ND-19-1115, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.11 (Index Number 550)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.11 (Index Number 550)

ML19290G397
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-19-1115
Download: ML19290G397 (7)

Text

V Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel OCT 1 7 2019 Docket Nos.: 52-025 52-026 ND-19-1115 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 2.5.02.11 [Index Number 5501 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 2.5.02.11

[Index Number 550] 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 Difector Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.11 [Index Number 550]

MJY/SBB/sfr

U.S. Nuclear Regulatory Commission ND-19-1115 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKlnney (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 Reoulatorv Commission Mr. W. Jones (w/o enclosures)

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

U.S. Nuclear Regulatory Commission ND-19-1115 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse 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. 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-19-1115 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-1115 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.11 [Index Number 550]

U.S. Nuclear Regulatory Commission ND-19-1115 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment

11. The RMS hardware and software is developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages:

a) Not used b) System definition phase c) Hardware and software development phase, consisting of hardware and software design and implementation d) System integration and test phase e) Installation phase Inspections/Tests/Analvses Inspection will be performed of the process used to design the hardware and software.

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

a) Not used.

b) Specification of functional requirements.

c) Documentation and review of hardware and software.

d) Performance of system tests and the documentation of system test results, including a response time test performed under maximum CPU loading to demonstrate that the PMS can fulfill its response time criteria.

e) Performance of installation tests and inspections.

ITAAC Completion Description An inspection is performed to verify that the Protection and Safety Monitoring System (PMS) hardware and software is developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages: System definition phase, hardware and software development phase (consisting of hardware and software design and implementation), system integration and test phase, and installation phase.

PMS is developed by the vendor using defined processes, activities and organizational responsibilities per WCAP-16096-P (Reference 1) as supplemented by WCAP-15927-P (Reference 2). The defined processes are further incorporated into the vendor's processes and procedures that include the software and hardware development life cycle (i.e., requirements, design, manufacturing, factory testing, independent verification and validation, and delivery).

U.S. Nuclear Regulatory Commission ND-19-1115 Enclosure Page 3 of 4 An inspection of the vendor's processes and procedures used to design the hardware and software was performed, and it was concluded that the processes define the organizational responsibilities, activities, and configuration management controls for specification of functional requirements, documentation and review of hardware and software, and performance of system tests and the documentation of system test results, including a response time test performed under maximum CPU loading to demonstrate that the PMS can fulfill its response time criteria.

Technical report APP-GW-GLR-620 "API000 Design Certification ITAAC 2.5.02.11: Protection and Safety Monitoring System Design Process Technical Report"(Reference 3) 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 installation tests and inspections is performed. The results of this inspection are documented in References 4 and 5 for Unit 3 and Unit 4, respectively. Hardware (e.g., PMS cabinets) are installed and inspected in accordance with 26139-000-4MP-T81C-N3301,"Electrical Equipment Installation"(Reference 6). Software installation and regression analysis are per SV3-GW-GCW-300(Reference 7) and SV4-GW-GCW-308(Reference 8)for Units 3 and 4, respectively. Post-installation tests are performed per the component test procedure B-GEN-ITPCI-001 (Reference 9).

The results of the above PMS inspections conclude that the process defines the organizational responsibilities, activities, and configuration management controls for the following: specification of functional requirements, documentation and review of hardware and software, performance of system tests and the documentation of system test results, including a response time test performed under maximum CPU loading to demonstrate that the PMS can fulfill its response time criteria, and performance of installation tests and inspections.

References 1 through 9 are available for NRG inspection as part of the ITAAC 2.5.02.11 Unit 3 and 4 Completion Packages (References 10 and 11).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company 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-19-1115 Enclosure Page 4 of 4 References(available for NRC inspection)

1. WCAP-16096-P "Software Program Manual"

2. WCAP-15927-P "Design Process for API000 Common Q Safety Systems"

3. APP-GW-GLR-620"API000 Design Certification ITAAC 2.5.02.11: Protection and Safety Monitoring System Design Process Technical Report"

4. 2.5.02.11-U3-SumRep-Rev X "Unit 3 PMS Installation Tests and Inspections Process Summary Reporf

5. 2.5.02.11-U4-SumRep-Rev X "Unit 4 PMS Installation Tests and Inspections Process Summary Report"

6. 26130-000-4MP-T81C-N3301,"Electrical Equipment Installation"

7. SV3-GW-GCW-300, Vogtle Unit 3 API000 f^MS Initial Software Installation - Software Release 8.7.0.1"

8. SV4-GW-GCW-308, Vogtle Unit 3 API000 PMS Initial Software Installation - Software Release 8.7.0.1"

9. B-GEN-ITPCI-001 "PMS Cabinets"

10. ITAAC 2.5.02.11-U3-CP-RevO,"ITAAC Completion Package"

11. ITAAC 2.5.02.11-U4-CP-RevO,"ITAAC Completion Package"

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