L-2014-134, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report

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

ML14142A007
Person / Time
Site:	Saint Lucie
Issue date:	05/12/2014
From:	Katzman E Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2014-134
Download: ML14142A007 (3)

Text

May 12, 2014 0

PPL.

L-2014-134 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 AREVA 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,>,1 Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

St. Lucie Unit I L-2014-134 Docket No. 50-335 Attachment 10 CFR 50.46 Change Report Page I 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 Inc. The following 30-day report, pertaining to the application of the AREVA small break loss of coolant accident (SBLOCA) evaluation model, is provided pursuant to 10CFR 50.46(a)(3)(ii). A summary of the calculated peak cladding temperature (PCT) changes for SBLOCA is provided in Table 1.

1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA S-RELAP5 Vapor Absorptivity Correlation It was determined that a correlation for vapor absorptivity used in S-RELAP5 was being applied outside of the intended range for the correlation. The impact on the SBLOCA analysis is estimated to be an increase in PCT of 90 OF. The resultant PCT for SBLOCA is 1870 OF.

The SBLOCA PCT, with the estimated impact of the above error, maintains significant margin to the limit of 2200 OF prescribed in 10 CFR 50.46. A summary of the calculated peak cladding temperature (PCT) changes (from those reported in Reference 2.1) for SBLOCA is provided in Table 1.

2.0 REFERENCES

2.1 FPL Letter L-2014-095, 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 31, 2014.

II St. Lucie Unit I L-2014-134 Docket No. 50-335 Attachment 10 CFR 50.46 Change Report Page 2 of 2 Table 1: St. Lucie Unit 1 SBLOCA Margin Summary Sheet day Report (April 2014)

Evaluation Model: EMF-2328(P)(A) Rev. 0 as supplemented by ANP-3000(P), Revision 0 Evaluation Model PCT: 1807°F Net PCT Absolute PCT PCT Effect Effect A Prior 10 CFR 50.46 Changes or Error -27 OF 27 °F 1780 °F Corrections - Previous Years B Prior 10 CFR 50.46 Changes or O 0 OF 1780 OF Errors Corrections - Current Year 10 CFR 50.46 Changes in Current Year Since Item B S-RELAP5 Vapor Absorptivity +90 °F 90 °F 1870 °F Correlation D Sum of 10 CFR 50.46 Changes APCT +63 °F 117 OF The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the 1870 OF< 2200 OF estimates of PCT impact for changes and errors identified since this analysis