ND-18-1500, CFR 50.46 Thirty Day Report

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CFR 50.46 Thirty Day Report
ML18352A785
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 12/18/2018
From: Aughtman A
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-18-1500
Download: ML18352A785 (11)
v • d • e


Text

Southern Nuclear Operating Company, Inc.

3535 Colonnade Parkway Birmingham, AL 35243 December 18, 2018 Docket Nos.: 52-025 ND-18-1500 52-026 10 CFR 50.46(a)(3)(ii)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4 10 CFR 50.46 Thirty Day Report Ladies and Gentlemen:

The purpose of this letter is to provide a required report in accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," for the Vogtle Electric Generating Plant (VEGP) Units 3 and 4 combined licenses (COLs), License Nos. NPF-91 and NPF-92, respectively.

On December 21, 2017, Southern Nuclear Operating Company (SNC) submitted license amendment request (LAR)-17-043 [ML18029A243]. The requested amendment proposed changes to UFSAR Tier 2, COL Appendix A (Technical Specifications) and COL Appendix C (and plant-specific Tier 1) information with regard to the containment pressure analysis. SNC subsequently supplemented and revised the requested amendment on September 28, 2018

[ML18271A188] in response to NRC requests for additional information.

On November 7, 2018, the NRC approved the changes proposed in LAR-17-043 as Amendment No. 147 [ML18289A745] for Vogtle Unit 3 and Amendment No. 146 for Vogtle Unit 4 [ML18289A748]. SNC incorporated these amendments into the Vogtle 3&4 Licensing Basis via licensing document change request (LDCR)-2017-158 on December 6, 2018.

Analyses performed by Westinghouse Electric Company (WEC) have shown that the design changes associated with LAR-17-043 result in an estimated peak clad temperature (PCT) increase for the large break loss-of-coolant accident (LBLOCA) transient and the small break loss-of-coolant accident (SBLOCA) transient.

The attachment to this letter provides the background, affected evaluation model, estimated effect of the changes, and an updated LBLOCA and SBLOCA PCT rackup sheets. The attachment refers to LAR-79, LAR-114 and LAR-133, which are Westinghouses LAR numbers for SNC LAR-17-043, LAR-16-012 and LAR-17-009, respectively.

A full SBLOCA reanalysis is scheduled to be performed and implemented in an upcoming LAR.

The LAR will incorporate cumulative design changes, including those from LAR-16-012 and LAR-17-009, and update the licensing basis accordingly. This LAR is currently scheduled to be submitted in the second quarter of 2019.

U.S. Nuclear Regulatory Commission ND-18-1500 Page 2 of 4 Southern Nuclear Operating Company's (SNC's) COLs for VEGP Units 3 and 4 incorporate by reference Appendix D to 10 CFR Part 52, and thus, utilize the Peak Cladding Temperature (PCT) calculations performed by WEC. Therefore, the PCT calculations performed by WEC are applicable to the VEGP Units 3 and 4 COLs.

This letter contains no regulatory commitments. This letter has been reviewed and determined not to contain security-related information.

If there are any questions regarding this report, please contact Ms. Amy Chamberlain at (205) 992-6361.

Respectfully submitted, (4~~

Amy G. Aughtman Director, Nuclear Development Licensing Southern Nuclear Operating Company

Attachment:

10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3 & 4 LBLOCA and SBLOCA Analyses of Record

U.S. Nuclear Regulatory Commission ND-18-1500 Page 3 of 4 cc:

Southern Nuclear Operating Company / Georgia Power Company Mr. S. E. Kuczynski (w/o enclosures)

Mr. D. G. Bost (w/o enclosures)

Mr. M. D. Meier (w/o enclosures)

Mr. D. H. Jones (w/o enclosures)

Mr. J. B. Klecha Mr. G. Chick Mr. D. L. McKinney (w/o enclosures)

Mr. T. W. Yelverton (w/o enclosures)

Mr. B. H. Whitley Ms. C. A. Gayheart Mr. C. R. Pierce Ms. A. G. Aughtman Mr. D. L. Fulton Mr. M. J. Yox Mr. C. T. Defnall Mr. J. Tupik Mr. W. A. Sparkman Ms. A. C. Chamberlain Ms. A. L. Pugh Mr. E. Riffle Ms. K. Roberts Document Services RTYPE: VND.LI.L00 File AR.01.02.06 Nuclear Regulatory Commission Mr. W. Jones (w/o enclosures)

Ms. J. Dixon-Herrity Mr. C. Patel Ms. J. M. Heisserer Mr. B. Kemker Mr. G. Khouri Ms. S. Temple Mr. F. Brown Mr. C. J. Even Mr. A. Lerch Mr. S. Walker State of Georgia Mr. R. Dunn

U.S. Nuclear Regulatory Commission ND-18-1500 Page 4 of 4 Oglethorpe Power Corporation Mr. M. W. Price Ms. A. Whaley Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Mr. L. Oriani (w/o enclosures)

Mr. C. Churchman (w/o enclosures)

Mr. M. Corletti Mr. M. L. Clyde Mr. D. Hawkins Mr. J. Coward Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. A. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham NDDocumentinBox@duke-energy.com, Duke Energy Mr. S. Franzone, Florida Power & Light

Southern Nuclear Operating Company ND-18-1500 Attachment Vogtle Electric Generating Plant (VEGP) Units 3 and 4 10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3&4 LBLOCA and SBLOCA Analyses of Record (This Attachment consists of 7 pages, including this cover page.)

ND-18-1500 Attachment 10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3 & 4 LBLOCA and SBLOCA Analyses of Record LARGE BREAK LOCA DESIGN CHANGE REBASELINE EVALUATION

Background

Numerous AP1000 plant design changes have occurred since the AP1000 Core Reference Report large break loss-of-coolant accident (LBLOCA) analysis was performed [1]. The design changes impacting the LBLOCA analysis included numerous passive core cooling system (PXS),

vessel model, containment pressure, reactor coolant system (RCS), and secondary system changes.

These items represent changes in plant configuration or associated set points, distinguished from an evaluation model change in Section 4 of WCAP-13451 [2].

Affected Evaluation Model(s) 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect An LBLOCA rebaseline evaluation was performed using the latest code versions with model corrections to determine an updated limiting peak cladding temperature (PCT) considering the AP1000 plant design changes up to May 5, 2014. The updated evaluation resulted in a PCT penalty of 54°F against the AP1000 plant Core Reference Report analysis [1].

References

1. WCAP-17524-P-A, Revision 1, AP1000 Core Reference Report, May 2015.
2. WCAP-13451, Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting, October 1992.

AP1000 is a trademark or registered trademark of Westinghouse Electric Company LLC, its affiliates and/or its subsidiaries in the United States of America 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.

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ND-18-1500 Attachment 10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3 & 4 LBLOCA and SBLOCA Analyses of Record SMALL BREAK LOCA DESIGN CHANGE REBASELINE ANALYSIS

Background

Numerous AP1000 plant design changes have occurred since the AP1000 Core Reference Report small break loss-of-coolant accident (SBLOCA) analysis was performed [1]. The design changes impacting the SBLOCA analysis included numerous passive core cooling system (PXS),

automatic depressurization system (ADS), reactor coolant system (RCS), containment pressure, and secondary system changes.

These items represent changes in plant configuration or associated set points, distinguished from an evaluation model change in Section 4 of WCAP-13451 [2].

Affected Evaluation Model(s) 1985 Westinghouse Advanced Plant Small Break LOCA Evaluation Model with NOTRUMP.

Estimated Effect An SBLOCA rebaseline analysis was performed using the latest code versions with model corrections to determine an updated limiting peak cladding temperature (PCT) considering the AP1000 plant design changes up to August 4, 2014. The updated analysis resulted in a PCT penalty of 243.5°F against the AP1000 plant Core Reference Report analysis [1].

References

1. WCAP-17524-P-A, Revision 1, AP1000 Core Reference Report, May 2015.
2. WCAP-13451, Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting, October 1992.

AP1000 is a trademark or registered trademark of Westinghouse Electric Company LLC, its affiliates and/or its subsidiaries in the United States of America 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.

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ND-18-1500 Attachment 10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3 & 4 LBLOCA and SBLOCA Analyses of Record 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: Current PCT Reference

(°F) # Note #

ANALYSIS-OF-RECORD 1936 1 (a)

Delta PCT Reference Reporting ASSESSMENTS* (°F) # Note # Year**

1. Revised Heat Transfer Multiplier Distributions 11 2 2013
2. Error in Burst Strain Application 23 3 2013
3. Design Change Rebaseline Evaluation 54 4, 5 (b) 2018 AOR + ASSESSMENTS PCT = 2024 °F
  • The licensee should determine the reportability of these assessments pursuant to 10 CFR 50.46.
    • The Reporting Year refers to the annual reporting year in which this assessment was included.

REFERENCES 1 WCAP-17524-P-A, Revision 1, AP1000 Core Reference Report, May 2015.

2 LTR-LIS-13-357, AP1000 Plant 10 CFR 50.46 Report for Revised Heat Transfer Multiplier Distributions, July 2013.

3 LTR-LIS-14-41, AP1000 Plant 10 CFR 50.46 Report for the HOTSPOT Burst Strain Error Correction, January 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.

© 2018 Westinghouse Electric Company LLC All Rights Reserved 4 of 7

ND-18-1500 Attachment 10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3 & 4 LBLOCA and SBLOCA Analyses of Record 5 ND-17-2074 (ML18029A243), Containment Pressure Analysis (LAR-17-043), December 2017. Approved by NRC November 7, 2018 as Amendments 147 (VEGP Unit 3) and 146 (VEGP Unit 4) (ML18289A742).

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) The design change rebaseline evaluation used current code versions and accounts for design changes up to May 5, 2014 and plant model error corrections.

© 2018 Westinghouse Electric Company LLC All Rights Reserved 5 of 7

ND-18-1500 Attachment 10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3 & 4 LBLOCA and SBLOCA Analyses of Record 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: Current PCT Reference

(°F) # Note #

ANALYSIS-OF-RECORD 663.5 1 Delta PCT Reference Reporting ASSESSMENTS* (°F) # Note # Year**

1. NOTRUMP Bubble Rise/Drift Flux Model Inconsistencies 32 2 2014
2. LAR-114 Evaluation 13 3, 4, 5 (a) 2016
3. LAR-133 Evaluation 144 6, 7 (b) 2018
4. Design Change Rebaseline Evaluation 243.5 8, 9 (c) 2018 AOR + ASSESSMENTS PCT = 1096 °F
  • The licensee should determine the reportability of these assessments pursuant to 10 CFR 50.46.
    • The Reporting Year refers to the annual reporting year in which this assessment was included.

REFERENCES 1 WCAP-17524-P-A, Revision 1, AP1000 Core Reference Report, May 2015.

2 LTR-LIS-15-5, Updates to the AP1000 Plant SBLOCA 10 CFR 50.46 PCT Rackups, January 2015.

3 LTR-LIS-16-144, Update to the AP1000 Plant SBLOCA 10 CFR 50.46 PCT Rackups for LAR-114, January 2017.

4 LTR-LIS-17-59, AP1000 Plant 10 CFR 50.46 Annual Notification and Reporting for 2016, March 2017.

© 2018 Westinghouse Electric Company LLC All Rights Reserved 6 of 7

ND-18-1500 Attachment 10 CFR 50.46 30-Day Report Content for the AP1000 Vogtle Units 3 & 4 LBLOCA and SBLOCA Analyses of Record 5 ND-16-0984 (ML16207A340), Automatic Depressurization System (ADS) Stage 2, 3 & 4 Valve Flow Area Changes and Clarifications (LAR-16-012), July 2016. Approved by NRC December 29, 2016 as Amendment 62 (ML16357A640).

6 LTR-LIS-16-429, Update of the AP1000 Plant SBLOCA 10 CFR 50.46 PCT Rackups for LAR-133, January 2017.

7 ND-17-0443 (ML17090A209), PXS/ADS Line Resistance Changes (LAR-17-009), March 2017. Approved by NRC February 28, 2018 as Amendments 111 (VEGP Unit 3) and 110 (VEGP Unit 4) (ML18026A565).

8 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.

9 ND-17-2074 (ML18029A243), Containment Pressure Analysis (LAR-17-043), December 2017 Approved by NRC November 7, 2018 as Amendments 147 (VEGP Unit 3) and 146 (VEGP Unit 4) (ML18289A742).

NOTES:

(a) The LAR-114 evaluation assesses the impact of reduced automatic depressurization system (ADS) Stage 2, 3, and 4 flow areas described in design change proposals (DCPs) 5051 and 5054.

(b) The LAR-133 evaluation assesses the impact of updated ADS Stages 1 - 4 and In-Containment Refueling Water Storage Tank (IRWST) line resistances described in DCPs 4903 and 5138.

(c) The design change rebaseline analysis used current code versions and accounts for design changes up to August 4, 2014 and plant model error corrections.

© 2018 Westinghouse Electric Company LLC All Rights Reserved 7 of 7

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