ND-19-0830, 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)

ML19193A203
Person / Time
Site:	Vogtle
Issue date:	07/12/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0830
Download: ML19193A203 (9)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Southern Nuclear Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel JUL 1 2 2019 Docket Nos.: 52-025 52-026 ND-19-0830 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 2.5.02.09d [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 July 8, 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.

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 2.5.02.09d [Index Number 548]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0830 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. R.G. West(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. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.LOO 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 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0830 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse 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, TetraTech NU8, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GD8 Associates, Inc.

Mr. 8. Roetger, Georgia Public 8en/ice 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-19-0830 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-19-0830 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.09d [Index Number 548]

U.S. Nuclear Regulatory Commission ND-19-0830 Enclosure Page 2 of 6 ITAAC Statement Desion Commitment 9.d) The RMS provides the interlock functions identified in Table 2.5.2-7.

I nsoections/Tests/Analvses 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 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 Section 7.2.

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 ARP-RMS-T2R-009(References 5 and 6).

Attachment B provides a listing of test cases used to test the interlocks.

Software installation and testing are performed on site to verify that the cabinets are intact and functional in accordance with Units 3 and 4 Field Change Notification (FCN) xxxx (References 7 and 8). Automated diagnostics further confirm the physical properties of the as-built RMS. A regression analysis (i.e., change evaluation) is performed post delivery and installation for hardware and software changes to determine if additional testing is needed for the as-built system.

U.S. Nuclear Regulatory Commission ND-19-0830 Enclosure Page 3 of 6 The completed Unit 3 and Unit 4 factory (references 5 and 6)and regression test results (References 7 and 8)confirm that PMS provides the interlock functions identified in Table 2.5.2-7.

References 1 through 8 are available for NRG inspection as part of the ITAAC 2.5.02.09d 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.

References favaiiabie for NRG inspection)

1. WCAP-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. Unit 3 Field Change Notice "PMS Software"

8. Unit 4 Field Change Notice "PMS Software"

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

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

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

U.S. Nuclear Regulatory Commission ND-19-0830 Enclosure Page 4 of 6 Attachment A COL Appendix 0 Table 2.5.2-7 Table 2.5.2-7 RMS Interlocks RNS Suction Valves PRHR Heat Exchanger Inlet Isolation Valve GMT Cold Leg Balance Line Isolation Valves Containment Vacuum Relief Isolation Valves

U.S. Nuclear Regulatory Commission ND-19-0830 Enclosure Page 5 of 6 Attachment B Factory Acceptance Test - Test Cases RNS Suction Valves Tag Test Report Test Case RNS-VOOIA PMS-T2R-009 TPS03D-01.46 TPS03D-02.3 RNS-VOOIB PMS-T2R-009 TPS03D-01.47 TPS03D-02.4 RNS-V002A PMS-T2R-009 TPS03B-01.46 TPS03B-02.4 RNS-V002B PMS-T2R-009 TPS03B-01.47 TSP03B-02.5 PRHR Heat Exchanger Inlet Isolation Valve Tag Test Report Test Case PXS-VlOl PMS-T2R-009 TPS03A-01.36 PMS-T2R-009 TPS03A-07.17 PMS-T2R-008 TPS02A-04.1 PMS-T2R-008 TPS02A-08.1 PMS-T2R-008 TPS02A-08.2 PMS-T2R-008 TPS02A-08.3 PMS-T2R-008 TPS02A-08.4 GMT Cold Leg Balance Line Isolation Valves Condition Test Report Test Case P-12 PMS-T2R-008 TPS02A-04.2 PXS-T2R-100 PXS_V002A_lnit_Cond PXS_V002A_PA_lnput PXS_V002A_PA_0 PXS_V002B_lnit_Cond PXS_V002B_PA_lnput PXS V002A PA 0

U.S. Nuclear Regulatory Commission ND-19-0830 Enclosure Page 6 of 6 Containment Vacuum Relief Isolation Valves Tag Procedure Test Case VFS-V800A PMS-T2R-009 TPS03A-01.33 TPS03A-02.4 PMS-T2R-008 TPS03A-07.14 TPS02A-27 VFS-V800B PMS-T2R-009 TPS03C-01.22 TPS03C-02.3 TPS03C-07.il PMS-T2R-008 TPS02C-27