ND-19-1104, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.08a.ii (Index Number 540)

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Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.08a.ii (Index Number 540)
ML19267A219
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 09/24/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.5.02.08a.ii, ND-19-1104
Download: ML19267A219 (10)
v • d • e


Text

Michael J. Yox 7825 River Road Sk. Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel SEP 2 il 2019 Docket Nos.: 52-025 52-026 ND-19-1104 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 2.5.02.08a.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 September 16, 2019, Vogtle 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-17-1362

[ML17244A076], dated Aug. 24, 2017. This resubmittal supersedes ND-17-1362 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. Yo>

Regulatory Affairs Dj/ector Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-19-1104 Page 2 of 3

Enclosure:

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

MJY/TMM/sfr 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 Ms. K. M. Stacy 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

U.S. Nuclear Regulatory Comnnlssion ND-19-1104 Page 3 of 3 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Orlani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corlettl 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-1104 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-19-1104 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.08a.li [Index Number 540]

U.S. Nuclear Regulatory Commission ND-19-1104 Enclosure Page 2 of 7 ITAAC Statement Desion 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 MGR.

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

Inspections/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), AP1000 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 Section 7.2. Test results are documented in API000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Report(Reference 4)and API000 Protection and Safety Monitoring System System Integration Test Integrated System Validation Test Report(References 5 and 6).

FAT (References 4, 5, and 6) verifies the functionality of the API000 PMS prior to shipment to the site and includes Channel Integration Testing (CIT) and System Integration Testing (SIT) of

U.S. Nuclear Regulatory Commission ND-19-1104 Enclosure Page 3 of 7 RMS. The GIT is used to isolate the RMS to a single division in order to facilitate performance of the Reactor Trip, Engineered Safety Features, Integrated Logic Processor Component Logic, Qualified Data Processing System (QDPS), Nuclear Instrumentation System, Input/Output Channel Accuracy, Cabinet Indications and Status, and Plant Control System Hardware Interface functionality. The CIT confirms the functionality of all intra-cabinet and intra-division cabling and communication. The SIT confirms system-level performance and the functionality of all inter-cabinet and inter-division cabling and communication via the Time Response, Maintenance and Test Panel Displays and Safety Panel Displays, and Abnormal Conditions testing.

Reference 4 documents the results of the CIT using the API000 PMS QDPS test function with software installed to test PMS channels. References 5 and 6 document the results of the SIT performed on the API000 PMS SIT Integrated System Validation function with software installed. The overall SIT Integrated System Validation test verified that the integration of the released application software with the production hardware meets all applicable requirements associated with API000 PMS SIT Integrated System Validation functions.

The FAT results demonstrate proper integration of PMS cabinets within a channel and their interconnections, correct hardware and software integration, and appropriate communications within and between PMS cabinets to verify applicable plant parameters generate visual alerts that identify challenges to critical safety functions for the correct logic and values. The FAT results confirm that the PMS inputs and outputs, logic and functions with software installed function correctly to provide for the visual alerts, as identified in Attachment A.

During the test, the process 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. Attachment B provides a listing of test cases used to verify correct visual alerts.

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 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 (References 7 and 8). References 7 and 8 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 and installation for hardware changes (references 9 and 10) and software changes (Reference

11) to determine if additional testing is needed for the as-built system.

The completed Unit 3 and Unit 4 FAT (References 4, 5, and 6), FCNs(References 7 and 8)and regression test results (References 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 1 through 11 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).

U.S. Nuclear Regulatory Commission ND-19-1104 Enclosure Page 4 of 7 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(avaiiabie for NRG 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"(WQ SCNXXXXXX)
8. SV4-GW-GCW-300, Field Change Notice "API000 Vogtle Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1"(WQ SCNYYYYYY)
9. GIC-AP1OOO-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"(Unit 3)
10. GIC-AP1 OOO-HEDS-19-001, Rev. 0"Regression Testing Analysis for Vogtle Unit 4 Protection and Safety Monitoring System (PMS) Baseline 8.2 to 8.4 Hardware Modifications Performed at Site"(Unit 4)
11. APP-PMS-T2R-050, API000 Protection and Safety Monitoring System Channel Integration Test Integrated System Validation 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"

U.S. Nuclear Regulatory Commission ND-19-1104 Enclosure Page 5 of 7 Attachment A Excerpt from COL Appendix 0 Table 2.5.2-5

^Description AiertO)

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-19-1104 Enclosure Page 6 of 7 Attachment A(continued)

^Description *Alert

RCS Subcooling Yes RGB 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.

U.S. Nuclear Regulatory Commission ND-19-1104 Enclosure Page 7 of 7 Attachment B Factory Acceptance Test - Test Cases Description Test Report Test Case Neutron Flux APP-PMS-T2R-010 TPS04-13 Step 9 Neutron Flux Doubling APP-PMS-T2R-010 TPS04-27.2: Step 2 Startup Rate APP-PMS-T2R-010 TPS04-13 Step 1 Reactor Coolant System (RCS) Pressure APP-PMS-T2R-010 TPS04-14: Step 15 Wide-range Cold Leg Temperature APP-PMS-T2R-010 TPS04-14: Step 5 RCS Cooidown Rate Compared to the Limit APP-PMS-T2R-010 TPS04-34: Step 6 Based on RCS Pressure Wide-range Cold Leg Temperature APP-PMS-T2R-010 TPS04-35, Step 26 Compared to the Limit Based on RCS Pressure Change of RCS Temperature by more than APP-PMS-T2R-010 TPS04-15.2, Step 24 5°F in the last 10 minutes Containment Water Level APP-PMS-T2R-010 TPS04-22, Step 13 Containment Pressure APP-PMS-T2R-010 TPS04-22, Step 8 Pressurizer Water Level APP-PMS-T2R-010 TPS04-28, Step 12 Reactor Vessel-Hot Leg Water Level APP-PMS-T2R-010 TPS04-15.2, Step 24 Core Exit Temperature APP-PMS-T2R-010 TPS04-29, Step 7 RCS Subcooling APP-PMS-T2R-010 TPS04-29, Step 2 RCS Cold Overpressure Limit APP-PMS-T2R-010 TPS04-34, Step 6 IRWST Water Level APP-PMS-T2R-010 TPS04-16, Step 7 PRHR Flow APP-PMS-T2R-010 TPS04-21, Step 8 PRHR Outlet Temperature APP-PMS-T2R-010 TPS04-17, Step 4 PRHR HX Inlet Isolation and Control Valve APP-PMS-T2R-010 TPS04-23 Status IRWST to Normal Residual Heat Removal APP-PMS-T2R-010 TPS04-19, Step 3 System (RNS)Suction Valve Status Containment Area High-range Radiation APP-PMS-T2R-010 TPS04-18.1, Step7 Level

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