L-2021-066, CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications

CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications

ML21105A488
Person / Time
Site:	Saint Lucie, Point Beach, Seabrook, Turkey Point
Issue date:	04/14/2021
From:	Parks W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2021-066
Download: ML21105A488 (16)

Text

April 14, 2021 L-2021-066 10 CFR50.46 ATIN: 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, I.LC Seabrook Station, Docket No. 50-443 NextEra Energy Point Beach, I.LC 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)(it), 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 Florida Power & Light's Turkey Point Nuclear Plant, Units 3 and 4; and St Lucie Nuclear Plant, Units 1 and 2; NextEra Energy Seabrook Station; and NextEra Energy Point Beach Nuclear Plant, Units 1 and 2 are reported in the attachments to this letter. The data interval for this report is from January 1, 2020 through December 31, 2020.

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-2021-066 Page 2 of2 Should you have any questions regarding this report, please contact Mr. Steve Catron, Fleet Licensing Manager, at (561) 304-6206.

Very truly yours, tv~~

William L. Parks General Manager, Safety Assurance and Learning Florida Power & Light Company Attachments (4) cc: USNRC Regional Administrator, Region I USNRC Regional Administrator, Region II USNRC Regional Administrator, Region III 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

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

L-2021-066 Attachment 1 Page I 1 of2 Table 1:

Turkey Point Unit 3 & 4 Small Break LOCA PCT 2020 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 Absolute PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections - up to 12/31/2019 (Reference 2) 0°F 0°F IO CFR 50.46 Changes or Errors Corrections -year 2020 None None Sum of 10 CFR 50.46 Changes or Errors Corrections 0°F 0°F I

The sum ofthe PCTfrom 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:

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

2. Letter from W. Parks to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annµal Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," L-2020-041, April 14, 2020.

L-2021-066 Attachment 1 Page I 2of2 Table 2:

Turkey Point Unit 3 & 4 Large Break LOCA PCT 2020 Annual Report Evaluation Methodology:

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

Evaluation Model PCT: 2152 °F (Reference 1)

Net PCT Absolute PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections - up to

-28 °F 80 Of 12/31/2019 (Reference 2) 10 CFR 50.46 Changes or Errors Corrections -year 2020 None None Sum of 10 CFR 50.46 Changes or Errors Corrections -28°F 80°F The sum ofthe PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT 2124 °F < 2200 °F impact for changes and e"ors identified since this analysis

References:

1. Letter from M. Kiley to U.S. Nuclear Regulatory 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, January 16, 2012.

2. Letter from W. Parks 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-2020-041, April 14, 2020.

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

L-2021-066 Page I 1 of4 Table 1:

St. Lucie Unit 1 Small Break LOCA PCT 2020 Annual Report Evaluation Methodology:

Framatome, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," EMF-2328(P)(A)

Revision Oas supplemented by ANP-3000(P), Revision 0.

Evaluation Model PCT: 1828°F NetPCT Absolute PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections - up to

+24°F 84 °F Year 2019 (Reference 1) 10 CFR 50.46 Changes or Error Corrections - Year 2020 None None Sum of 10 CFR 50.46 Changes or Error Corrections +24°F g4op The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1852 °F < 2200 °F impactfor changes and errors identified since this analysis

References:

1. Letter L-2020-041, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," 4/14/20 (ML20105A379).

L-2021-066 Page I 2of4 Table 2:

St. Lucie Unit 1 Large Break LOCA PCT 2020 Annual Report Evaluation Methodology:

Framatome, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," EMF-2103(P)(A) Revision Oas supplemented by ANP-2903(P), Revision 1.

Evaluation Model PCT: 1788°F Absolute PCT Net PCT Effect Effect Prior IO CFR 50.46 Changes or Error Corrections - up to

+6°F 6°F Year 2019 (Reference 1)

IO CFR 50.46 Changes or Error Corrections - Year 2020 None None Sum of IO CFR 50.46 Changes or Error Corrections +6oF 6°F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1794 °F < 2200 °F impactfor changes and errors identified since this analysis

References:

1. Letter L-2020-041, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," 4/14/20 (ML20105A379).

L-2021-066 Page I 3of4 Table 3:

St. Lucie Unit 2 Small Break LOCA PCT 2020 Annual Report Evaluation Methodology:

Framatome, 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 Year2019 (Reference I) 10 CFR 50.46 Changes or Error Corrections - Year 2020 None None Sum of 10 CFR 50 .46 Changes or Error Corrections -279°P 393 °P The sum of the PCTfrom 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 L-2020-041, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," 4/14/20 (ML20105A379).

L-2021-066 Page 14 of4 Table 4:

St. Lucie Unit 2 Large Break LOCA PCT 2020 Annual Report Evaluation Methodology:

Framatome, "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 10 CFR 50.46 Changes or Error Corrections - up to 0 op 0 °F Year 2019 (Reference 1) 10 CFR 50.46 Changes or Error Corrections - Year 2020 None None Sum of 10 CFR 50.46 Changes or Error Corrections 0°F 0°F The sum of the PCTfrom 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 L-2020-041, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," 4/14/20 (ML20105A379).

ATTACHMENT 3 NextEra Energy Seabrook Station

L-2021-066 Attachment 3 Page I 1 of2 Table 1:

Seabrook Unit 1 Small Break LOCA PCT 2020 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 CFR 50 .46 Changes or Error Corrections - up to oop 12/31/2019 (Reference 2) 00°F 10 CFR 50.46 Changes or Errors Corrections -year 2020 None None Sum of 10 CFR 50.46 Changes or Errors Corrections oop oop The sum ofthe PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1373 °F < 2200 °F impactfor changes and e"ors 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 W. Parks 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-2020-041, April 14, 2020.

L-2021-066 Attachment 3 Paget 2of2 Table 2:

Seabrook Unit 1 Large Break LOCA PCT 2020 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 CFR 50.46 Changes or Error Corrections - up to 155 °P 155 °P 12/31/2019 (Reference 2) 10 CPR 50.46 Changes or Errors Corrections -year 2020 None None Sum of 10 CPR50.46 Changes or Errors Corrections 155 °P 155 °P The sum ofthe PCTfrom 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 Regulatory Commission, "License Amendment Request 04-03, Application for Stretch Power Uprate," NYN-04016, March 17, 2004.

2. Letter from W. Parks 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-2020-041, April 14, 2020.

ATTACHMENT 4

. NextEra Energy Point Beach Units 1 and 2

L-2021-066 Page 11 of2 Table 1:

Point Beach Units 1 and 2 Small Break LOCA PCT 2020 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 I/Unit 2): 1049°F/1103°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections - up to 0°F/0°F 0°F/0°F Year 2019 (Reference 1) 10 CFR 50.46 Changes or Error Corrections - Year 2020 None None Sum of 10 CFR 50.46 Changes or Error Corrections 0°F/0°F 0°F/0°F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1049°F/1103°F < 2200 °F impact for changes and errors identified since this analysis

References:

1. Letter L-2020-041, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in in Emergency Core Cooling System Models or Applications," 4/14/2020 (ML20105A379).

L-2021-066 Pagel 2of2 Table 2:

Point Beach Units 1 and 2 Large Break LOCA PCT 2020 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 1, 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 Year 2019 (Reference 1)

+210°F/+248°F 210°F/340°F 10 CFR 50.46 Changes or Error Corrections - Yeat 2020 None None Error in Unheated Conductor Noding 0°F/0°F 0°F/0°F (Reference 2)

Sum of 10 CFR 50.46 Changes or Error Corrections +210°F/+248°F 210°F/340°F The sum of the PCTfrom 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 L-2020-041, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in in Emergency Core Cooling System Models or Applications," 4/14/2020 (ML20105A379).

2. Letter L-2020-128, "10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report," 8/10/2020 (ML20227Al08).