RA-21-0042, William States Lee III Nuclear Station, Units 1 and 2 - Submission of Periodic Reports

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William States Lee III Nuclear Station, Units 1 and 2 - Submission of Periodic Reports
ML21111A321
Person / Time
Site: Lee  Duke Energy icon.png
Issue date: 04/21/2021
From: Catherine Nolan
Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-21-0042
Download: ML21111A321 (12)
v • d • e


Text

1.. DUKE M. Christopher Nolan

  • ~ ENERGY Vice President Nuclear Regulatory Affairs, Policy &

Emergency Preparedness Duke Energy 526 South Church Street, EC07C Charlotte, NC 28202 704-382-7426 Chris.Nolan@duke-energy.com Serial: RA-21-0042 April 21, 2021 10 CFR 52, Appendix D, X.B 10 CFR 50.59 10 CFR 52.97 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 WILLIAM STATES LEE III NUCLEAR STATION, UNITS 1 AND 2 COMBINED LICENSE NOS NPF-101 AND NPF-102 DOCKET NOS.52-018 AND 52-019

SUBJECT:

Submission of Periodic Reports

REFERENCES:

1. Letter from Joseph W. Donahue (Duke Energy) to U.S. Nuclear Regulatory Commission (NRC), dated October 8, 2018, Submission of Periodic Reports and Annual UFSAR Update, Serial: NPD-NRC-2018-010.

The purpose of this letter is to submit periodic reports for William States Lee III Nuclear Station (WLS), Units 1 and 2 as required by NRC regulations and/or license conditions for a Part 52 combined license holder. These reports address various annual or semi-annual reporting requirements. The following reports are addressed by this letter:

  • Semi-Annual Changes, Tests, and Experiments Report
  • Semi-Annual Departures Report
  • Semi-Annual Schedule for Implementation of Operational Programs
  • Annual 10 CFR 50.46 Report Semi-Annual Departures Report and Semi-Annual Changes, Tests, and Experiments Report. For the WLS Units 1 and 2, in accordance with the requirements of 10 CFR 50.59(d)(2) and 10 CFR 52, Appendix D, paragraphs X.B.1 and X.8.3.b, during the period of September 24, 2020 through April 22, 2021:
  • no changes, tests or experiments were implemented pursuant to 10 CFR 50.59(c), and

Semi-Annual Schedule for Implementation of Operational Programs. Pursuant to the WLS COL Section 2.D.(11), a schedule for implementation of operational programs is required to be submitted within one year of the date of COL issuance, with subsequent reports submitted on a

U.S. Nuclear Regulatory Commission RA-21-0042 Page 2 semi-annual basis until the 10 CFR 52.103(g) finding. There are no changes to the schedule since the letter sent in Reference 1. Therefore, the previously submitted schedule continues to be current.

Annual 10 CFR 50.46 Report. In accordance with 10 CFR 59.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," for the WLS Units 1 and 2. A design certification holder is required to report to the NRC in accordance with 10 CFR 50.46(a)(3). This same regulation requires a similar report from any combined license (COL) holder and COL applicant. The Duke Energy COL for WLS Units 1 and 2 incorporate 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 the WLS Units 1 and 2.

This letter contains no new regulatory commitments.

Please address any comments or questions regarding this matter to Art Zaremba, Manager -

Fleet Licensing at (980) 373-2062.

Sincerely, M. Christopher Nolan Vice President, Nuclear Regulatory Affairs, Policy & Emergency Preparedness

Enclosure:

Letter from Zachary S. Harper, Westinghouse Electric Company (WEC), 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.

cc: L. Dudes, U.S. NRC Region II Administrator

0. Murray, U.S. NRC Project Manager

U.S. Nuclear Regulatory Commission RA-21-0042 Enclosure Letter from Zachary S. Harper, Westinghouse Electric Company (WEC), 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 of9

@ 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 c1iteria 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 enors for the 2020 Model Year (i.e., 01/01/2020 - 12/3 l /2020) that affect the peak cladding temperan1re (PCT) calculations for the APl000 plant design.

As described below, two APIO00 analyses of record (AORs) are repo1ted:

APIO0O Design Ce1tification AOR:

On December 30th, 2011 , the U.S . Nuclear Regulato1y Commission ce1tified an amendment to the Design Ce1tification Rule for the APIO00 plant. As such. APl 000 Design Control Document (DCD) Revision 19 documents the AOR for the APl000 Design Ce1tification. The limiting transient for the APl00O 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 summa1y of the PCT margin allocations and their bases for the APl000 Design Ce1tification AOR are provided in the Attachment 1.

APIO00 Vogtle Units 3 & 4 AOR:

In addition to the AOR for the APl000 Design Ce1tification, the NRC has approved the APl000 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 APJOOO 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 rese,-,ied.

Unauthorized use is strictly prohibited. Other names mco1be 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 API 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 10 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 infonnation should be directed to Westinghouse. Please send copies of such questions or requests to the respective COL Holders and COL Applicants referencing the amended API 000 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 of9 Attachment 1 10 CFR 50.46 Annual Repo11 for the API000 Design Ce11ification AOR, 2020 Model Year

© 2021 Westinghouse Electric Company LLC All Rights Resen1ed

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 (0 F) Reference# Note#

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

1. Evaluation of Pellet Thennal 2012 Conductivity Degradation and 139 2 Peaking Factor Bumdown
2. Revised Heat Transfer 2013 11 3 Multiplier Distributions
3. farnr in Burst Strain Application 23 4 2013 AOR + ASSESSME TS 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 repo1ting year in which this assessment was included.

REFERENCES 1 APP-GW-GL-700, Revision 19, "APl000 Design Control Document," June 2011.

2 LTR-LIS-12-288, "h1forrnation Regarding the Evaluation of Fuel Pellet The1mal Conductivity Degradation and Peaking Factor Bumdown Including Analysis Input 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 + ASSESSMENTS PCT = 1634.0 °F
  • The licensee should determil1e 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 2011.

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 of9 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 Resen1ed

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. farnr 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 rep01ting 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 Report for the HOTSPOT Burst Strain Enor Co1Tection,"

Januaiy 2014.

4 LTR-LIS-18-393 , "Update to the Vogtle Units 3 & 4 LBLOCA and SBLOCA 10 CFR 50.46 PCT Stmuna1y 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 Smmnary 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) and 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) The 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: CU1Tent PCT (0 F) Rt'ference # Note#

ANALYSIS-OF-RECORD 1099 1 AOR + ASSESSME TS PCT= 1099.0 °F REFERENCES 1 ND-19-1142 (ML19273A953), "Automatic Depressurization 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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