L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report

10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report

ML19220A049
Person / Time
Site:	Point Beach, Seabrook, Turkey Point
Issue date:	08/06/2019
From:	Parks W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2019-151
Download: ML19220A049 (8)

Text

• . FPL.

August 6, 2019 L-2019-151' 10 CFR 50.46 U.S. Nuclear Regulatory Commission Attn: Dcicuinent Control Desk .

Washington, DC 20555-0001.

Re: *N exi:Era Energy Point Beach, LLC

• Point Beach Units 1 mid 2, Docket Nos. 5Q:C266, 50-301

• Florida Power &Light Company Turkey Point Units 3 and 4, Docket.Nos. 50-250, 50-251.

NextEra Energy Seabrook; LLC

.Seabrook Station, Docket No. 50-443

• 10 CFR. -

50.46 - .Emergency

. . . . Core

. Cooling .System LBLOCA 30-Day

. . Report

.. Pursuant to.10 CFR 50.46(a)(3)(ii), this letter contains.th~ 30-day report for.the Point Beach Nuclear Plant, .

Units 1 and'2, Turkey Point Nuclear Plant,Units 3 and*4, and Seabrook Statton for the emergency core cooling system an~ysis performed by Westinghouse Electric *company, I.LC, in the respective attachments to **

this letter.

, . I. . . . . . .

One error \val') ideµtified by Westinghouse that affects the Large-Break (LB) LOCA models. As the reported

• error is of a 0°F iinpact, the PCT continues to remain within the limits:. However, as the cumulative PCT change already exceeds 50 °F for the LBLOCA analysis, a 30 day 10CFR50.46 report must be issued. .

... ~valuationi.of each teported eri:61: have ccmcluded that re-analysis was not required...

This ktter contains no new 9r revised regulatory commitments. . \.

Should you have any question~ regarding this report, please contact Mr. Steve Catroh; Fleet Licehsing Manager, at (561) 304-620.6.

• : Very truly yours,

• WilliamL Parks Director, Nuclear Regulatory Affairs .

Florida.Power &Light Company **

Attachm~nts. (3) AP/)l-f'i (<.R-Florid.a.Power & Light Company 700 Universe Boulevard, Juno Beach, FL 33408

L-2019-151 10 CFR 50.46 P~ge 2 of2 cc: USNRC Regional Administrator, Region I USNRC Regional Administrator, Region II USNRC Regional Administrator, Region III USNRC Project Manager, Point Beach Nuclear Plartt USNRC Project Manager, Turkey Point Nucleru: Plant USNRC Project Manager, Seabrook Station USNRC Senior Resident Inspector, Point Beach Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Seabrook Station

Attachme11t 1 POINT BEACH

L-2019-151 10 CFRS0.46 Attachment 1 Page 1 ofl Point Beach Units 1 and 2 Large Break LOCA PCT 30-Day 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 2018 r (Reference I) +210°F/+248°F 210°F/340°F

\

Prior IO CFR 50.46 Changes or Error Corrections - Year 2019 (Reference 2) 0°F/0°F 0°F/0°F New 10 CFR 50.46 Changes or Error Corrections- Year 2019 I Error in the Implementation of the Vessel Interfacial Heat 0°F/0°F 0°F/0°F Transfer Limit Sum of IO CFR 50.46 Changes or Error Corrections +210°F/+248°F 210°F/340°F The sum of the. PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and 2185°F/2058°F < 2200°F errors identified since this analysis Error in the Implementation of Vessel Interfacial Heat Transfer Limit Westinghouse identified an error in the implementation of vessel interfacial heat transfer limit applicable to tne large break loss of coolant (LBLOCA) WCOBRA/TRAC code. Westinghouse has, however, determined that the use of the code remains consistent with the original code validation runs. The impact on the peak cladding temperature (PCT) is estimated to be 0°F.

References:

1. L-2019-057, W. Parks (FPL) to U.S. Nuclear Regulatory Commission, "10CFR50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System'Models or Applications,"

March 19, 2019.

2. L-2019-058, W. Parks (FPL) to U.S. Nuclear Regulatory Commission, "10CFR50.46-Emergency Core Cooling System LBLOCA 30-Day Report," March 25, 2019.

Attachment 2 TURKEY POINT

L-2019-151 10 CFR 50.46 Attachment 2 Page 1 of 1 Turkey Point Units 3 and 4 Large Break LOCA PCT 30-Day 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 (Unit 1/Unit 2): 2152°F (Reference 1)

Net PCT Absolute PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections - up to Year 2018 -2sap soap (Reference 2)

Prior 10 CPR 50.46 Changes or Errors Corrections- Year 2019 r I Error in Vapor Temperature Resetting Logic (Reference 3) oap oap New 10 CPR 50.46 Changes or Errors Corrections- Year 2019

-,..J J Error in the Implementation of the Vessel Interfacial Heat oap - oap Transfer Limit .

Sum of 10 CPR 50.46 Changes or Errors Corrections -2sap soap The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT impact for changes and 2124aF < 2200aF errors identified since this analysis Error in the Implementation of Vessel Interfacial Heat Transfer Limit Westinghouse identified an error in the implementation of vessel interfacial heat transfer limit applicable to the large break loss of coolant (LBLOCA) WCOBRA/TRAC code. Westinghouse has, however,

• determined that the use of the code remains consistent with the original code validation runs. The impact on the peak cladding temperature (PCT) is estimated to be 0°F.

References:

1. L-2012-019, M. Kiley (FPL) 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," January 16, 2012.

2. L-2019-057, W. Parks (FPL) 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,"

March 19, 2019.

3. L-2019-058, W. Parks (FPL) to U.S. Nuclear Regulatory Commission, "10 CFR 50.46-Emergency Core Cooling System LBLOCA 30-Day Report," March 25, 2019.

SEABROOK

,4 * ' '

L-2019-151 10 CFR 50.46 Attachment 3 Page 1 of1 Seabrook Unit 1 Large Break LOCA PCT

.30-Day 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 Year 2018 155°F 155°F (Reference 2)

Prior 10 CFR 50.46 Changes or Errors Corrections - Year 2019 Error in Vapor Temperature Resetting Logic (Reference 3) oop oop New 10 CFR 50.46 Changes or Errors Corrections- Year 2019 ,-

Error in the Implementation of the Vessel Interfacial Heat oop oop Transfer Limit Sum of 10 CFR 50.46 Changes or Errors Corrections 155°F 155°F The sum ofthe PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT impact for changes and I939°F < 2200°F errors identified since this analysis Error in the Implementation of Vessel Interfacial Heat Transfer Limit

, Westinghouse identified an error in the implementation of vessel interfacial heat transfer limit applicable to the large break loss of coolant (LBLOCA) WCOBRA/TRAC code. Westinghouse has, however, determined that the use of the code remains consistent with the original code validation runs. The impact on the peak cladding temperature (PCT) is estimated to be 0°F.

References:

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

/

2. L-2019-057. W. Parks (FPL) 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,"

March 19, 2019.

3. L-2019-058, W. Parks (FPL) to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 -

Emergency Core Cooling System LBLOCA 30-Day Report," March 25, 2019.