L-2015-093, 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

ML15092A097
Person / Time
Site:	Saint Lucie
Issue date:	03/24/2015
From:	Katzman E Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2015-093
Download: ML15092A097 (5)

Text

March 24, 2015 L-2015-093 0 10 CFR 50.46 FPL.

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, 2014 through December 31, 2014.

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 ES K/K WF Attachment Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2015-093 Attachment Page 1 of 4 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 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 Tables I and 2 (for St. Lucie Units I and 2, respectively). The data interval for this report is from January 1, 2014 through December 31, 2014. A discussion of the changes follows.

1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA One error was found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1.

The vapor absorptivity correlation was incorrectly applied outside of the bounds of the correlation. When the equations using the correlation were truncated at the appropriate conditions, the estimated impact was 90 'F.

This error was previously reported in a 30-day report in Reference 3.2.

The limiting SBLOCA PCT with the above estimated impact is 1870 'F and is documented in Table 1.

1.2 Changes to LBLOCA There were two errors found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1.

The vapor absorptivity correlation was incorrectly applied outside of the bounds of the correlation. When the equations using the correlation were truncated at the appropriate conditions, the estimated impact was 0 'F.

The modal decomposition (re-mapping of neutronics nodes to S-RELAP5 node structure) resulted in non-physical axial shapes being generated in some cases. For PSL I the shapes generated still remained applicable, therefore the estimated impact was 0 'F.

The limiting LBLOCA PCT with the above estimated impact is 1672 'F and is documented in Table 1.

2.0 ST. LUCIE UNIT 2 2.1 Changes to SBLOCA No errors were found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. The limiting SBLOCA PCT remains at 1903 'F and is documented in Table 1.

2.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. The limiting LBLOCA PCT remains at 2087 'F and is documented in Table 1.

L-2015-093 Attachment Page 2 of 4

3.0 REFERENCES

3.1 Letter L-2014-095, Eric 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 31, 2014.

3.2 Letter L-2014-134, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St.

Lucie Unit I Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report," May 12, 2014.

L-2015-093 Attachment Page 3 of 4 Table 1: 2014 St. Lucie Unit 1 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary Evaluation Model: EMF-2328(P)(A) Rev. 0 as supplemented by ANP-3000(P), Revision 0 Evaluation Model PCT: 18071F Absolute PCT Net PCT Effect PCT Effect Prior 10 CFR 50.46 Changes or Error A Corrections - Previous Years -27 OF 27 OF 1780 OF (Reference 3.1)

B Prior 10 CFR 50.46 Changes or Errors See below See below Corrections - Current Year (Reference 3.2)

Vapor absorptivity correlation applied +90 OF 90 OF 1870 0F outside the bounds of the correlation C 10 CFR 50.46 Changes in Current Year 0 OF 0 OF 1870 OF Since Item B D Absolute Sum of 10 CFR 50.46 Changes APCT 117 OF The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 1870 OF < 2200 OF changes and errors identified since this analysis Unit 1 LBLOCA Summary Evaluation Model: EMF-2103(P)(A) Rev. 0 as supplemented by ANP-2903(P), Revision 1 Evaluation Model PCT: 1667 0F Absolute PCT Net PCT Effect Effe Effect PCT Prior 10 CFR 50.46 Changes or Error A Corrections - Previous Years +5 OF 23 OF 1672 OF S(Reference 3.1)

B Prior 10 CFR 50.46 Changes or Errors +0 OF 0 OF 1672 OF Corrections - Current Year C 10 CFR 50.46 Changes in Current Year See below See below Since Item B Vapor absorptivity correlation applied +0 OF 0 OF 1672 OF outside the bounds of the correlation Modal decomposition generation of non- +0 OF 0 OF 1672 OF physical shapes D Absolute Sum of 10 CFR 50.46 Changes APCT 23 0 F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 1672 OF < 2200 OF changes and errors identified since this analysis

L-2015-093 Attachment Page 4 of 4 Table 2: 2014 St. Lucie Unit 2 SBLOCA and LBLOCA PCT Summary Unit 2 SBLOCA Summary Evaluation Model: CENPD-137, Supplement 2-P-A (S2M)

Evaluation Model PCT: 19031F Absolute PCT Net PCT Effect PCT Effect Prior 10 CFR 50.46 Changes or Error A Corrections - Previous Years 0 OF 0 OF 1903 OF (Reference 3.1)

B Prior 10 CFR 50.46 Changes or Errors 0 OF 0 OF 1903 OF Corrections - Current Year C 10 CFR 50.46 Changes in Current Year 0 OF 0 OF 1903 OF Since Item B D Absolute Sum of 10 CFR 50.46 Changes APCT 0 °F The sum of the PCTfrom the most recent analysis using an acceptableevaluation model and the estimates of PCT impact for 1903 OF < 2200 OF changes and errors identified since this analvsis Unit 2 LBLOCA Summary Evaluation Model: CENPD-132, Supplement 4-P-A (1999 EM)

Evaluation Model PCT: 20871F Net PCT Effect Absolute PCT EfetPCT Effect Prior 10 CFR 50.46 Changes or Error A Corrections - Previous Years 0 OF 0 OF 2087 OF (Reference 3.1)

B Prior 10 CFR 50.46 Changes or Errors 0 OF 0 OF 2087 OF Corrections - Current Year C 10 CFR 50.46 Changes in Current Year 0 OF 0 OF 2087 OF Since Item B D Absolute Sum of 10 CFR 50.46 Changes APCT 0 OF The sum of the PCTfrom the most recent analysis using an acceptable evaluationmodel and the estimates of PCT impactfor 2087 OF < 2200 OF changes and errors identifiedsince this analysis