L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications

and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications

ML23086C017
Person / Time
Site:	Saint Lucie, Point Beach, Seabrook, Turkey Point
Issue date:	03/27/2023
From:	Strand D Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-2023-028
Download: ML23086C017 (1)

Text

March 27, 2023 L-2023-028 10 CFR 50.46 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Re: Florida Power & Light Company Turkey Point Units 3 and 4, Docket Nos. 50-250, 50-251 Florida Power & Light Company St. Lucie Units 1 and 2, Docket Nos. 50-335, 50-389 NextEra Energy Seabrook, LLC Seabrook Station, Docket No. 50-443 NextEra Energy Point Beach, LLC Point Beach Units 1 and 2, Docket Nos. 50-266, 50-301 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 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 Turkey Point Nuclear Plant, Units 3 and 4; and St. Lucie Nuclear Plant, Units 1 and 2; Seabrook Station; and Point Beach Nuclear Plant, Units 1 and 2 are reported in the attachments to this letter by Florida Power & Light Company (FPL), on behalf of itself and its affiliates, NextEra Energy Seabrook, LLC and NextEra Energy Point Beach, LLC . The data interval for this report is from January 1, 2022 through December 31, 2022.

Evaluations of each reported error have concluded that re-analysis was not required.

This letter contains no new or revised regulatory commitments.

Florida Power & Light Company 700 Universe Boulevard, Juno Beach, FL 33408

L-2023-028 Page 2 of 2 Should you have any questions regarding this report, please contact Mr. Kenneth Mack, Fleet Licensing Manager, at (561) 904-3635.

Very truly yours, l\(5-+.r General Manager, Regulatory Affairs Florida Power & Light Company Attachments (4) cc: USNRC Regional Administrator, Region I USNRC Regional Administrator, Region II USNRC Regional Administrator, Region Ill USNRC Project Manager, Seabrook Station USNRC Project Manager, St. Lucie Nuclear Plant USNRC Project Manager, Turkey Point Nuclear Plant USNRC Project Manager, Point Beach Nuclear Plant USNRC Senior Resident Inspector, Seabrook Station USNRC Senior Resident Inspector, St. Lucie Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Point Beach Nuclear Plant Florida Power & Light Company 700 Universe Boulevard, Juno Beach, FL 33408

ATTACHME NT 1 Florida Power & Light Company Turkey Point Units 3 and 4

L-2023-028 Page 11 of2 Table 1:

Turkey Point Unit 3 and 4 Small Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Westinghouse, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code,"

WCAP-10054-P-A, August 1985 and Addendum 2, Revision 1, July 1997.

Evaluation Model PCT: 1231 °F (Reference 1)

Net PCT Effect Absolute PCT Effect Unit 3/Unit 4 Unit 3/Unit 4 Prior 10 CPR 50.46 Changes or Error Corrections- up to 0 op 0 op 12/31/2021 (Reference 2) 10 CPR 50.46 Changes or Errors Corrections -year 2022 None None Sum of 10 CPR 50.46 Changes or Errors Corrections 0 op 0 op The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1231 °F < 2200 °F impact for changes and errors identified since this analysis

References:

l. Letter from M. Kiley to U.S. Nuclear Regulatory Commission, "License Amendment Request for Extended Power Uprate (LAR 205)," L-2010-113, October 21, 2010.

2. Letter from T. Lesniak to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," L-2022-039, April 14, 2022.

L-2023-028 Page 12 of2 Table 2:

Turkey Point Unit 3 and 4 Large Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Westinghouse, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment OfUnce11ainty Method (ASTRUM)," WCAP-16009-P-A, Revision 0, January 2005.

Evaluation Model PCT: 2152 °F (Reference 1)

Net PCT Effect Absolute PCT Effect Unit 3/Unit 4 Unit 3/Unit 4 Prior IO CPR 50.46 Changes or Error Corrections - up to -28 °P 80 °P 12/31/2021 (Reference 2)

IO CPR 50.46 Changes or Etrnrs Corrections -year 2022 Error in Non-Conservation of Energy in the 0 op 0 op Generalized Energy Deposition Model (Reference 3)

Sum of IO CPR 50.46 Changes or Errors Corrections -28 °P 80 °P The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 2124 °F < 2200 °F impact for changes and errors identified since this analysis

References:

I. Letter from M. Kiley to U.S. Nuclear Regulatmy Commission, "Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Thermal Conductivity Degradation," L-2012-019, Januaty 16, 2012.

2. Letter from T. Lesniak to U.S. Nuclear Regulatmy Commission, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," L-2022-039, April 14, 2022.

3. Letter from D. Strand to U.S. Nuclear Regulatmy Commission, "10 CFR 50.46-Emergency Core Cooling System LBLOCA 30-Day Report," L-2022-168, October 26, 2022.

ATTACHMENT 2 Florida Power & Light Company St. Lucie Units 1 and 2

L-2023-028 Page 11 of 4 Table 1:

St. Lucie Unit 1 Small Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Pramatome, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," EMF-2328(P)(A) Revision 0 as supplemented by ANP-3000(P), Revision 0.

Evaluation Model PCT: 1828°F Absolute PCT Net PCT Effect Effect Prior 10 CPR 50.46 Changes or Enor CotTections- up to

+24 °P 84 °P Year 2021 (Reference I)

IO CPR 50.46 Changes or Error Corrections - Year 2022 None None Sum of IO CPR 50.46 Changes or Error Corrections +24 °P 84 °P The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1852 °F < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter from T. Lesniak to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting of Changes to, or En-ors in Emergency Core Cooling System Models or Applications,"

L-2022-039, April 14, 2022.

L-2023-028 Page 12 of 4 Table 2:

St. Lucie Unit 1 Large Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Pramatome, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," EMF-2103(P)(A)

Revision O as supplemented by ANP-2903(P), Revision 1.

Evaluation Model PCT: 1788°F Absolute PCT Net PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections- up to +6 op 6°P Year 2021 (Reference 1) 10 CPR 50.46 Changes or Error Corrections - Year 2022 None None Sum of 10 CPR 50.46 Changes or Error Corrections +6 op 6°P The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1794 °F < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter from T. Lesniak to U.S. Nuclear Regulato1y Commission, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications,"

L-2022-039, April 14, 2022.

L-2023-028 Page 13 of4 Table 3:

St. Lucie Unit 2 Small Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Pramatome, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," EMF-2328(P)(A) Revision.0.

Evaluation Model PCT: 2057°F Absolute PCT Net PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections - up to

-279°P 393 °P Year 2021 (Reference 1) 10 CPR 50 .46 Changes or Error Corrections - Year 2022 None None Sum of 10 CPR 50.46 Changes or Enor Corrections -279°P 393 °P The sum of the PCT fi'om the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1778 °F < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter from T. Lesniak to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting of Changes to, or EITors in Emergency Core Cooling System Models or Applications,"

L-2022-039, April 14, 2022.

L-2023-028 Page 14 of 4 Table 4:

St. Lucie Unit 2 Large Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Pramatome, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," EMF-2103(P)(A)

Revision 0.

Evaluation Model PCT: 1732°F Absolute PCT Net PCT Effect Effect Prior IO CPR 50.46 Changes or Error Corrections - up to 0 op 0 op Year 2021 (Reference 1) 10 CPR 50.46 Changes or Error Corrections - Year 2022 None None Sum of 10 CPR 50.46 Changes or Error Corrections 0 op 0 op The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1732 °F < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter from T. Lesniak to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting of Changes to, or Enors in Emergency Core Cooling System Models or Applications,"

L-2022-039, April 14, 2022.

ATTACHMENT 3 N extEra Energy Seabrook, LLC Seabrook Station

L-2023-028 Page 11 of 2 Table 1:

Seabrook Unit 1 Small Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Westinghouse, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code,"

WCAP-10054-P-A, August 1985 and Addendum 2, Revision 1, July 1997 Evaluation Model PCT: 1373 °F (Reference 1)

Net PCT Absolute PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections - up to 0 op 0 op 12/31/2021 (Reference 2) 10 CPR 50.46 Changes or Errors Corrections -year 2022 None None Sum of 10 CPR 50.46 Changes or Errors Conections 0 op 0 op The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1373 °F < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter from M. Warner to U.S. Nuclear Regulatory Commission, "License Amendment Request 04-03, Application for Stretch Power Uprate," NYN-04016, March 17, 2004.

2. Letter from T. Lesniak to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," L-2022-039, April 14, 2022.

L-2023-028 Page 12 of2 Table 2:

Seabrook Unit 1 Large Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Westinghouse, "Code Qualification Document for Best Estimate LOCA Analysis," WCAP-12945-P-A, March 1998.

Evaluation Model PCT: 1784 °F (Reference 1)

Net PCT Absolute PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections - up to 155 °P 155 °P 12/31/2021 (Reference 2) 10 CPR 50.46 Changes or Errors Corrections -year 2022 Error in Non-Conservation of Energy in the Generalized Energy Deposition Model 0 op 0 op (Reference 3)

Sum of 10 CPR 50.46 Changes or Errors Corrections 155 °P 155 °P The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1939 °F < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter from M. Warner to U.S. Nuclear Regulat01y Commission, "License Amendment Request 04-03, Application for Stretch Power Uprate," NYN-04016, March 17, 2004.

2. Letter from T. Lesniak to U.S. Nuclear Regulat01y Commission, "10 CFR 50.46 Annual Rep01iing of Changes to, or En-ors in Emergency Core Cooling System Models or Applications," L-2022-039, April 14, 2022.

3. Letter from D. Strand to U.S. Nuclear Regulat01y Commission, "10 CFR 50.46-Emergency Core Cooling System LBLOCA 30-Day Report," L-2022-168, October 26, 2022.

ATTACHMENT 4 N extEra Energy Point Beach, LLC Point Beach Units 1 and 2

L-2023-028 Page 11 of2 Table 1:

Point Beach Units 1 and 2 Small Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Westinghouse, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," WCAP-10054-P-A, August 1985 and Addendum 2, Revision 1, July 1997.

Evaluation Model PCT (Unit 1/Unit 2): 1049°F/1103°F Net PCT Effect Absolute PCT Effect Unit 1/Unit 2 Unit 1/Unit 2 Prior 10 CPR 50.46 Changes or Error Corrections - up to 0°P/0°P 0°P/0°P Year 2021 (Reference 1) 10 CPR 50.46 Changes or Error Corrections - Year 2022 None None Sum of 10 CPR 50.46 Changes or Error Corrections 0°P/0°P 0°P/0°P The sum of the PCT fi*om the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1049°F/1103°P < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter from T. Lesniak to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting of Changes to, or Etrnrs in Emergency Core Cooling System Models or Applications,"

L-2022-039, April 14, 2022.

L-2023-028 Attachment 4 Page 12 of2 Table 2:

Point Beach Units 1 and 2 Large Break LOCA PCT 2022 Annual Report Evaluation Methodology:

Westinghouse, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," WCAP-16009-P-A, January 2005.

Westinghouse, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," WCAP-14449-P-A Revision I, October 1999.

Evaluation Model PCT (Unit 1/Unit 2): 1975°F/1810°F Net PCT Effect Absolute PCT Effect Unit 1/Unit 2 Unit 1/Unit 2 Prior 10 CFR 50.46 Changes or Error Corrections - up to

+2l0°F/+248°F 210°F/340°F Year 2021 (Reference 1) 10 CFR 50.46 Changes or Error Corrections - Year 2022 None None I Error in Non-Conservation of Energy in the 0°F/0°F oopJOop Generalized Energy Deposition Model (Reference 2)

Sum of 10 CFR 50.46 Changes or Error Corrections +210°F/+248°F 2 l 0°F /340°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates ofPCT 2185°F/2058°F < 2200°F impact for changes and errors identified since this analysis

References:

1. Letter from T. Lesniak to U.S. Nuclear Regulatory Commission, "10 CPR 50.46 Almual Reporting of Changes to, or EITors in Emergency Core Cooling System Models or Applications,"

L-2022-039, April 14, 2022.

2. Letter from D. Strand to U.S. Nuclear Regulatory Commission, "10 CPR 50.46-Emergency Core Cooling System LBLOCA 30-Day Report," L-2022-168, October 26, 2022.