ND-19-1127, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.01.04 (Index Number 519)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.01.04 (Index Number 519)

ML19290G511
Person / Time
Site:	Vogtle
Issue date:	10/17/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-1127
Download: ML19290G511 (7)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel OCT 1 7 2019 Docket Nos.: 52-025 52-026 ND-19-1127 10CFR 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 2.5.01.04 [Index Number 5191 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 15, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.01.04

[Index Number 519] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. 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. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.01.04 [Index Number 519]

MJY/SBB/sfr

U.S. Nuclear Regulatory Commission ND-19-1127 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. 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 Regulatory 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 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1127 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., CDS 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, Batch Bingham

U.S. Nuclear Regulatory Commission ND-19-1127 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-1127 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.01.04[Index Number 519]

U.S. Nuclear Regulatory Commission ND-19-1127 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

4. The DAS hardware and any software are developed using a planned design process which provides for specific design documentation and reviews during the following life cycle Stages:

a) Development phase for hardware and any software b) System test phase c) Installation phase The planned design process also provides for the use of commercial off-the-shelf hardware and software.

Inspections/Tests/Analvses Inspection will be performed of the process used to design the hardware and any software.

Acceptance Criteria A report exists and concludes that the process defines the organizational responsibilities, activities, and configuration management controls for the following:

a) Documentation and review of hardware and any software.

b) Performance of tests and the documentation of test results during the system test phase.

c) Performance of tests and inspections during the installation phase.

The process also defines requirements for the use of commercial off-the-shelf hardware and software.

ITAAC Completion Description An inspection is performed to verify that the Diverse Actuation System (DAS) hardware and software are developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages: Development phase for hardware and any software, system test phase and Installation phase. The planned design process also provides for the use of commercial off-the-shelf hardware and software.

DAS is developed using defined processes, activities and organizational responsibilities per APP-DAS-GEH-001 (Reference 1). The defined processes are further incorporated into the vendor's processes and procedures that include the software and hardware development life cycle (i.e., development phase, hardware and software requirements, design, manufacturing, factory testing, and delivery).

U.S. Nuclear Regulatory Commission ND-19-1127 Enclosure Page 3 of 4 An inspection of the vendor's processes and procedures used to develop and test the hardware and software was performed, and It was concluded that the processes define the organizational responsibilities, activities, and configuration management controls for documentation and review of hardware and any software, performance of tests and the documentation of test results during the system test phase, and requirements for the use of commercial off-the-shelf hardware and software. Technical report APP-GW-GLR-623,"API000 Design Certification ITAAC 2.5.01.04: Diverse Actuation System Design Process Technical Report"(Reference 2) documents the results of the inspection and includes references to vendor processes and procedures that define each of the Acceptance Criteria.

An inspection of processes used for the performance of tests and inspections during the installation phase is performed. The results of this inspection are documented in References 3 and 4 for Unit 3 and Unit 4, respectively. DAS cabinets are installed and inspected in accordance with 26139-000-4MP-T81C-N3301,"Electrical Equipment Installation"(Reference 5). The DAS is designed using the Advanced Logic System (ALS) platform. The platform is based on Field Programmable Gate Array(FPGA)technology that does not utilize software-based controls and does not require software loading on site. Software installation for the DAS service unit is per SV3-GW-GCW-0125(Reference 6) and SV4-GW-GCW-0126 (Reference 7) for Units 3 and 4, respectively. Post-installation tests are performed per the component test procedure B-GEN-ITPCI-002(Reference 8) after completion of the system energization.

The results of the above DAS inspections conclude that the processes define the organizational responsibilities, activities, and configuration management controls for documentation and review of hardware and any software, performance of tests and the documentation of test results during the system test phase, requirements for the use of commercial off-the-shelf hardware and software, and requirements for the use of commercial off-the-shelf hardware and software.

References 1 through 8 are available for NRC inspection as part of the ITAAC 2.5.01.04 Unit 3 and 4 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 all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-19-1127 Enclosure Page 4 of 4 References ^available for NRG inspection^

1. APP-DAS-GEH-001,"API000 Diverse Actuation System Design Process"

2. APP-GW-GLR-623,"API000 Design Certification ITAAC 2.5.01.04: Diverse Actuation System Design Process Technical Report"

3. 2.5.01.04-U3-SumRep-Rev X "Unit 3 Diverse Actuation System Installation Phase Process Summary Report"

4. 2.5.01.04-U4-SumRep-Rev X "Unit 4 Diverse Actuation System Installation Phase Process Summary Report

5. 26130-000-4MP-T81C-N3301,"Electrical Equipment Installation"

6. SV3-GW-GCW-0125,"API000 Vogtle Unit 3 Diverse Actuation System (DAS) ASU PC Update and Application Ver 1.11 Installation"

7. SV4-GW-GCW-0126,"API000 Vogtle Unit 4 Diverse Actuation System (DAS) ASU PC Update and Application Ver 1.11 Installation"

8. B-GEN-ITPCI-002,"Diverse Actuation System (DAS) Cabinets"

9. ITAAC 2.5.01.04-U3-CP-Rev0,"ITAAC Completion Package"

10. ITAAC 2.5.01.04-U4-CP-Rev0,"ITAAC Completion Package"

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