ND-19-1263, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.01.04e (Index Number 588)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.01.04e (Index Number 588)

ML19329D491
Person / Time
Site:	Vogtle
Issue date:	11/25/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1263
Download: ML19329D491 (12)

Text

Southern Nuclear Michael J. Vox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 NOV 2 5 2019 Docket Nos.: 52-025 52-026 ND-19-1263 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.6.01.04e [Index Number 5881 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of Nov 22, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.6.01.04e

[Index Number 588] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.6.01.04e [Index Number 588]. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by the guidance described in NEI-08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.

All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant 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 Dir^fctor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.6.01.04e [Index Number 588]

MJY/KM/sfr

U.S. Nuclear Regulatory Commission ND-19-1263 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. 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. Page Mr. P. Martino Mr. 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. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Requlatorv Commission M . W. Jones (w/o enclosures)

M . F. D. Brown M . C. P. Patel M . G. J. Khouri Ms. S. E. Temple M . N. D. Karlovich M . A. Lerch M . C. J. Even M . B. J. Kemker Ms. N. C. Coovert M . C. Welch M . J. Gaslevic M . V. Hall M . G. Armstrong Ms. T. Lamb M M. Webb M T. Fredette M C. Weber M S. Smith M C. Santos Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1263 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-19-1263 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Pian for Uncompleted ITAAC 2.6.01.04e[Index Number 588]

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 2 of 9 ITAAC Statement Design Commitment 4.a) The ECS provides the capability for distributing non-Class 1E ac power from onsite sources (ZOS)to nonsafety-reiated loads listed in Table 2.6.1-2.

4.e) The ECS provides two loss-of-voltage signals to the onsite standby power system (ZOS), one for each diesel-backed 6900 Vac switchgear bus.

4.f) The ECS provides a reverse-power trip of the generator circuit breaker which is blocked for at least 15 seconds following a turbine trip.

5. Controls exist in the MCR to cause the circuit breakers identified in Table 2.6.1-3 to perform the listed functions.

6. Displays of the parameters identified in Table 2.6.1-3 can be retrieved in the MCR.

Inspections/Tests/Analvses Tests will be performed using a test signal to confirm that an electrical path exists for each selected load listed in Table 2.6.1-2 from an ECS-ES-1 or ECS-ES-2 bus. Each test may be a single test or a series of overlapping tests.

Tests on the as-built ECS system will be conducted by simulating a loss-of-voltage condition on each diesel-backed 6900 Vac switchgear bus.

Tests on the as-built ECS system will be conducted by simulating a turbine trip signal followed by a simulated reverse-power condition. The generator circuit breaker trip signal will be monitored.

Tests will be performed to verify that controls in the MCR can operate the circuit breakers identified in Table 2.6.1-3.

Inspection will be performed for retrievability of the displays identified in Table 2.6.1-3 in the MCR.

Acceptance Criteria A test signal exists at the terminals of each selected load.

A loss-of-voltage signal Is generated when the loss-of-voltage condition is simulated.

The generator circuit breaker trip signal does not occur until at least 15 seconds after the simulated turbine trip.

Controls in the MCR cause the circuit breakers identified in Table 2.6.1-3 to operate.

Displays identified in Table 2.6.1-3 can be retrieved in the MCR.

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 3 of 9 ITAAC Completion Description Testing and inspection are performed to verify that the Main AC Power System (ECS) performs the following:

• The ECS provides the capability for distributing non-Class 1E ac power from onsite sources (ZOS)to nonsafety-related loads listed in Combined License(COL)Table 2.6.1-2 (Attachment A).

• The ECS provides two loss-of-voltage signals to the onsite standby power system (ZOS),

one for each diesel-backed 6900 Vac switchgear bus.

• The ECS provides a reverse-power trip of the generator circuit breaker which is blocked for at least 15 seconds following a turbine trip.

• Controls exist in the MCR to cause the circuit breakers identified in COL Table 2.6.1-3 (Attachment B)to perform the listed functions.

• Displays of the parameters identified in COL Table 2.6.1-3(Attachment B)can be retrieved in the MCR.

A test sional exists at the terminals of each selected load.

Testing is performed in accordance with Unit 3 and Unit 4 component test package work orders SNC921177 and SNCYYYYYY (References 1 and 2), preoperational tests 3/4-ZOS-ITPP-501 (References 9 and 10), and preoperational tests 3/4-RCS-ITPP-504(References 11 and 12) to verify that each load identified in Combined License(COL)Table 2.6.1-2 (Attachment A) is powered from the ECS-ES-1 6900 Vac Switchgear Bus 1 or the ECS-ES-2 6900 Vac Switchgear Bus 2.

References 9 and 10 ensure ECS-ES-1 and 2 are energized from the standby diesel generator by paralleling each diesel to its respective ES bus and loading the diesel to full load. References 1 and 2 test each load listed in Attachment A and verifies that each load is de-energized, the power supply breaker(s) are then closed, and the load is verified to be energized. References 11 and 12 ensure the pressurizer heaters (listed in Attachment A) are de-energized and during RCS pressure control testing, it is verified that the heaters are energized. This will constitute a series of overlapping tests to test all components. The combined test results confirm that a test signal exists at the terminals of each selected load.

A loss-of-voltaae signal is generated when the loss-of-voltage condition is simulated.

Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3/4-ZOS-ITPP-503(References 3 and 4)to verify that the ECS provides two loss-of-voltage signals to the onsite standby power system (ZOS), one for each diesel-backed 6900 Vac switchgear bus. The loss-of-voltage protection circuit for each switchgear bus and the diesel generator starting control circuitry are monitored. A loss-of-voltage condition is simulated at each diesel-backed 6900 Vac switchgear to initiate the loss-of voltage condition. The loss-of-voltage condition is verified to initiate switchgear supply breakers opening, switchgear load breakers opening and the starting of the respective standby generator. The completed test results confirm a loss-of-voltage signal is generated when the loss-of-voltage condition is simulated on each switchgear bus.

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 4 of 9 The generator circuit breaker trip signal does not occur until at least 15 seconds after the simulated turbine trip.

Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3/4-ZAS-ITPP-501 (References 5 and 6) with the turbine tripped. Test equipment is utilized to simulate a reverse power condition to the reverse power relay(RY1) and a timer is started. The timer is stopped when the reverse power relay output to the generator lockout relay (86SEQ1)is actuated and the time is recorded. The generator circuit breaker trip circuit contacts are verified to close when the 86SEQ1 relay actuates. This testing is repeated for the RY2 and 86SEQ2 relays. The time delay for the Unit 3 RY1 relay is XX sec and YY sec for RY2. The time delay for the Unit 4 RY1 is XX sec and YY sec for RY2. The test results confirm that the generator circuit breaker trip signal does not occur until at least 15 seconds after the simulated turbine trip.

Controls in the MCR cause the circuit breakers identified in Table 2.6.1-3 to operate.

Testing is performed in accordance with Unit 3 and Unit 4 Component Test Work Packages, SNCXXXXXX and SNCYYYYYY (References 7 and 8)to verify controls in the MCR operate to cause the 6900 Vac Switchgear Bus 1 and 6900 Vac Switchgear Bus 2 circuit breakers listed in Combined License (COL)Table 2.6.1-3(Attachment B)to operate. The control functions of each circuit breaker are tested and verified by inspection. The test results confirm that controls in the MCR can operate the circuit breakers identified in Attachment B.

Displavs identified in Table 2.6.1-3 can be retrieved in the MCR.

An inspection is performed in accordance with Unit 3 and Unit 4 Component Test Work Packages, SNCXXXXXX and SNCYYYYYY (References 7 and 8)for ECS and ZAS (Main Generator System) which visually confirms that when each of the displays of parameters identified in Attachment B is summoned at an MCR workstation, the summoned plant parameter appears on a display monitor at that MCR workstation.

References 1 - 8 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC Completion Packages (References 9 and 10).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References(available for NRC inspection)

1. SNC921177,"ECS Component Power Verification Test- ITAAC; SV3-2.6.01.04e Item 4.a"

2. SNCYYYYYY,"ECS Component Power Verification Test- ITAAC: SV4-2.6.01.04e Item 4.a"

3. 3-ZOS-ITPP-503,"Onsite Standby Power System - Load Sequencing Tests"

4. 4-ZOS-ITPP-503,"Onsite Standby Power System - Load Sequencing Tests"

5. 3-ZAS-ITPP-501,"Main Generation Preoperational Test Procedure"

6. 4-ZAS-ITPP-501,"Main Generation Preoperational Test Procedure"

7. SNCXXXXXX,"Main AC Power System Control and Indication Verifications - ITAAC: SV3-2.6.01.04e Items 5 and 6"

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 5 of 9

8. SNCYYYYYY,"Main AC Power System Control and Indication Verifications - ITAAC: SV4-2.6.01.04e Items 5 and 6"

9. 3-ZOS-ITPP-501,"Onsite Standby Power System" 10.4-ZOS-ITPP-501,"Onsite Standby Power System" 11.3-RCS-ITPP-504,"Reactor Coolant System Pressurizer Pressure, Level, And Spray Precore Hot Functional Test Preoperational Test Procedure" 12.4-RCS-ITPP-504,"Reactor Coolant System Pressurizer Pressure, Level, And Spray Precore Hot Functional Test Preoperational Test Procedure" 13.2.6.01.04e-U3-CP-Rev 0, ITAAC Completion Package 14.2.6.01.04e-U4-CP-Rev 0, ITAAC Completion Package

15. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 6 of 9 Attachment A COL Appendix 0 Table 2.6.1-2 Load Description Power Source Load Center Transformers EK-11, EK-12, EK-13, EK-14 ZOS-MG-02A Diesel Oil Transfer Module Enclosure A Electric Unit Heater ZOS-MG-02A Diesel Oil Transfer Module Enclosure A Fan ZOS-MG-02A Class 1E Division A Regulating Transformer ZOS-MG-02A Class IE Division C Regulating Transformer ZOS-MG-02A Diesel Generator Fuel Oil Transfer Pump 1A ZOS-MG-02A Diesel Generator Room A Building Standby Exhaust ZOS-MG-02A Fans 1A and 2A Diesel Generator Service Module A Air Handling Unit ZOS-MG-02A (AHU)01A Fan Startup Feedwater Pump A ZOS-MG-02A Service Water Pump A ZOS-MG-02A Service Water Cooling Tower Fan A ZOS-MG-02A MCR/Control Support Area (CSA)AHU A ZOS-MG-02A Supply and Return Fans Divisions A/C Class 1E Electrical Room AHU A ZOS-MG-02A Supply and Return Fans Divisions B/D Class 1E Electrical Room AHU D Supply ZOS-MG-02A and Return Fans Air-cooled Chiller Pump 2 ZOS-MG-02A Component Cooling Water Pump 1A ZOS-MG-02A Air-cooled Chiller 2 ZOS-MG-02A Chemical and Volume Control System (CVS) Makeup ZOS-MG-02A Pump 1A CVS Pump Room Unit Cooler Fan A ZOS-MG-02A Normal Residual Heat Removal System (RNS)Pump 1A ZOS-MG-02A RNS Pump Room Unit Cooler Fan A ZOS-MG-02A Equipment Room AHU Supply and Return Fans ZOS-MG-02A VXS-MA-01A/02A

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 7 of 9 Attachment A (Cent.)

COL Appendix 0 Table 2.6.1-2 Load Description Power Source Switchgear Room A AHU Supply and Return Fans ZOS-MG-02A VXS-MA-05A/06A Non-1 E Battery Charger EDS1-DC-1 ZOS-MG-02A Non-1 E Battery Room A Exhaust Fan ZOS-MG-02A Non-1 E Battery Charger EDS3-DC-1 ZOS-MG-02A Class 1E Division A Battery Charger 1 (24-hour) ZOS-MG-02A Class 1E Division C Battery Charger 1 (24-hour) ZOS-MG-02A Class 1E Division C Battery Charger 2(72-hour) ZOS-MG-02A Divisions A/C Class 1E Battery Room Exhaust Fan A ZOS-MG-02A Supplemental Air Filtration Unit Fan A ZOS-MG-02A Backup Group 4A Pressurizer Heaters ZOS-MG-02A Spent Fuel Cooling Pump 1A ZOS-MG-02A Load Center Transformers EK-21, EK-22, EK-23, EK-24 ZOS-MG-02B Diesel Oil Transfer Module Enclosure B Electric Unit Heater ZOS-MG-02B Diesel Oil Transfer Module Enclosure B Fan ZOS-MG-02B Class IE Division B Regulating Transformer ZOS-MG-02B Class IE Division D Regulating Transformer ZOS-MG-02B Diesei Generator Fuel Oil Transfer Pump IB ZOS-MG-02B Diesel Generator Room B Building Standby Exhaust ZOS-MG-02B Fans 1B and 2B Diesel Generator Service Module B AHU 01B Fan ZOS-MG-02B Startup Feedwater Pump B ZOS-MG-02B Service Water Pump B ZOS-MG-02B Service Water Cooling Tower Fan B ZOS-MG-02B MCR/CSA AHU B Supply and Return Fans ZOS-MG-02B Divisions B/D Class 1E Electrical Room AHU B Supply and ZOS-MG-02B Return Fans

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 8 of 9 Attachment A (Cont.)

COL Appendix 0 Table 2.6.1-2 Load Description Power Source Divisions A/C Class 1E Electrical Room AHU C Supply and ZOS-MG-02B Return Fans Air-cooled Chiller Pump 3 ZOS-MG-02B Component Cooling Water Pump 1B ZOS-MG-02B Air-cooled Chiller 3 ZOS-MG-02B CVS Makeup Pump 1B ZOS-MG-02B CVS Pump Room Unit Cooler Fan B ZOS-MG-02B RNS Pump IB ZOS-MG-02B RNS Pump Room Unit Cooler Fan B ZOS-MG-02B Equipment Room B AHU Supply and Return Fans ZOS-MG-02B VXS-MA-01B/02B Switchgear Room B AHU Supply and Return Fans ZOS-MG-02B VXS-MA-05B/06B Non-IE Battery Charger EDS2-DC-1 ZOS-MG-02B Non-IE Battery Charger EDS4-DC-1 ZOS-MG-02B Non-IE Battery Room B Exhaust Fan ZOS-MG-02B Class 1E Division B Battery Charger 1 (24-hour) ZOS-MG-02B Class 1E Division B Battery Charger 2(72-hour) ZOS-MG-02B Class 1E Division D Battery Charger 1 (24-hour) ZOS-MG-02B Divisions B/D Class 1E Battery Room Exhaust Fan B ZOS-MG-02B Supplemental Air Filtration Unit Fan B ZOS-MG-02B Backup Group 4B Pressurizer Heaters ZOS-MG-02B Spent Fuel Cooling Pump 1B ZOS-MG-02B

U.S. Nuclear Regulatory Commission ND-19-1263 Enclosure Page 9 of 9 Attachment B COL Appendix 0 Table 2.6.1-3 Equipment Tag No. Display Control Function 6900 V Switchgear Bus 1 ECS-ES-1 Yes Yes (Bus voltage, breaker (Breaker open/close) position for all breakers on bus) 6900 V Switchgear Bus 2 ECS-ES-2 Yes Yes (Bus voltage, breaker (Breaker open/close) position for all breakers on bus)

Unit Auxiliary ZAS-ET-2A No Yes Transformer A (Secondary Voltage)

Unit Auxiliary ZAS-ET-2B No Yes Transformer B (Secondary Voltage)

Reserve Auxiliary ZAS-ET-4A No Yes Transformer A (Secondary Voltage)

Reserve Auxiliary ZAS-ET-4B Yes No Transformer B (Secondary Voltage)