L-2017-056, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 Annual Report

Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 Annual Report

ML17086A321
Person / Time
Site:	Saint Lucie
Issue date:	03/27/2017
From:	Snyder M Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2017-056
Download: ML17086A321 (4)

Text

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MAR 2 7 20t7 L-2017-056 10 CPR 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 CPR 50.46 Annual Report Pursuant to 10 CPR 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 this report is from January 1, 2016 through December 31, 2016.

Please contact Ken Prehafer at 772-467-77 48 should you have any questions regarding this submittal.

Sincerely,

~if;£/

Licensing Manager St. Lucie Plant MJS/K\W Attachment cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Nuclear Plant Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2017-056 Attachment Page 1 of 3 St. Lucie Units 1 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 1 and 2 (for St. Lucie Units 1 and 2, respectively). The data interval for this report is from January 1, 2016 through December 31, 2016. A discussion of the changes follows.

1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA No errors were found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 1 provides a summary of PCT changes for St. Lucie Unit 1.

1.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 1 provides a summary of PCT changes for St. Lucie Unit 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. Table 2 provides a summary of PCT changes for St. Lucie Unit 2.

2.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 2 provides a summary of PCT changes for St. Lucie Unit 2.

3.0 REFERENCES

3.1 Letter L-2016-049, Eric Katzman to U.S. Nuclear Regulatory Commission Attn: 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 2, 2016 (ML16077A230).

L-2017-056 Attachment Page 2 of 3 Table 1: 2016 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: 1828°F Net PCT Absolute PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections -

A +22 °F 82 °F up to Year 2015 Prior 10 CFR 50.46 Changes or Error Corrections -

B None None Year 2016 C 10 CFR 50.46 Changes in Year 2016 Since Item B None None D Sum of 10 CFR 50.46 Changes +22 °F 82 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1850 F < 2200 F impact for 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: 1788°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections A +6 °F 6°F

- up to Year 2015 Prior 10 CFR 50.46 Changes or Error Corrections B None None

- Year 2016 C 10 CFR 50.46 Changes in Year 2016 Since Item B Incorrect cutback ratio applied to gadolina bearing

+0 °F 0 °F rods D Sum of 10 CFR 50.46 Changes +6 °F 6°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1794 F < 2200 F impact for changes and errors identified since this analysis

L-2017-056 Attachment Page 3 of 3 Table 2: 2016 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: 1903°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections -

A 0 °F 0 °F up to Year 2015 Prior 10 CFR 50.46 Changes or Errors Corrections -

B None None Year 2016 C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1903 °F < 2200 °F impact for changes and errors identified since this analysis Unit 2 LBLOCA Summary Evaluation Model: CENPD-132, Supplement 4-P-A (1999 EM)

Evaluation Model PCT: 2087°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections -

A up to Year 2015 0 °F 0 °F (Reference 3.1)

Prior 10 CFR 50.46 Changes or Errors Corrections -

B None None Year 2016 C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 2087 °F < 2200 °F impact for changes and errors identified since this analysis