ND-19-1197, Report of UFSAR Chapter 14 Changes to Initial Test Program in Accordance with License Condition 2.D.(7)(a)

Report of UFSAR Chapter 14 Changes to Initial Test Program in Accordance with License Condition 2.D.(7)(a)

ML19294A097
Person / Time
Site:	Vogtle
Issue date:	10/21/2019
From:	Whitley B Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-1197
Download: ML19294A097 (5)

Text

B. H. Whitley Southern Nuclear Director Operating Company, Inc.

Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 Tel 205.992.7079 October 21, 2019 Docket No.: 52-025 52-026 ND-19-1197 10 CFR 52.97(c)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Mr. Ho Nieh Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4 Report of UFSAR Chapter 14 Changes to Initial Test Program In Accordance with License Condition 2.D.(7)(a)

Ladies and Gentlemen:

In accordance with license condition 2.D.(7)(a) of the Vogtle Electric Generating Plant (VEGP)

Units 3 and 4 Combined Licenses, Numbers NPF-91 and NPF-92, respectively, Southern Nuclear Operating Company (SNC) is required to report, within 30 days, a change made to the Initial Test Program described in Updated Final Safety Analysis Report (UFSAR) Chapter 14, in accordance with 10 CFR 50.59(d) or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures.

On October 1, 2019, SNC approved Licensing Document Change Request (LDCR) 2019-094, changing the Initial Test Program described in the VEGP Units 3&4 UFSAR, to remove duplicate data, ensure consistency within the licensing basis and align test descriptions with system design as follows: (1) removes the two-of-four reactor coolant pump (RCP) coastdown test from the reactor coolant system pre-critical flow coastdown tests (Subsection 14.2.10.1.18); (2) removes the cold condition control rod tests before first criticality (Subsections 14.2.10.1.13 and 14.2.10.1.14); (3) clarifies the use of temporary neutron detectors as optional during initial fuel load testing (Subsections 14.2.10.1.3, 14.2.10.1.4, and 14.2.10.1.5); and (4) removes the test requirement for low capacity chilled water system (VWS) pump discharge pressure monitoring (Subsection 14.2.9.2.9).

On October 4, 2019, SNC approved LDCR-2019-086, changing the Initial Test Program described in VEGP Units 3&4 UFSAR Subsections 14.2.9, Preoperational Test Descriptions, and 14.2.10, Startup Test Procedures, to reflect the VEGP Units 3&4 plant design changes, clarifications to performance criteria, and modifications to the testing based on lessons learned from startup testing programs at currently operating plants. These changes impact the following UFSAR Subsections:

U.S. Nuclear Regulatory Commission ND-19-1197 Page 2 of 5

1. UFSAR Subsection 14.2.9.1.8, Control Rod Drive System,

2. UFSAR Subsection 14.2.10.1.2, Reactor Systems Sampling for Fuel Loading,

3. UFSAR Subsection 14.2.10.1.3, Fuel Loading Instrumentation and Neutron Source Requirements,

4. UFSAR Subsection 14.2.10.1.4, Inverse Count Rate Ratio Monitoring for Fuel Loading, and UFSAR Subsection 14.2.10.1.5, Initial Fuel Loading,

5. UFSAR Subsection 14.2.10.1.6, Post-Fuel Loading Precritical Test Sequence,

6. UFSAR Subsection 14.2.10.1.7, Incore Instrumentation System Precritical Verification,

7. UFSAR Subsection 14.2.10.1.8, Resistance Temperature Detectors-Incore Thermocouple Cross Calibration,

8. UFSAR Subsection 14.2.10.1.9, Nuclear Instrumentation System Precritical Verification,

9. UFSAR Subsection 14.2.10.1.10, Setpoint Precritical Verification,

10. UFSAR Subsection 14.2.10.1.11, Rod Control System,

11. UFSAR Subsection 14.2.10.1.12, Rod Position Indication System,

12. UFSAR Subsection 14.2.10.1.13, Control Rod Drive Mechanism,

13. UFSAR Subsection 14.2.10.1.16, Process Instrumentation Alignment,

14. UFSAR Subsection 14.2.10.1.19, Pressurizer Spray Capability and Continuous Spray Flow Verification,

15. UFSAR Subsection 14.2.10.1.20, Feedwater Valve Stroke Test,

16. UFSAR Subsection 14.2.10.2.3, Nuclear Instrumentation System Verification,

17. UFSAR Subsection 14.2.10.2.4, Post-Critical Reactivity Computer Checkout,

18. UFSAR Subsection 14.2.10.3.5, Bank Worth Measurement,

19. UFSAR Subsection 14.2.10.4.3, Nuclear Instrumentation System,

20. UFSAR Subsection 14.2.10.4.5, Startup Adjustments of Reactor Control Systems,

21. UFSAR Subsection 14.2.10.4.6 Rod Cluster Control Assembly Out of Bank Measurements (First Plant Only),

22. UFSAR Subsection 14.2.10.4.7, Axial Flux Difference Instrumentation Calibration,

23. UFSAR Subsection 14.2.10.4.12, Steam Dump Control System,

24. UFSAR Subsection 14.2.10.4.13, Steam Generator Level Control System,

25. UFSAR Subsection 14.2.10.4.14, Radiation and Effluent Monitoring Systems,

26. UFSAR Subsection 14.2.10.4.15, Ventilation Capability,

27. UFSAR Subsection 14.2.10.4.19, Reactor Power Control System,

28. UFSAR Subsection 14.2.10.4.23, Hot Full Power Boron Endpoint,

29. UFSAR Subsection 14.2.10.4.24, Plant Trip from 100 Percent Power, and

30. UFSAR Subsection 14.2.10.4.26, Loss of Offsite Power.

These departures from Tier 2 information in the UFSAR (which include the plant-specific DCD) were evaluated in accordance with 10 CFR 52 Appendix D Section VIII, and it was determined that these changes did not involve changes to Tier 1 information, Tier 2* information, or the Technical Specifications. The evaluations also determined that prior NRC approval for these departures was not required.

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

Should you have any questions, please contact Mr. Mark Humphrey at (205) 992-6452.

U.S. Nuclear Regulatory Commission ND-19-1197 Page 3 of 5 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 21st of October 2019.

Respectfully submitted, Brian H. Whitley Director, Regulatory Affairs Southern Nuclear Operating Company

U.S. Nuclear Regulatory Commission ND-19-1197 Page 4 of 5 cc:

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

Mr. P. P. Sena III (w/o enclosures)

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

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

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. M. Ronnlund Mr. D. L. Fulton Mr. M. J. Yox Mr. C. T. Defnall Mr. J. Tupik Ms. S. Agee Ms. A. C. Chamberlain Mr. M. Humphrey Mr. N. Kellenberger Mr. E. Riffle Ms. K. Roberts Mr. J. Haswell Mr. D. T. Blythe 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 Mr. B. Kemker Mr. G. Khouri Ms. S. Temple Mr. F. Brown Mr. C. J. Even Mr. A. Lerch Mr. S. Walker Mr. N.D. Karlovich Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Ms. K. P. Carrington Mr. P.J. Heher Mr. M. Webb

U.S. Nuclear Regulatory Commission ND-19-1197 Page 5 of 5 State of Georgia Mr. R. Dunn 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. T. Rubenstein (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