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{{#Wiki_filter:Westinghouse Non-Proprieta1y Class 3 DCP_NRC_003344                                                                                              Page *1 of9
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@ 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 cliteria 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- 12/31/2020) that affect the peak cladding temperature (PCT) calculations for the APl000 plant design.
As  described below, two APIO00 analyses of record (AORs) are repo1ted:
APIO00 Design Ce1tification AOR:
On December 30th, 2011 , the U.S. Nuclear Regulat01y Commission cettified an amendment to the Design Ce1tification Rule for the APl00O plant. As such, APl000 Design Control Document (DCD) Revision 19 documents the AOR for the APl000 Design Ce1tification. The limiting transient for the APl00O Design Ce1tification is the Best Estimate Large Break Loss-of-Coolant Accident (LBLOCA). Westinghouse last provided an annual rep01ting 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 remams at 2010°F and does not exceed the 10 CFR 50.46 (b)(l) acceptance crite1ion of 2200°F.
The surnmaiy of the PCT margin allocations and their bases for the APl000 Design Ce1tification AOR are provided in the Attachment 1.
APl000 Vogtle Units 3 & 4 AOR:
In addition to the AOR for the APl000 Design Ce1tification, the NRC has approved the APl0O0 Core Reference Rep01t (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 Repo1t (CRR) has also been approved for inco1poration into the Vogt.le 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 reserved.
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 of2200°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 AP1000 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 APl000 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 APl 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, APIO00 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 APl000 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                0. Weaver        - Westinghouse    M. Sheaffer    - Westinghouse E. Grant            -SNC                A. Konig        - Westinghouse    M . Barca      - Westinghouse Y. Arafeh          -SNC                K. Hosack        - Westin_ghouse    M. Patterson    - Westin_ghouse
                            <<'.) 2021 Westinghouse Electric Company LLC All Rights Reserved
 
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3                Page 3 of9 Attachment 1 10 CFR 50.46 Annual Repo1t for the APl000 Design Ce1tification AOR, 2020 Model Year
                          &#xa9; 2021 Westinghouse Electric Company LLC All Rights Resen,ed
 
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 {&deg;F)            Reference#      Note#
ANALYSIS-OF-RECORD                                1837 Delta PCT                                              Reporting ASSESSMENTS*                                    {&deg;AF)              Refe1*ence #    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. Elrnr in Burst Strain Application            23                    4                            2013 AOR + ASSESSME TS                            PCT=        2010.0 Of
* The licensee should determine the rep011ability of these assessments pmsuant to 10 CFR 50 .46.
**  The "Rep011ing Year" refers to the a1111ual reporting year in which this assessment was included.
REFERENCES 1  APP-GW-GL-700, Revision 19, "APl000 Design Control Document," June 201 I.
2  LTR-LIS-12-288, "Information Regarding the Evaluation of Fuel Pellet The1mal Conductivity Degradation and Peaking Factor Bumdown Including Analysis Input Changes for APl000 Large Break LOCA Analysis," June 2012.
3  LTR-LIS-13-357 , "APIO00 Plant IO CFR 50.46 Rep011 for Revised Heat Transfer Multiplier Distributions," July 2013 .
4  LTR-LIS- 14-41 "APIO00 Plant IO CFR 50.46 Repo11 for the HOTSPOT Burst Strain Enor Coffection,"
Janua1y 2014.
NOTES:
(a) None
                                        &#xa9; 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#
Al~YSIS-OF-RECORD                                1370                    1          (a)
Delta PCT                                            Reporting ASSESSMENTS*                                    {&deg;AF)              Reference#      Note#            Year**
: 1. Adiabatic Heat-up Calculation              264                    2            (a)            2010 AOR + ASSESSME TTS                          PCT=      1634.0 &deg;F
* The licensee should determine the rep011ability of these assessments pmsuant to 10 CFR 50.46.
**  The ''Rep011ing Year" refers to the ammal rep011ing year in which this assessment was included.
REFERENCES 1 APP-GW-GL-700, Revision 19, "APIO00 Design Control Document," June 2011.
2  LTR-LIS-10-373, "10 CFR 50.46 Repo11 for the Evaluation of APl000 SBLOCA IO-inch Transient Adiabatic Heat-up Calculation," June 2010.
NOTES:
(a) This is an adiabatic heat-up calculated PCT.
                                        &#xa9; 2021 Westinghouse Electric Company LLC All Rights Reserved
 
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3                Page 6 of9 Attachment 2 10 CFR 50.46 Annual Repo1t for the API000 Vogtle Units 3 & 4 AOR, 2020 Model Year
                          &#xa9; 2021 Westinghouse Electric Company LLC All Rights Resen,ed
 
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#
Al~YSIS-OF-RECORD                                1936                  1            (a)
Delta PCT                                            Reporting ASSESSMENTS*                                    {&deg;AF)              Reference#      Note#          Year**
I. Revised Heat Transfer                                                                          2013 11                    2 Multiplier Distributions
: 2. Elrnr 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 + ASSESSME 'TS                          PCT=        2046.0 Of
* The licensee should detennine the rep01tability of these assessments pursuant to 10 CFR 50.46.
**  The "Repo1ting Year" refers to the annual repo1ting year in which this assessment was included.
REFERENCES 1 WCAP-17524-P-A, Revision 1, "APl000 Core Reference Report," May 20 15.
2  LTR-LIS-13-357, "APl000 Plant 10 CFR 50.46 Rep01t for Revised Heat Transfer Multiplier Distributions " July 2013 .
3  LTR-LIS-14-41 , "APIO0O Plant IO CFR 50.46 Repo1t for the HOTSPOT Burst Strain Enor Con-ection,"
Januaiy 2014.
4  LTR-LIS- 18-393, "Update to the Vogtle Units 3 & 4 LBLOCA and SBLOCA IO CFR 50.46 PCT Summary Sheets for LAR-79," November 20 18.
5  ND-17-2074 (ML18029A243 ), " Containment Pressure Analysis (LAR-17-043)," December 20 17.
Approved byNRC November 7, 2018 as Amendments 147 (VEGP Un.it 3) aiid 146 (VEGP Unit 4)
(MLl 8289A742).
6  LTR-LIS- 17-39, "APIO00 Plant Suggested 10 CFR 50.46 Repo1ting Text and Updated LBLOCA PCT Summary Sheet for Evaluation of Reactor Coolant Pump (RCP) Design Cha11ges," Janua1y 2017 .
7  ND-18-1147 (ML18243A459), "Reactor Coolant System (RCS) Flow Coastdown (LAR-18-025) ," August 2018. Approved byNRC Febmaiy 25, 2019 as Amendments 155 (VEGPUnit3) and 154 (VEGPUnit4)
                                      &#xa9; 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&deg;F bias for PCT sensitivity to PRHR isolation, per Reference 1 response to CRR-008, Table 2 and Table 15.6.5-8.
(b) The design change rebaseline evaluation used cmTent code versions and accounts for design changes up to May 5, 2014 and plant model e1rnr 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). The evaluated changes include updated homologous curves and small changes to the pump rated conditions and rotor ine1tia.
                                      &#xa9; 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:      Cw.Tent PCT (0 F)          Reference#  Noh.*#
Al~YSIS-OF-RECORD                              1099 AOR + ASSESSME TS                      PCT=      1099.0 &deg;F REFERENCES 1 ND-19-1142 (ML19273A953), "Automatic Depressurization System (ADS) and Core Makeup Tank (CMT) Design Parameters (LAR-19-009)," September 20 19. Approved by NRC March 11 , 2020 as Amendments 176 (VEGP Unit 3) and 175 (VEGP Unit 4) (ML20049A721/ML20049A808).
NOTES:
(a) None
                                  &#xa9; 2021 Westinghouse Electric Company LLC All Rights Reserved}}

Revision as of 20:08, 8 September 2021

Westinghouse Electric Company LLC, 10 CFR 50.46 Annual Report for the AP1000 Plant Design
ML21090A035
Person / Time
Site: Vogtle, 05200006
Issue date: 03/24/2021
From: Harper Z
Westinghouse, Westinghouse
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCP_NRC_003344
Download: ML21090A035 (9)
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