ND-19-1558, Vogtie Electric Generating Plant Unit 3 and Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.08a.ii (Index Number 540)

Vogtie Electric Generating Plant Unit 3 and Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.08a.ii (Index Number 540)

ML19364A028
Person / Time
Site:	Vogtle
Issue date:	12/27/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.5.02.08a.ii, ND-19-1558
Download: ML19364A028 (9)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel DEC 2 7 2019 Docket Nos.: 52-025 52-026 ND-19-1558 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Controi Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initiai Fuel Load Item 2.5.02.08a.ii [index Number 5401 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 20, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.02.08a.ii [Index Number 540]

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 2.5.02.08a.ii [Index Number 540] ND-19-1104[ML19267A219],

dated September 24, 2019. This resubmittal supersedes ND-19-1104 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 Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.08a.ii [Index Number 540]

MJY/CWM/sfr

U.S. Nuclear Regulatory Commission ND-19-1558 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 Requlatorv 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. 8. 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 Oalethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1558 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-1558 Enclosure Page 1 of6 Southern Nuclear Operating Company ND-19-1558 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.08a.ii [Index Number 540]

U.S. Nuclear Regulatory Commission ND-19-1558 Enclosure Page 2 of6 ITAAC Statement Design Commitment 8.a) The RMS provides for the minimum inventory of displays, visual alerts, and fixed position controls, as identified in Table 2.5.2-5. The plant parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved in the MCR.

The fixed position controls listed with a "Yes" in the "Control" column are provided in the MCR.

Insoections/Tests/Analvses ii) An inspection and test will be performed to verify that the plant parameters are used to generate visual alerts that identify challenges to critical safety functions.

Acceptance Criteria ii) The plant parameters listed in Table 2.5.2-5 with a "Yes" in the "Alert" column are used to generate visual alerts that identify challenges to critical safety functions. The visual alerts actuate in accordance with their correct logic and values.

ITAAC Completion Description Inspection and testing are performed to verify that the Protection and Safety Monitoring System (PMS) provides visual alerts as identified in Table 2.5.2-5(Attachment A). The inspection and testing confirm that the plant parameters listed with a "Yes" in the "Alert" column are used to generate visual alerts that identify challenges to critical safety functions and that these visual alerts actuate in accordance with their correct logic and values.

ITAAC 2.5.02.08a.ii is completed by:

• Factory Acceptance Testing - Channel Integration Test and System Integration Test for visual alerts that identify challenges to critical safety functions.

• 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 (Reference 14)

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 the Software Program Manual for Common Q Systems WCAP-16096(Reference 1), API000 Protection and Safety Monitoring System Test Plan (Reference 2), API000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Procedure (Reference 3), and applicable Codes and Standards described in Vogtle 3 and 4 UFSAR Chapter 7(Reference 15).

During the FAT, the plant parameters were simulated and adjusted to create applicable alert conditions, PMS outputs were monitored, and it was confirmed that the visual alerts actuate in accordance with their correct logic and values. This testing was performed in accordance with FAT Test Procedure APP-PMS-T1P-010(Reference 3). The results of the PMS testing are documented in the FAT test reports APP-PMS-T2R-010(Reference 4). The FAT results confirm

U.S. Nuclear Regulatory Commission ND-19-1558 Enclosure Page 3 of6 that the RMS inputs and outputs, logic and installed software function correctly to provide for the visual alerts, as identified in Attachment A.

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)AP1000 Vogtle Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1 and API000 Vogtle Unit 4 PMS Initial Software Installation - Software Release 8.7.0.1 and B-GEN-ITPCI-001 (References 7, 8, and 16).

References 7, 8, and 16 include steps that confirm and document successful software load and further confirm the physical properties of the as-built PMS. A regression analysis (i.e., change evaluation) is performed post-delivery for hardware changes (references 9 and 10) and software changes(References 5, 6, and 11) if additional testing is needed for the as-built system.

The completed Unit 3 and Unit 4 FAT (Reference 4), FCNs(References 7 and 8)and regression test results (References 5, 6, 9,10, and 11) confirm that PMS plant parameters listed in Attachment A with a "Yes" in the "Alert" column are used to generate visual alerts that identify challenges to critical safety functions. These results also confirm that visual alerts actuate in accordance with their correct logic and values.

References 4 through 11 and 16 are available for NRC inspection as part of the ITAAC 2.5.02.08a.ii Unit 3 and 4 Completion Packages(References 12 and 13).

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 favailabie for NRC inspection)

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

2. APP-PMS-T5-001, Rev. 5,"API000 Protection and Safety Monitoring System Test Plan"

3. APP-PMS-T1P-010, Rev. 4,"API000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Procedure"

4. APP-PMS-T2R-010 "API000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Report," Rev. 0.

5. SV3-PMS-T2R-150-R0 "API000 Protection and Safety Monitoring System System Integration Test Integrated System Validation Test Report"

6. SV4-PMS-T2R-150-R0 "API000 Protection and Safety Monitoring System System Integration Test Integrated System Validation 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-300, Field Change Notice "API000 Vogtle Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1"(WO SCNYYYYYY)

9. 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"

U.S. Nuclear Regulatory Commission ND-19-1558 Enclosure Page 4 of6

10. GIG-API000-HEDS-XX-YYY, Rev. X "Regression Testing Analysis forVogtle 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 #)

11. SV0-PMS-T2R-050,"Vogtle API000 Protection and Safety Monitoring System Fuel Load Regression Test Report"

12. ITAAC 2.5.02.08a.ii-U3-CP-Rev0, ITAAC Completion Package

13. ITAAC 2.5.02.08a.ii-U4-CP-Rev0, ITAAC Completion Package

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

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

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

U.S. Nuclear Regulatory Commission ND-19-1558 Enclosure Page 5 of6 Attachment A

• Excerpt from COL Appendix 0 Table 2.5.2-5

^Description *Alert<^)

Neutron Flux Yes Neutron Flux Doubling Yes Startup Rate Yes Reactor Coolant System (RCS)Pressure Yes Wide-range Cold Leg Temperature Yes RCS Cooldown Rate Compared to the Limit Based on RCS Pressure Yes Wide-range Cold Leg Temperature Compared to the Limit Based on RCS Pressure Yes Change of RCS Temperature by more than 5°F in the last 10 minutes Yes Containment Water Level Yes Containment Pressure Yes Pressurizer Water Level Yes Reactor Vessel-Hot Leg Water Level Yes Core Exit Temperature Yes

1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the main control room, the visual alerts are embedded in the safety-related displays as visual signals.

U.S. Nuclear Regulatory Commission ND-19-1558 Enclosure Page 6 of6 Attachment A (continued)

• Descriptlon *Alert<^>

RCS Subcooling Yes RCS Cold Overpressure Limit Yes IRWST Water Level Yes PRHR Flow Yes PRHR HX Outlet Temperature Yes PRHR HX Inlet Isolation and Control Valve Status Yes IRWST to Normal Residual Heat Removal System (RNS)Suction Valve Status Yes Containment Area High-range Radiation Level Yes

1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the main control room, the visual alerts are embedded in the safety-related displays as visual signals.