ND-19-1538, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.09d (Index Number 548)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.09d (Index Number 548)

ML20002B904
Person / Time
Site:	Vogtle
Issue date:	01/02/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1538
Download: ML20002B904 (7)

Text

A Michael J. Yox 7325 River Road SOUtnBrn NUCIBdr Regulatory Affairs Director Vogtle 3 a. 4 Waynesboro, GA 30830 706-848-6459 tel JAN 0 2 2020 Docket Nos.: 52-025 52-026 ND-19-1538 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 2.5.02.09d (Index Number 5481 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 18, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.02.09d

[Index Number 548] 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.

Southern Nuclear Operating Company(SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.5.02.09d [Index Number 548] ND-19-0830

[ML19193A203], dated July 12, 2019. This resubmittal supersedes ND-19-0830 in its entirety.

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 Affaira'Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.09d [Index Number 548]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-1538 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. 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 Regulatory 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 Mr. C. Santos Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1538 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Eiectric 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 NU8, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GD8 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-1538 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-1538 Enclosure Vogtle Electric Generating Piant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.09d [Index Number 548]

U.S. Nuclear Regulatory Commission ND-19-1538 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 9.d) The RMS provides the interlock functions identified in Table 2.5.2-7.

i nspections/Tests/Anaivses An operational test of the as-built RMS will be performed using real or simulated test signals.

Acceptance Criteria Appropriate RMS output signals are generated as the interlock conditions are changed.

ITAAC Completion Description Testing is performed to verify that the Protection and Safety Monitoring System (RMS) provides interlock functions identified in Combined License Appendix C Table 2.5.2-7 (Attachment A).

ITAAC 2.5.02.09d is completed as a combination of:

• Factory Acceptance Test- Functional testing of interlocks

• Site software installation and regression test- Hardware and software integration verification and testing of post system delivery changes The Factory Acceptance Testing (FAT)follows the guidance of NEI 08-01 Section 9.4 (Reference 16)for the as-built tests to be performed at other than the final installed location.

The FAT was performed in accordance with RMS Software Program Manual WCAR-16096 (Reference 1), RMS Test Plan ARR-RMS-T5-001 (Reference 2) and applicable Codes and Standards described in Vogtle 3 and 4 UFSAR Chapter 7(Reference 15).

The FAT included testing of RMS inputs and outputs, logic, and functionality. During this test, the initial condition for the test scenarios was established and confirmed that the interlocks actuate as appropriate for the interlocks described in Vogtle 3&4 UFSAR Chapter 7, Section 7.6. During the test, the process parameters were simulated and adjusted to create applicable interlock conditions, RMS outputs were monitored, and it was confirmed that the interlocks work as designed, in accordance with RMS Channel Integration Test procedures ARR-RMS-T1R-008 and ARR-RMS-T1R-009(References 3 and 4). The results of the testing are documented in the FAT test reports ARR-RMS-T2R-008 and ARR-RMS-T2R-009 (References 5 and 6).

Additional hardware and software installation and associated inspections and testing are performed on-site to verify that the cabinets are intact and functional in accordance with Units 3 and 4 for applicable Field Change Notifications(FCNs) API000 Vogtle Unit 3 RMS Initial Software Installation - Software Release 8.7.0.1 and API000 Vogtle Unit 4 RMS Initial Software Installation - Software Release 8.7.0.1, and B-GEN-ITRCI-001 (References 7, 8, and 9).

References 7, 8, and 9 include steps that confirm and document successful software load and further confirm the physical properties of the as-built RMS. A regression analysis (i.e., change

U.S. Nuclear Regulatory Commission ND-19-1538 Enclosure Page 3 of 4 evaluation) is performed for hardware changes (References 10 and 11) and software changes (Reference 12) to determine if additional testing is needed for the as-built system.

The completed Unit 3 and Unit 4 FAT test reports (references 5 and 6), FGNs (References 7 and 8), B-GEN-ITPCI-001 (Reference 9), and regression test results (References 10 through

12) confirm that appropriate PMS output signals are generated as the interlock conditions are changed.

References 5 through 12 are available for NRG inspection as part of the ITAAG 2.5.02.09d Unit 3 and 4 Completion Packages(References 13 and 14).

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

References(available for NRC inspection)

1. WGAP-16096 "Software Program Manual for Common Q Systems" Revision 4A

2. APP-PMS-T5-001 "API000 Protection and Safety Monitoring System Test Plan"

3. APP-PMS-T1P-008 "API000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Procedure"

'4. APP-PMS-T1P-009 "API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Procedure"

5. APP-PMS-T2R-008 "API000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Report"

6. APP-PMS-T2R-009"API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Report"

7. SV3-GW-GCW-300, Field Change Notice "API000 Vogtle Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1"(WO SCNXXXXXX)

8. SV4-GW-GCW-XXX, Field Change Notice "API000 Vogtle Unit 4 PMS Initial Software Installation - Software Release 8.7.0.1"(WO SCNYYYYYY)

9. B-GEN-ITPCI-001,"PMS CABINETS"

10. GIC-AP1000-HEDS-19-001, Rev. 0"Regression Testing Analysis for Vogtle Unit 3 Protection and Safety Monitoring System (PMS) Baseline 8.2 to 8.4 Hardware Modifications Performed at Site"

11. GIC-AP1000-HEDS-YY-XXX, Rev. X "Regression Testing Analysis for Vogtle Unit 4 Protection and Safety Monitoring System (PMS) Baseline X.X to X.X Hardware Modifications Performed at Site"(YY-XXX is the Year-Letter #)

12. SV0-PMS-T2R-050,"API000 Protection and Safety Monitoring System Channel Integration Test Integrated System Validation Test Report"

13. ITAAC 2.5.02.09d-U3-CP-Rev0, ITAAC Completion Package

14. ITAAC 2.5.02.09d-U4-CP-Rev0, ITAAC Completion Package

15. Vogtle Electric Generating Plant(VEGP) Units 3 and 4 Updated Final Safety Analysis Report(UFSAR)

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

U.S. Nuclear Regulatory Commission ND-19-1538 Enclosure Page 4 of 4 Attachment A COL Appendix 0 Table 2.5.2-7 Table 2.5.2-7 PMS Interlocks RNS Suction Valves PRHR Heat Exchanger inlet isolation Valve GMT Gold Leg Balance Line Isolation Valves Containment Vacuum Relief Isolation Valves