^ ,t 1. I I Michael J. Yox 7825 River RoadRegulatory Affairs Director Waynesboro, GA 30830Southern NuclearVogtle 3 & 4 706-848-6459 tel

OCT 2 8 2019Docket Nos.: 52-025

52-026

ND-19-1047

10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory CommissionDocument Control Desk

Washington, DC 20555-0001

Southern Nuclear Operating CompanyVogtle Electric Generating Plant Unit 3 and Unit 4

Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load

Item 2.5.03.02 (Index Number 5551

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRCthat as of October 25, 2019, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.03.02 [IndexNumber 555] has not been completed greater than 225-days prior to initial fuel load. The Enclosuredescribes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a laterdate, provide additional notifications for ITAAC that have not been completed 225-days prior toinitial fuel load.

This notification is informed by the guidance described in NEI 08-01, Industry Guideline for theITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in RegulatoryGuide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which requiredinspections, tests, or analyses have not been performed or have been only partially completed. AllITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will besubmitted to NRC to support the Commission finding that all acceptance criteria are met prior toplant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Vox

Regulatory Affairs Director Vogtle 3 & 4

Enclosure: Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4Completion Plan for Uncompleted ITAAC 2.5.03.02 [Index Number 555]

MJY/VK/sfr

U.S. Nuclear Regulatory CommissionND-19-1047

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To:

Southern Nuclear Operating Company/ Georgia Power CompanyMr. Peter P. Sena III (w/o enclosures)Mr. D. L. McKinney (w/o enclosures)Mr. M. D. Meier (w/o enclosures)Mr. D. H. Jones (w/o enclosures)Mr. G. Chick

Mr. M. PageMr. M. J. Yox

Mr. A. S. Parton

Ms. K. A. Roberts

Mr. T. G. Petrak

Mr. C. T. Defnall

Mr. C. E. Morrow

Mr. J. L. HughesMr. S. LeightyMs. A. C. Chamberlain

Mr. J. C. Haswell

Document Services RTYPE: VND.LI.L06

File AR.01.02.06

cc:

Nuclear Requlatorv Commission

M

M

M

M

Ms. S. E. TempleM

M

M

M

M

M

M

M

M

M

M

M

W. Jones (w/o enclosures)F. D. Brown

C. P. Patel

G. J. Khourl

N. D. Karlovich

A. Lerch

C. J. Even

B. J. Kemker

Ms. N. C. Coovert

. C. Welch

. J. Gaslevic

. V. Hall

. G. ArmstrongMs. T. Lamb

M. Webb

T. Fredette

C. Weber

S. Smith

Qqlethorpe Power Corporation

Mr. R. B. Brinkman

Mr. E. Rasmussen

U.S. Nuclear Regulatory CommissionND-19-1047

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Municipal Electric Authority of Georgia

Mr. J. E. Fuller

Mr. 8. M. Jackson

Daiton Utilities

Mr. T. Bundros

Westinqhouse Electric Company. LLC

Dr. L. Oriani (w/o enclosures)Mr. D. 0. Durham (w/o enclosures)Mr. M. M. Corletti

Ms. L. G. Iller

Mr. Z. 8. HarperMr. J. L. Coward

Other

Mr. J. E. Hosier, Bechtel Power CorporationMs. L. Matis, Tetra Tech NUS, Inc.Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.Mr. 8. Roetger, Georgia Public Service CommissionMs. 8. W. Kernlzan, Georgia Public Service CommissionMr. K. C. Greene, Troutman SandersMr. 8. Blanton, Batch Bingham

U.S. Nuclear Regulatory CommissionND-19-1047 Enclosure

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Southern Nuclear Operating CompanyND-19-1047

Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4Completion Plan for Uncompleted ITAAC 2.5.03.02 [Index Number 555]

U.S. Nuclear Regulatory CommissionND-19-1047 Enclosure

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ITAAC Statement

Design Commitment

2. The PLS provides control interfaces for the control functions listed in Table 2.5.3-1.

Inspections/T ests/Analvses

An operational test of the system will be performed using simulated input signals. Systemoutputs or component operations will be monitored to determine the operability of the controlfunctions.

Acceptance Criteria

The PLS provides control interfaces for the control functions listed in Table 2.5.3-1.

ITAAC Completion Description

Testing is performed to verify the Plant Control System (PLS) provides control interfaces for thecontrol functions listed in VEGP Combined License (COL) Appendix C Table 2.5.3-1(Attachment A).

Testing is performed in accordance with the following Unit 3 and Unit 4 preoperational testprocedures 3/4-PLS-ITPP-520 (References 1 and 2), 3/4-PLS-ITPP-507 (References 3 and 4),3/4-RCS-ITPP-504 (References 5 and 6), 3/4-SGS-ITPP-502 (References 7 and 8), 3/4-MSS-ITPP-502 (References 9 and 10), 3/4-CVS-ITPP-502 (References 11 and 12). This testingverifies PLS operability of the control functions listed in Attachment A.

References 1 and 2 conduct preoperational testing of the Digital Rod Position Indication (DRPI)System control interface with the PLS. The DRPI System is placed in a normal configurationand the Westinghouse DRPI Simulator Test Box is connected at existing connectors on theIntegrated Head Package (IMP) Connector Panel. The test demonstrates that DRPIcommunicates with the PLS and indicates the correct rod position at the Main Control RoomWorkstation when simulated using the Simulator Test Box for each of the 69 control rods.

The completed test results (References 1 and 2) satisfy the Acceptance Criteria for PLS toprovide control interfaces for Reactor Rod Position functions.

References 3 and 4 conduct preoperational testing of the Digital Rod Control System (DRCS)System during Hot Functional Testing (HPT), near full temperature and pressure, todemonstrate Reactor Power and Rapid Power Reduction control functions using the PLS controlinterface.

The test demonstrates Reactor Power control rod withdrawal, insertion, and overlap movementby simulating a varying Tavg-Tref for temperature mismatch conditions and then verifying thecorresponding Rod Bank Speed withdrawal and insertion signals. Additionally, testing isperformed by inserting an axial offset condition and verifies the Axial Offset (AO) rods respondproperly to negative and positive axial offsets.

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The test also demonstrates Rapid Power Reduction with control rods fully withdrawn, thenselecting rapid power reduction banks for a rod sequence and simulating forced point values toobtain and verify the selected control rod banks release.

The completed test results (References 3 and 4) satisfy the Acceptance Criteria for PLS toprovide control interfaces for Reactor Power and Rapid Power Reduction functions.

References 5 and 6 conduct preoperational testing of Reactor Coolant System (RCS)Pressurizer (PZR) pressure control interface functions during HPT, near full temperature andpressure.

PZR pressure spray valves are placed in manual and fully opened. During the pressurizerpressure decrease, the control and backup heaters are verified to energize and fully load toattempt to maintain pressurizer pressure. The pressurizer spray valves are then closed andplaced in automatic. Pressurizer pressure is monitored and verified to return to setpoint. Thenthe pressurizer spray valves are placed in manual, closed and the pressurizer backup heatersare placed in manual and turned on. Pressurizer pressure and heater current are monitored andwhen pressurizer pressure increases to system normal operating pressure, the pressurizermaster controller is placed in automatic and the spray valves are placed in automatic.Pressurizer pressure is monitored and verified to return to setpoint.

The completed test results (References 5 and 6) satisfy the Acceptance Criteria for PLS toprovide control interface for Pressurizer pressure functions.

References 7 and 8 conduct preoperational testing of the Main and Startup Feedwater System(FWS) during HPT, near full temperature and pressure, to demonstrate the Steam GeneratorSystem (SGS) Feedwater control for steam generator (SGs) using the Startup FeedwaterControl Valves (SFCV).

SG feedwater control test for each SG is performed with the SFCV initially in manual and theSG level is raised above the setpoint. Then the SFCV is placed in Auto, and the SG level ismonitored and verified to return to setpoint. This is reperformed with the SFCV in manual andSG level is lowered and then SFCV is placed in Auto, and SG level is verified to return tosetpoint.

The completed test results (References 7 and 8) satisfy the Acceptance Criteria for PLS toprovide control interface for SG Feedwater control function.

References 9 and 10 conduct preoperational testing of the Main Steam System turbine bypassvalves (Steam Dumps) during HFT, near full temperature and pressure, to demonstrate steamdump valves operate properly in the steam pressure mode, and the Tavg mode to verify PLScontrol interface functions.

The test initially isolates the steam dumps and demonstrates that in the Tavg mode theappropriate steam dump valves open on simulated Tavg High 1 and on simulated Tavg High 2conditions to control the RCS temperature. The steam dumps are unisolated and placed in thesteam pressure mode, then the setpoint is changed and the valves are monitored to control andincrease steam pressure at the new setpoint.

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The completed test results (References 9 and 10) satisfy the Acceptance Criteria for PLS toprovide control interface for Steam Dump valve control.

References 11 and 12 conduct preoperational testing of the Chemical and Volume ControlSystem during HFT, near full temperature and pressure, to demonstrate the Pressurizer WaterLevel control interface functions with the PLS.

Testing to demonstrate the automatic makeup function for PZR level control is performed withReactor Makeup Control System (RCMS) and the Makeup Pump in automatic. Manual Letdownto lower PZR Level is initiated, an automatic makeup start on Pressurizer low level is verified,and letdown is secured. Pressurizer level is monitored and when the makeup stop level isreached, makeup is verified to shut down and the makeup flow control valves close.

Testing to demonstrate the automatic letdown function for PZR level control is performed withRCMS in automatic. A manual makeup is initiated, pressurizer level is monitored, and whenletdown initiates on high pressurizer level, makeup is secured and returned to automatic.Pressurizer level is monitored and when the PZR level is below setpoint letdown is verified toautomatically stop and the letdown valves close.

The completed test results (References 11 and 12) satisfy the Acceptance Criteria for PLS toprovide control interface for Pressurizer level control functions.

The combination of all the successfully performed preoperational tests and correspondingresults confirm that the PLS provides control interfaces for the control functions listed in Table2.5.3-1.

References 1 through 12 are available for NRC inspection as part of Unit 3 and Unit 4 ITAACCompletion Packages (Reference 13 and 14).

List of ITAAC Findings

In accordance with plant procedures for ITAAC completion. Southern Nuclear OperatingCompany (SNC) performed a review of all findings pertaining to the subject ITAAC andassociated corrective actions. This review found there are no relevant ITAAC findingsassociated with this ITAAC.

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References (available for NRG inspection)

1. 3-PLS-ITPP-520, "Digital Rod Position indication System Preoperationai Test Procedure"2. 4-PLS-iTPP-520, "Digital Rod Position indication System Preoperationai Test Procedure"3. 3-PLS-iTPP-507, "Digital Rod Control System Hot Functional Preoperationai Test

Procedure"

4. 4-PLS-ITPP-507, "Digital Rod Control System Hot Functional Preoperationai TestProcedure"

5. 3-RCS-ITPP-504, "Reactor Coolant System Pressurizer Pressure, Level, And SprayPrecore Hot Functional Test Preoperationai Test Procedure"

6. 4-RCS-ITPP-504, "Reactor Coolant System Pressurizer Pressure, Level, And SprayPrecore Hot Functional Test Preoperationai Test Procedure"

7. 3-SGS-ITPP-502, "Steam Generator System Hot Functional Preoperationai TestProcedure"

8. 4-SGS-ITPP-502, "Steam Generator System Hot Functional Preoperationai TestProcedure"

9. 3-MSS-ITPP-502, "Main Steam System Precore Hot Functional Test Procedure"10.4-MSS-ITPP-502, "Main Steam System Precore Hot Functional Test Procedure"11.3-CVS-ITPP-502, "Chemical and Volume Control System Pre-core Hot Functional Test

Preoperationai Test Procedure"12.4-CVS-ITPP-502, "Chemical and Volume Control System Pre-core Hot Functional Test

Preoperationai Test Procedure"13.2.5.03.02-U3-CP-Rev0, ITAAC Completion Package14.2.5.03.02-U4-CP-Rev0, ITAAC Completion Package15. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

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Attachment A

COL Appendix C Table 2.5.3-1Control Functions Supported by the PLS

Table 2.5.3-1

Control Functions Supported by the PLS

1. Reactor Power 5. Steam Generator Feedwater

2. Reactor Rod position 6. Steam Dump

3. Pressurizer Pressure 7. Rapid Power Reduction

4. Pressurizer Water Level