subsequent calculation that assessed the effects of these issues, along with other previous changes and errors in the accident analysis, resulted in a new peak cladding temperature (PCT) value within the regulatory limit of 2200 'F provided in 10 CFR 50.46. However, the accumulated effect on PCT was greater than 50 'F.
According to 10 CFR 50.46, when a cumulative PCT change in errors or changes to the analysis of 50 'F occurs, a 30 day report shall be sent to the NRC with a proposed schedule for providing reanalysis or taking action as may be needed to show compliance with 50.46 requirements. This information is provided in the attachment to this letter.
Please contact Ken Frehafer at (772) 467-7748 should you have any questions regarding this submittal.
Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment S00Z-an FPL Group company
L-2011-090 Attachment Page 1 of 2 St. Lucie Unit 1 - 10 CFR 50.46 30-Day Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 is performed by AREVA NP Inc. The following 30-Day report pertaining to the application of the AREVA NP Inc. large break loss of coolant accident (LBLOCA) evaluation model (SEM/PWR-98) to St. Lucie Unit 1, is provided pursuant to 10 CFR 50.46(a)(3)(ii). A summary of the calculated peak cladding temperature (PCT) changes for LBLOCA is provided in Table 1.
1.0 Changes to LBLOCA 1.1 Array Index Issues in RELAP4 Code AREVA identified array index issues in the RELAP4 code used as part of the EMF-2087(P)(A) SEM/PWR-98 LOCA methodology for PWRs. This methodology is used in the current St. Lucie Unit 1 LBLOCA analysis. The impact of this issue on St. Lucie Unit 1 PCT is estimated to be 0' F.
1.2 Previous LBLOCA PCT changes are documented in Reference 2.1. Table I summarizes the estimated impact of the changes/errors on the St. Lucie Unit 1 LBLOCA PCT. The cumulative PCT change for LBLOCA remains at 760 F. The limiting LBLOCA PCT with the estimated effect of all the changes/errors is 20790 F. With the impact of all changes/errors, St. Lucie Unit I LBLOCA PCT of 2079' F continues to comply with the 10 CFR 50.46 acceptance criterion for PCT of< 22000 F.
LBLOCA for St. Lucie Unit I has been re-analyzed and submitted in November 2010, as part of the Extended Power Uprate (EPU) license amendment request (Reference 2.2).
2.0 References 2.1 FPL Letter L-2010-067, Eric S. Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Units 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 30, 2010 2.2 FPL Letter L-2010-259, Richard L. Anderson to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Plant Unit 1, Docket No. 50-335 Renewed License No. DPR-67, License Amendment Request for Extended Power Uprate," November 22, 2010
L-2011-090 Attachment Page 2 of 2 Table 1: St. Lucie Unit 1 LBLOCA PCT Margin Summary Sheet Day Report Evaluation Model:
Evaluation Model PCT:
EMF-2087(P)(A), Revision 0 2005 OF Net PCT Effect Absolute ect PCT Effect A.
Prior 10 CFR 50.46 Changes or Error Corrections APCT
+ 74°F
- Previous Years (L-2010-067, Reference 2.1) 76 0F B.
Prior 10 CFR 50.46 Changes or Error Corrections APCT 0°F 0°F
- Year 2010 C.
Current 10 CFR 50.46 Changes
- 1. Effect of array index issues in RELAP4 code APCT 0°F 0°F Absolute Sum of 10 CFR 50.46 Changes APCT 760F The sum of the PCTftom the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors 2079°F < 2200°F identified since this analysis