L-2019-057, Cf~ 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications

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

ML19080A058
Person / Time
Site:	Saint Lucie, Point Beach, Seabrook, Turkey Point, Duane Arnold
Issue date:	03/19/2019
From:	Parks W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2019-057
Download: ML19080A058 (18)

Text

March 19, 2019 L-2019-057 10 CFR 50.46 ATTN: Document Control Desk U. S. Nuclear Regulato1y 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 N extEra Energy Seabrook, LLC Seabrook Station, Docket No. 50-443 N extEra Energy Duane Arnold, LLC Duane Arnold Energy Center, Docket No. 50-331 N extEra Energy Point Beach, LLC Point Beach Units 1 and 2, Docket Nos. 50-266, 50-301 10 CF~ 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 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; NextEra Energy Duane Arnold; 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, 2018 through December 31, 2018.

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-2019-057 Page 2 of2 Should you have any questions regarcling this report, please contact Mr. Steve Catron, Fleet Licensing Manager, at (561) 304-6206.

Very truly yours, wfi~

William Parks

\ Director, Nuclear Licensing and Regulatory Compliance Florida Power & Light Company Attachments (5) 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, Duane Arnold Energy Center 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, Duane Arnold Energy Center USNRC Senior Resident Inspector, Point Beach Nuclear Plant

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

L-2019-057 Page 11 of2 Table 1:

Turkey Point Unit 3 & *4 Small Break LOCA PCT 2018 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 - Ab~olute PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections- up to 0 op 0 op 12/31/2017 (Reference 2) 10 CPR 50 .46 Changes or Errors Corrections - year 2018 None Sum of 10 CPR 50.46 Changes or Errors Corrections 0 op 0 op The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT impact 1231 °F < 2200 °F for changes and errors identified since this analysis References!

1. 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 L. Nicholson to U.S. Nuclear Regulatory Commission, "10 CPR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," L-2018-063, March 26, 2018.

L-2019-057 Attachment 1 Page 12 of2 Table 2:

Turkey Point Unit 3 & 4 Large Break LOCA PCT 2018 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

.J Prior 10 CFR 50 .46 Changes or Error Corrections - up to

-28 °F 80 °F 12/31/2017 (Reference 2) 10 CFR 50.46 Changes or Errors Corrections -year 2018 I

Inconsistent Application of Numerical Ramp Applied to the Entrained Liquid / Vapor Interfacial 0 op 0 op Drag Coefficient (Reference 2)

Inappropriate Resetting of Transverse Liquid Mass 0 op 0 op Flow (Reference 2)

Steady-State Fuel Temperature Calibration Method 0 op 0 op (Reference 2)

Sum of 10 CFR 50.46 Changes or Errors Corrections -28 °F 80 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact 2124 °F < 2200 °F for changes and errors identified since this analysis

References:

1

l. 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 L. Nicholson to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," L-2018-063, March 26, 2018.

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

L-2019-057 Page 11 of 4 Table 1:

St. Lucie Unit 1 Small Break LOCA PCT 2018 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 Net PCT Absolute PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections- up to

+24°P 84 °P Year 2017 (Reference 1) 10 CPR 50 .46 Changes or Error Corrections - Year 2018 None None Sum of 10 CPR 50.46 Changes or Error Corrections +24 °P 84 °P The sum of the PCTfrom 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 L-2018-063, "10 CPR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," 3/2(,/18 (ML18088A163).

L-2019-057 Page 12 of4 Table 2:

St. Lucie Unit,1 Large Break LOCA PCT 2018 Annual Report Evaluation Methodology:

Framatome, "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 CFR 50.46 Changes or Error Corrections- up to +6 op 6°F Year 2017 (Reference 1) 10 CFR 5 0 .46 Changes or Error Corrections - Year 2018 Norie None Sum of 10 CFR 50.46 Changes or Error Corrections +6°F 6°F The sum of the PCTfrom 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 L-2018-063, "10 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," 3/26/18 (ML18088Al63).

L-2019-057 Page 13 of4 Table 3:

St. Lucie Unit 2 Small Break LOCA PCT 2018 Annual Report Evaluation Methodology:

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

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

-279°P 393 °P Year 2017 (Referenc~ 1) 10 CPR 50 .46 Changes or Error Corrections - Year 2018 None None Sum of 10 CPR 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-2018-063, "10 CPR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency-Core Cooling System Models or Applications," 3/26/18 (ML18088A163).

L-2019-057 Page J 4 of4 Table 4:

St. Lucie Unit 2 Large Break LOCA PCT 2018 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 CPR 50.46 Changes or Error Corrections- up to 0 op 0 op Year 2017 (Reference 1) 10 CFR 50 .46 Changes or Error Corrections - Year 2018 None None Sum of 10 CPR 50.46 Changes or Error Corrections 0 op 0 op 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:

I. Letter L-2018-063, "10 CPR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," 3/26/18 (ML18088A163).

ATTACHMENT 3 N extEra Energy Seabrook Station

L-2019-057 Page 11 of 2 Table 1:

Seabrook Unit 1 Small Break LOCA PCT 2018 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 12/31/2017 (Reference 2) 10 CPR 50.46 Changes or Errors Corrections-year 2018 None Sum of 10 CPR 50.46 Changes or Errors Corrections 0 op 0 op The sum of the PCTfrom tl?e most recent analysis using an acceptable evaluation model and the estimates ofPCT impact 1373 °F < 2200 °F 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 L. Nicholson to U.S. Nuclear Regulatory Commission, "10 CPR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," L-2018-063, March 26, 2018.

L-2019-057 Page J 2 of2 Table 2:

Seabrook Unit 1 Large Break LOCA PCT 2018 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)

NetPCT Absolute PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections-up to 155 °F 155 °F 12/31/2017 (Reference 2) 10 CFR 50.46 Changes or Errors Corrections -year 2018 Inconsistent Application of Numerical Ramp Applied to 1he Entrained Liquid / Vapor Interfacial 0 op 0 op Drag Coefficient (Reference 2)

Inappropriate Resetting of Transverse Liquid Mass 0 op 0 op Flow (Reference 2)

Sum of 10 CFR 50.46 Changes or Errors Corrections 155 °F 155 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact 1939 °F < 2200 °F 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 L. Nicholson to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," L-2018-063, March 26, 2018.

ATTACHMENT 4 NextEra Energy Duane Arnold

L-2019-057 Page 11 of 1 Table 1:

Duane Arnold GNF2 LOCA PCT 2018 Annual Report Evaluation Methodology:

General Electric, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of Coolant Accident: Volume III - SAFER/GESTR Application Methodology," NEDE-23785-1-PA, February 1985.

Global Nuclear Fuel, Licensing Topical Report, "The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance," Technical Bases - NEDC-33256P-A, Qualification - NEDC-33257P-A, and Application Methodology- NEDC-33258P-A, September 2010.

General Electric-Hitachi, "Duane Arnold Energy Center GNF2 ECCS-LOCA Evaluation," Engineering Report #0000-0133-6901-RO, DRF 0000-0133-6885-RO, August 2012.

Evaluation Model PCT: 1730 °F Net PCT Absolute Effect PCT Effect Prior 10 CFR 50.46 Changes or Error Corrections-up to 12/31/2017

-10 °F 70 °F (Reference 1) 10 CFR 50.46 Changes or Error Corrections -2018 None Sum of 10 CFR 50.46 Changes or Errors Corrections -10 °F 70 °F The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and 1720 °F < 2200 °F errors identified since this analysis

References:

1. Letter from L. Nicholson (Florida Power & Light Company) to USNRC, "10 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications," L-2018-063, March 26, 2018.

ATTACHMENT 5 N extE,ra Energy Point Beach Units 1 and 2

L-2019-057 Page 11 of2 Table 1:

Point Beach Units 1 and 2 Small Break LOCA PCT 2018 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 Absolute PCT Effect Effect Prior 10 CFR 50 .46 Changes or Error Corrections - up to 0°F/0°F 0°F/0°F Year 2017 (Reference 1) 10 CFR 50 .46 Changes or Error Corrections - Year 2018 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-2018-063, "10 CFR 50.46 Annual Reporting and 30-day Notification ofchanges or Errors in Emergency Core Cooling System Models or Applications," 3/26/2018 (ML18088A163). ,

L-2019-057

' ' Attachment 5 Page 12 of2 Table 2:

Point Beach Units 1 and 2 Large Break LOCA PCT 2018 Annual Report Evaluation Methodology:

Westinghouse, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), 11 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

+210°F/+248°F 210°F/340°F Year 2017 (Reference 1) 10 CFR 50.46 Changes or Error Corrections - Year 2018 Inconsistent application of numerical ramp applied to the entrained liquid/vapor interfacial oopfOop 0°F/0°F drag coefficient (Reference 1)

Inappropriate resetting of transverse liquid mass oopfOop 0°F/0°F flow (Reference 1)

Potential non-conservatism in the steady state fuel 0°F/0°F 0°FI0°F temperature calibration method (Reference 1)

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-2018-063, "10 CFR 50.46 Annual Reporting and 30-day Notification of changes or Errors in Emergency Core Cooling System Models or Applications," 3/26/2018 (ML18088A163).