L-2016-049, Annual Operating Report for St. Lucie 1 and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors

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Annual Operating Report for St. Lucie 1 and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors
ML16077A230
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 03/02/2016
From: Katzman E
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2016-049
Download: ML16077A230 (6)
v • d • e


Text

0F=PLo March 2, 2016

  • L-2016-049 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 SO0.46(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, 2015 through December 31, 2015.

Please contact Ken Frehafer at 772-467-7748 should you have any questions regarding this submittal.

Sincerely, Eric S. Katzman ~'e ~k*

Licensing Manager St. Lucie Plant ESK/KWF Attachment Florida Power &Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2016-049 Attachment Page 1 of 5 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 (__* 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, 2015 through December 31, 2015. A discussion of the changes follows.

St. Lucie Unit 1 transitioned to M5 fuel rod cladding during the year 2015 and the new evaluation model PCT with M5 cladding was reported to the NRC in Reference 3.2.

1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCTto support the change to M5 cladding. No errors were found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.2. The limiting SBLOCA PCT remains at 1850 0F and is documented in Table 1.

1.2 Changes to LBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCT to support the change to M5 cladding. There was one error found in the LBLOCA ECCS performance analysis since the previous report of Reference 3.2.

The error is in the cutback ratio (relative power) for once-burned gadolina bearing fuel rod compared to rods containing only U235. This resulted in gadolina bearing rods being modeled at an artificially reduced power, and when corrected results in an estimated impact to the PCT of 0 0F The limiting LBLOCA PCT with the above estimated impact remains at 1794 °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 0 F and is documented in Table 2.

L-2016-049 Attachment Page 2 of 5 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 0 F and is documented in Table 2.

3.0 REFERENCES

3.1 Letter L-2015-093, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Units 1 and 2 Docket Nos. 50-33 5 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report," March 24, 2015 (ML15092A097).

3.2 Letter L-2015-1 55, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "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," May 14, 2015 (ML15149A150).

L-20 16-049 Attachment Page 3 of 5 Table 1: 2015 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 Absolute PCT Net PCT Effect Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections -

Previous Years ANA N/A N/A (New evaluation model during Year 2015, ReferenceN/

3.2) ________

Prior 10 CFR 50.46 Changes or Errors Corrections -

B Current Year (Reference 3.2) 0 0 0 Vapor absorptivity correlation applied outside the +2 2 80 bounds of the correlation Design Change for Initial Pressurization of Fuel Rod -30 0F 30 0 F 1850 0 F C 10 CFR 50.46 Changes in Current Year Since Item B 0 0F 0 0F 1850 0 F D Sum of 10 CFR 50.46 Changes +22 0 F 82 0 F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 1850 °F < 2200 °F changes and errors identifiedsince this analysis

L-20 16-049 Attachment Page 4 of 5 Unit 1 LBLOCA Summary Evaluation Model: EMF-2103(P)(A) Rev. 0 as supplemented by ANP-2903(P), Revision 1.

Evaluation Model PCT: 17880 F Absolute PCT Net PCT Effect Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections -

A Previous YearsN/NA (New evaluation model during Year 2015, ReferenceN/

3.2)

Prior 10 CFR 50.46 Changes or Errors Corrections -

B Current Year (Reference 3.2)

S-RELAP5 RODEX3a Trapped Stack Coding Error +6 °F 6 °F 1794 0F S-RELAP5 Vapor Absorptivity Correlation Error 0 °F 0 °F 1794 °F Modal Decomposition Generation of Non-Physical 0° 0 °F 1794 0F Shapes Design Change for Initial Pressurization of Fuel Rod 0 0F 0 °F 1794 0F C 10 CFR 50.46 Changes in Current Year Since Item B Incorrect cutback ratio applied to gadolina bearing rods +0 0F 0 °F 1794 0F D Sum of 10 CFR 50.46 Changes +6 °F 60F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 1794 0 F < 2200 0 F changes and errors identified since this analysis

L-201 6-049 Attachment Page 5 of 5 Table 2: 2015 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 0 F Absolute PCT Net PCT Effect Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections -

A Previous Years 0 °F 0 °F 1903 °F (Reference 3.1)

B Prior 10 CFR 50.46 Changes or Errors Corrections - 0° 0 0F 1903 0F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0F 0 0F 1903 0 F D Sum of 10 CFR 50.46 Changes 0 0F 0 0F The sum of the PCTfitom the most recent analysis using an acceptable evaluationmodel and the estimates of PCT impact for 1903 0 F < 2200 °F 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 EfetPCT Prior 10 CFR 50.46 Changes or Error Corrections -

A Previous Years 0 °F 0 °F 2087 °F (Reference 3.1)__________

B Prior 10 CFR 50.46 Changes or Errors Corrections - 0 0F ,0 0F 2087 0F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0F 0 0F 2087 0F D Sum of 10 CFR 50.46 Changes 0 0F 0 0F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 2087 °F < 2200 °F changes and errors identified since this analysis

0F=PLo March 2, 2016

  • L-2016-049 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 SO0.46(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, 2015 through December 31, 2015.

Please contact Ken Frehafer at 772-467-7748 should you have any questions regarding this submittal.

Sincerely, Eric S. Katzman ~'e ~k*

Licensing Manager St. Lucie Plant ESK/KWF Attachment Florida Power &Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2016-049 Attachment Page 1 of 5 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 (__* 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, 2015 through December 31, 2015. A discussion of the changes follows.

St. Lucie Unit 1 transitioned to M5 fuel rod cladding during the year 2015 and the new evaluation model PCT with M5 cladding was reported to the NRC in Reference 3.2.

1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCTto support the change to M5 cladding. No errors were found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.2. The limiting SBLOCA PCT remains at 1850 0F and is documented in Table 1.

1.2 Changes to LBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCT to support the change to M5 cladding. There was one error found in the LBLOCA ECCS performance analysis since the previous report of Reference 3.2.

The error is in the cutback ratio (relative power) for once-burned gadolina bearing fuel rod compared to rods containing only U235. This resulted in gadolina bearing rods being modeled at an artificially reduced power, and when corrected results in an estimated impact to the PCT of 0 0F The limiting LBLOCA PCT with the above estimated impact remains at 1794 °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 0 F and is documented in Table 2.

L-2016-049 Attachment Page 2 of 5 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 0 F and is documented in Table 2.

3.0 REFERENCES

3.1 Letter L-2015-093, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Units 1 and 2 Docket Nos. 50-33 5 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report," March 24, 2015 (ML15092A097).

3.2 Letter L-2015-1 55, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "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," May 14, 2015 (ML15149A150).

L-20 16-049 Attachment Page 3 of 5 Table 1: 2015 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 Absolute PCT Net PCT Effect Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections -

Previous Years ANA N/A N/A (New evaluation model during Year 2015, ReferenceN/

3.2) ________

Prior 10 CFR 50.46 Changes or Errors Corrections -

B Current Year (Reference 3.2) 0 0 0 Vapor absorptivity correlation applied outside the +2 2 80 bounds of the correlation Design Change for Initial Pressurization of Fuel Rod -30 0F 30 0 F 1850 0 F C 10 CFR 50.46 Changes in Current Year Since Item B 0 0F 0 0F 1850 0 F D Sum of 10 CFR 50.46 Changes +22 0 F 82 0 F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 1850 °F < 2200 °F changes and errors identifiedsince this analysis

L-20 16-049 Attachment Page 4 of 5 Unit 1 LBLOCA Summary Evaluation Model: EMF-2103(P)(A) Rev. 0 as supplemented by ANP-2903(P), Revision 1.

Evaluation Model PCT: 17880 F Absolute PCT Net PCT Effect Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections -

A Previous YearsN/NA (New evaluation model during Year 2015, ReferenceN/

3.2)

Prior 10 CFR 50.46 Changes or Errors Corrections -

B Current Year (Reference 3.2)

S-RELAP5 RODEX3a Trapped Stack Coding Error +6 °F 6 °F 1794 0F S-RELAP5 Vapor Absorptivity Correlation Error 0 °F 0 °F 1794 °F Modal Decomposition Generation of Non-Physical 0° 0 °F 1794 0F Shapes Design Change for Initial Pressurization of Fuel Rod 0 0F 0 °F 1794 0F C 10 CFR 50.46 Changes in Current Year Since Item B Incorrect cutback ratio applied to gadolina bearing rods +0 0F 0 °F 1794 0F D Sum of 10 CFR 50.46 Changes +6 °F 60F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 1794 0 F < 2200 0 F changes and errors identified since this analysis

L-201 6-049 Attachment Page 5 of 5 Table 2: 2015 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 0 F Absolute PCT Net PCT Effect Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections -

A Previous Years 0 °F 0 °F 1903 °F (Reference 3.1)

B Prior 10 CFR 50.46 Changes or Errors Corrections - 0° 0 0F 1903 0F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0F 0 0F 1903 0 F D Sum of 10 CFR 50.46 Changes 0 0F 0 0F The sum of the PCTfitom the most recent analysis using an acceptable evaluationmodel and the estimates of PCT impact for 1903 0 F < 2200 °F 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 EfetPCT Prior 10 CFR 50.46 Changes or Error Corrections -

A Previous Years 0 °F 0 °F 2087 °F (Reference 3.1)__________

B Prior 10 CFR 50.46 Changes or Errors Corrections - 0 0F ,0 0F 2087 0F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0F 0 0F 2087 0F D Sum of 10 CFR 50.46 Changes 0 0F 0 0F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impactfor 2087 °F < 2200 °F changes and errors identified since this analysis

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