RA-21-0044, AP1000 Combined License Application Departure Report Update and 10 CFR 50.46 Annual Update

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AP1000 Combined License Application Departure Report Update and 10 CFR 50.46 Annual Update
ML21111A311
Person / Time
Site: 05200022, 05200023
Issue date: 04/21/2021
From: Catherine Nolan
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-21-0044
Download: ML21111A311 (12)
v • d • e


Text

M. Christopher Nolan 1.. DUKE Vice President Nuclear Regulatory Affairs, Policy &

SUBJECT:

AP1000 Combined License Application Departure Report Update and 10 CFR 50.46 Annual Update Duke Energy Progress, Inc. (DEP) submitted an application, dated February 18, 2008, for a combined license for two AP1000 advanced pressurized water reactors to be located at the Shearon Harris Nuclear Power Plant Site. Part 7 of the application is entitled Departures and Exemption Requests. This letter provides an update to the report describing plant-specific departures from the AP1000 Design Control Document (i.e. Departures Report) as required by 10 CFR 52, Appendix D, paragraphs X.B.1 and X.B.3.b.

There have been no new departures or changes to the departures described in the Shearon Harris Nuclear Power Plant (HAR), Units 2 and 3, COLA Part 7, Departures and Exemption Requests for the period of September 24, 2020 to April 22, 2021.

In addition, this letter provides a required report in accordance with 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, for HAR.

A design certification holder is required to report to the NRC in accordance with 10 CFR 50.46(a)(3). This same regulation required a similar report from any combined license (COL) holder and COL applicant. The DEP COL application for HAR, Units 2 and 3, incorporates by reference the AP1000 design certification document and thus, also utilize the peak cladding temperature calculations performed by Westinghouse Electric Company (WEC). As such, the WEC report, provided in the Enclosure, is applicable to HAR Units 2 and 3.

This submittal contains no regulatory commitments.

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U.S. Nuclear Regulatory Commission RA-21-0044 Enclosure Letter from Zachary S. Harper, Westinghouse Electric Company to the U.S. Nuclear Regulatory Commission 10 CFR 50.46 Annual Report for the AP1000 Plant Design Letter No. DCP_NRC_003344, dated March 24, 2021

Westinghouse Non-Proprieta1y Class 3 DCP_NRC_003344 Page 1 of 9

@ Westinghouse Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulat01y Commission Direct tel: 412-374-5093 Document Control Desk Direct fax: 724-940-8505 11555 Rockville Pike e-mail: hamerzs@westinghouse.com Rockville, MD 20852 Your Ref: Docket No.52-006 Our Ref: DCP NRC 003344 March 24, 2021

Subject:

10 CFR 50.46 Annual Report for the APlO00 Plant Design Pursuant to 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors", Westinghouse Electric Company, LLC is submitting this repo1t to document emergency core cooling system (ECCS) evaluation model changes or e1rnrs for the 2020 Model Year (i.e., 01/01/2020 - 12/31/2020) that affect the peak cladding temperature (PCT) calculations for the APlOOO plant design.

As described below, two APIOOO analyses of record (AORs) are repo1ted:

APIOOO Design Ce1tification AOR:

On December 30th, 2011 , the U.S . Nuclear Regulato1y Commission ce1tified an amendment to the Design Ce1tification Rule for the APIOOO plant. As such, APl 000 Design Control Document (DCD) Revision 19 documents the AOR for the APlOOO Design Ce1tification. The limiting transient for the APl 000 Design Certification is the Best Estimate Large Break Loss-of-Coolant Accident (LBLOCA). Westinghouse last provided an annual repo1ting letter to the NRC in March 2020 (DCP_NRC_ 003340) which presented an estimated PCT of 2010°F for the LBLOCA evaluation. There are no new ECCS model changes that impact PCT for the 2020 model year.

The estimated PCT for LBLOCA remains at 2010°F and does not exceed the 10 CFR 50.46 (b)(l) acceptance criterion of 2200°F.

TI1e sununa1y of the PCT margin allocations and their bases for the APlOOO Design Ce1tification AOR are provided in the Attachment 1.

APIOOO Vogtle Units 3 & 4 AOR:

In addition to the AOR for the APlOOO Design Ce1tification, the NRC has approved the APlOOO Core Reference Repo1t (WCAP-17524-P-A), a generic topical which includes an ECCS "reanalysis" in the context of 10 CFR 50.46. The AOR contained in the Core Reference Rep01t (CRR) has also been approved for inco1poration into the Vogtle Units 3 & 4 licenses via NRC License Amendment 52. Westinghouse last provided an annual rep01ting letter to the NRC in March 2020 (DCP_NRC_ 003340) which presented an estimated PCT of 2046°F for the LBLOCA evaluation. There are no new ECCS model changes that impact the limiting LBLOCA PCT for AP1000 is a trademark or registered trademark of Westinghouse Electric Company LLC, its affiliates and/or its subsidiaries in the United States ofAmerica and may be registered in other countries throughout the world. All rights resen1ed.

Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners

© 2021 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3 the 2020 model year. As such, the estimated PCT for LBLOCA is 2046°F and does not exceed the IO CFR 50.46 (b)(I) acceptance criterion of 2200°F.

Additionally, changes as part of the Automatic Depressurization System (ADS) and Core Makeup Tank (CMT) design parameters changes included in LAR-19-009 constitute a "reanalysis" in the context of IO CFR 50.46 for the small break loss of coolant accident (SBLOCA) analysis and have been approved for incorporation into the Vogtle Units 3&4 licenses via NRC License Amendments 176 (Unit 3) and 175 (Unit 4). The estimated LBLOCA PCT continues to be the limiting estimated PCT following the SBLOCA reanalysis.

The summary of the PCT margin allocations and their bases for the APl 000 Vogtle Units 3 & 4 AOR are provided in the Attachment 2.

By copy of this letter, COL Holders and COL Applicants are hereby notified of any changes or errors in the API000 standard plant design PCT calculations as required by IO CFR 50.46(a)(3)(iii). This letter contains site-specific evaluations for Vogtle Units 3 & 4.

Questions or requests for additional infonnation related to content and preparation of this information should be directed to Westinghouse. Please send copies of such questions or requests to the respective COL Holders and COL Applicants referencing the amended API000 Design Certification Rule for the API 000 nuclear power plant. A representative for each COL Holder and COL Applicant is included on the cc: list of this letter.

Very truly yours, Zachary S. Harper Manager, API000 Licensing

/Attachments I. IO CFR 50.46 Annual Report for the AP I 000 Design Certification AOR, 2020 Model Year

2. 10 CFR 50.46 Annual Report for the API0O0 Vogtle Units 3 & 4 AOR, 2020 Model Year Cc:

M. Dudek - U.S. NRC A. Zaremba - Duke/Progress M. Corletti - Westinghouse A. Bradford -U.S. NRC S. Franzone - FPL A. Schoedel - Westinghouse W. Ward - U.S. NRC R. Orthen -FPL M. Yuan - Westinghouse A. Chamberlain -SNC L. Oriani - Westinghouse D. McDevitt - Westinghouse M. Humphrey -SNC D. Weaver - Westinghouse M. Sheaffer - Westinghouse E. Grant -SNC A. Konig - Westinghouse M . Barca - Westinghouse Y. Arafeh -SNC K. Hosack - Westinghouse M. Patterson - Westinghouse

© 2011 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3 DCP_ NRC_003344 Page 3 of 9 Attachment 1 10 CFR 50.46 Annual Repo11 for the APIOOO Design Ce11ification AOR, 2020 Model Year

© 2021 Westinghouse Electric Company LLC All Rights Reserved

DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 4 of 9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: APlOOO Utility Name: Westinghouse Nuclear Power Plants EM: ASTRUM (2004)

AOR

Description:

Best Estimate Large Break Summary Sheet Status:DCD PCT {°F) Reference# Note#

ANALYSIS-OF-RECORD 1837 1 Delta PCT Reporting ASSESSMENTS* {°AF) Reference# Note# Year**

1. Evaluation of Pellet The1mal 2012 Conductivity Degradation and 139 2 Peaking Factor Bumdown
2. Revised Heat Transfer 2013 11 3 Multiplier Distributions
3. Eirnr in Burst Strain Application 23 4 2013 AOR + ASSESSME rTs PCT= 2010.0 Of
  • The licensee should determine the rep01tability of these assessments pmsuant to 10 CFR 50.46.
    • The "Reporting Year" refers to the annual rep01ting year in which this assessment was included.

REFERENCES l APP-GW-GL-700, Revision 19, "API000 Design Control Document," June 2011.

2 LTR-LIS-12-288, "hlfonnation Regarding the Evaluation of Fuel Pellet The1mal Conductivity Degradation and Peaking Factor Bumdown hlcluding Analysis hlput Changes for APIO00 Large Break LOCA Analysis," Jm1e 2012.

3 LTR-LIS-13-357, "APl000 Plant 10 CFR 50.46 Repo1t for Revised Heat Transfer Multiplier Distributions," July 2013 .

4 LTR-LIS-14-41 , "APIO00 Plant 10 CFR 50.46 Repo1t for the HOTSPOT Burst Strain Enor CoITection,"

Januaiy 2014.

NOTES:

(a) None

© 2021 Westinghouse Electric Company LLC All Rights Reserved

DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 5 of9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: APlOOO Utility Name: Westinghouse Nuclear Power Plants EM: NOTRUMP-AP AOR

Description:

Appendix K Small Break Summary Sheet Status:DCD PCT (0 F) Reference# Note#

ANALYSIS-OF-RECORD 1370 (a)

Delta PCT Reporting ASSESSMENTS* {°AF) Reference# Note# Year**

1. Adiabatic Heat-up Calculation 264 2 (a) 2010 AOR + ASSESSME TS PCT = 1634.0 °F
  • The licensee should determine the rep01tability of these assessments pmsuant to 10 CFR 50.46.
    • The "Reporting Year" refers to the annual rep01ting year in which this assessment was included.

REFERENCES 1 APP-GW-GL-700, Revision 19, "APl000 Design Control Document," June 20 11.

2 LTR-LIS-10-373, "10 CFR 50.46 Repo1t for the Evaluation of APl 000 SBLOCA 10-inch Transient Adiabatic Heat-up Calculation," June 2010.

NOTES:

(a) This is an adiabatic heat-up calculated PCT.

© 2021 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3 DCP_ NRC_003344 Page 6 of 9 Attachment 2 10 CFR 50.46 Annual Rep01t for the APlOOO Vogtle Units 3 & 4 AOR, 2020 Model Year

© 2021 Westinghouse Electric Company LLC All Rights Reserved

DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 7 of9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: Vogtle Unit 3 and Unit 4 Utility Name: Southern Nuclear Operating Company EM: ASTRUM (2004)

AOR

Description:

Best Estimate Large Break Summary Sheet Status:Cunent PCT (0 F) Reference# Note#

ANALYSIS-OF-RECORD 1936 (a)

Delta PCT Reporting ASSESSMENTS* {°AF) Reference# Note# Year**

1. Revised Heat Transfer 2013 11 2 Multiplier Distributions
2. Eirnr in Burst Strain Application 23 3 2013
3. Design Change Rebaseline 2018 54 4,5 (b)

Evaluation

4. Evaluation ofRCP Design 2019 22 6,7 (c)

Changes - LAR 189 AOR + ASSESSMENTS PCT= 2046.0 Of

  • The licensee should detennine the rep01tability of these assessments pursuant to 10 CFR 50.46.
    • The "Reporting Year" refers to the ammal repo1ting year in which this assessment was included.

REFERENCES 1 WCAP-17524-P-A, Revision 1, "APl000 Core Reference Repo1t," May 2015.

2 LTR-LIS-13-357, "APl000 Plant 10 CFR 50.46 Repo1t for Revised Heat Transfer Multiplier Distributions " July 2013 .

3 LTR-LIS-14-41 , "APlO0O Plant 10 CFR 50.46 Repo1t for the HOTSPOT Burst Strain Enor Co1Tection,"

Jaimaiy 2014.

4 LTR-LIS-18-393 , "Update to the Vogtle Units 3 & 4 LBLOCA and SBLOCA 10 CFR 50.46 PCT Summary Sheets for LAR-79," November 2018.

5 ND-17-2074 (ML18029A243), " Containment Pressure Analysis (LAR-17-043)," December 2017 .

Approved byNRC November 7, 2018 as Amendments 147 (VEGP Unit 3) and 146 (VEGP Unit 4)

(ML18289A742).

6 LTR-LIS-17-39, "APlO00 Plant Suggested 10 CFR 50.46 Reporting Text and Updated LBLOCA PCT Smnma1y Sheet for Evaluation of Reactor Coolant Pump (RCP) Design Changes," Januaiy 2017.

7 ND-18-1147 (ML18243A459), "Reactor Coolant System (RCS) Flow Coastdown (LAR-18-025)," August 2018. Approved by NRC Febmaiy 25 , 2019 as Amendments 155 (VEGP Unit 3) aiid 154 (VEGP Unit 4)

© 2021 Westinghouse Electric Company LLC All Rights Reserved

DCP_ NRC_003344 Westinghouse Non-Proprietary Class 3 Page 8 of 9 (ML19038A450).

NOTES:

(a) Value contains 2°F bias for PCT sensitivity to PRHR isolation, per Reference 1 response to CRR-008, Table 2 and Table 15.6.5-8.

(b) Tue design change rebaseline evaluation used ctment code versions and accounts for design changes up to May 5, 2014 and plant model enor conections.

(c) Tue RCP design changes evaluation assesses the impact ofDCP 5338 (APP-GW-GEE-5338), which is tied to DCP 4880 (APP-GW-GEE-4880). Tue evaluated changes include updated homologous curves and small changes to the pump rated conditions and rotor ineliia.

© 2021 Westinghouse Electric Company LLC All Rights Reserved

DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 9 of9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: Vogtle Unit 3 and Unit 4 Utility Name: Southern Nuclear Operating Company EM: NOTRUMP-AP AOR

Description:

Appendix K Small Break Summary Sheet Status: CUITent PCT (0 F) Reference# Note#

ANALYSIS-OF-RECORD 1099 1 AOR + ASSESSME rTs PCT= 1099.0 °F REFERENCES 1 ND-19-1142 (ML19273A953), "Automatic Depresslllization System (ADS) and Core Makeup Tank (CMT) Design Parameters (LAR-19-009)," September 2019. Approved by NRC March 11, 2020 as Amendments 176 (VEGP Unit 3) and 175 (VEGP Unit 4) (ML20049A721 /ML20049A808).

NOTES:

(a) None

© 2021 Westinghouse Electric Company LLC All Rights Reserved

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