ND-18-0830, Unit 4 - ITAAC Closure Notification on Completion of ITAAC 3.2.00.01c.ii (Index Number 742)

Unit 4 - ITAAC Closure Notification on Completion of ITAAC 3.2.00.01c.ii (Index Number 742)

ML18179A072
Person / Time
Site:	Vogtle
Issue date:	06/27/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 3.2.00.01 c.ii, ND-18-0830
Download: ML18179A072 (7)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 te!

410-474-8587 cell myox@southernco.com JUN 2 7 2018 Docket Nos.: 52-025 52-026 ND-18-0830 10CFR 52.99(c)(1)

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 ITAAC Closure Notification on Completion of ITAAC 3.2.00.01 c.ii [Index Number 7421 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)

Unit 3 and Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.2.00.01 c.ii [Index Number 742] for verifying the Human Factors Engineering (HFE) integrated system validation of the Main Control Room (MCR) configuration. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Tom G. Petrak at 706-848-1575.

Respectfully submitted.

• Uyt/VMXV Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 3.2.00.01 c.ii [Index Number 742]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0830 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Vox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reouiatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Qqiethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0830 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse 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. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis 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 Sen/Ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Batch BIngham

U.S. Nuclear Regulatory Commission ND-18-0830 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0830 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 3.2.00.01 c.ii [Index Number 742]

U.S. Nuclear Regulatory Commission ND-18-0830 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment

1. The HFE verification and validation program is performed in accordance with the HFE verification and validation implementation plan and includes the following activities:

c) Integrated system validation Insoections/Tests/Analvses c)(ii) Tests and analyses of the following plant evolutions and transients, using a facility that physically represents the MCR configuration and dynamically represents the MCR HSI and the operating characteristics and responses of the AP1000 design, will be performed:

- Normal plant heatup and startup to 100% power

- Normal plant shutdown and cooldown to cold shutdown

- Transients: reactor trip and turbine trip

- Accidents:

- Small-break LOCA

- Large-break LOCA

- Steam line break

- Feedwater line break

- Steam generator tube rupture Acceotance Criteria c)(ii) A report exists and concludes that: The test and analysis results demonstrate that the MCR operators can perform the following:

- Heat up and start up the plant to 100% power

- Shut down and cool down the plant to cold shutdown

- Bring the plant to safe shutdown following the specified transients

- Bring the plant to a safe, stable state following the specified accidents ITAAC Determination Basis Multiple ITAAC are performed to verify that the Human Factors (HF) Engineering (HFE) verification and validation (V&V) program, as described in VEGP 3 &4 Updated Final Safety Analysis Report, Section 18.11, "Human Factors Engineering Verification and Validation" (Reference 1), is performed in accordance with the HFE V&V implementation plan. The subject ITAAC requires that tests and analyses of the following plant evolutions and transients, using a facility that physically represents the Main Control Room (MCR) configuration and dynamically represents the MCR Human-System Interface (HSI) and the operating characteristics and responses of the API 000 design, be performed:

Normal plant heatup and startup to 100% power Normal plant shutdown and cooldown to cold shutdown

- Transients: reactor trip and turbine trip

- Accidents:

U.S. Nuclear Regulatory Commission ND-18-0830 Enclosure Page 3 of 4

- Small-break Loss of Coolant Accident (LOCA)

- Large-break LOCA

- Steam line break

- Feedwater line break

- Steam generator tube rupture An Integrated System Validation (ISV) was conducted in accordance with the NRC approved "AP1000 Human Factors Engineering Integrated System Validation Plan" (Reference 2) to provide a human performance-based assessment of the MSI resources, based on their realistic operation within a simulator-driven MCR. The ISV used the plantevolutions, transients and accident scenarios listed above to assess the usability of the MCR and HSi resources. The objective of ISV was to ensure that the functions and tasks allocated to plant personnel can be accomplished with the HSI design implementation.

The HFE ISV plan for the AP1000 plant was developed based on the information and guidance described in NUREG-0711, "Human Factors Engineering Program Review Model" (Reference 3). The HFE V&V activities, which include HFE integrated system validation, confirm the adequacy of HSI resources and Operationand Control Center System (DCS) design. The overall objective of HFE V&V is to ensure that the API 000 design attains a high standard of HF adequacy and thereby contributes to the safety, operability and maintainability of the plant.

Following completion of the ISV an evaluation was conducted ofthe ISV activity to ensure that the test and analysis results demonstrate that the MCR operators can perform the following:

heat up and start upthe plant to 100% power; shut down and cool down the plant to cold shutdown; bring the plant to safe shutdown following a reactor trip and a turbine trip; and bring the plant to a safe, stable state for the small-break LOCA, large-break LOCA, steam line break, feedwater line break and steam generator tube rupture accidents.

The results of the ISV are documented in the "API 000 Human Factors Engineering Integrated System Validation Report" (Reference 4). The ISV results identified a number of Human Engineering Discrepancies (HEDs) during the performance of the normal plant heatup and startup, and small-break LOCA scenarios. Subsequently, these HEDs were resolved and targeted ISV retests were conducted using the "API 000 Human Factors Engineering Discrepancy Resolution Process" (Reference 5). The results of the ISV retests are documented in the "API 000 Human Engineering Discrepancy Resolution Summary Report" (Reference 6).

These reports conclude that the test and analysis results demonstrate that the MCR operators can perform the following: heat up and start upthe plant to 100% power; shut down and cool down the plant to cold shutdown; bring the plant to safe shutdown following a reactor trip and a turbine trip and bring the plant to a safe, stable state for the small-break LOCA, large-break LOCA, steam line break, feedwater line break and steam generator tube rupture accidents.

ITAAC Finding Review In accordance with plantprocedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the Unit 3 and Unit 4 ITAAC Completion Package for ITAAC 3.2.00.01 c.ii (Reference 7) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-18-0830 Enclosure Page 4 of 4 ITAAC ComDietion Statement Based on the above information, SNC hereby notifies the NRG that ITAAC 3.2.00.01c.ii was performed for Vogtle Units 3 and 4 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliantcondition in accordance with approved plant programs and procedures.

References favailable for NRG inspection)

1. Updated Final Safety Analysis Report, Section 18.11, "Human Factors Engineering Verification and Validation"

2. APP-OCS-GEH-320, Rev 7, "API 000 Human Factors Engineering Integrated System Validation Plan"

3. NUREG-0711, "Human Factors Engineering Program Review Model"

4. APP-OCS-GER-320, Rev 3, "API 000 Human Factors Engineering Integrated System Validation Report"

5. APP-OCS-GEH-420, Rev 2, "API000 Human Factors Engineering Discrepancy Resolution Process"

6. APP-OCS-GER-420, Rev 0, "API 000 Human Engineering Discrepancy Resolution Summary Report"

7. 3.2.00.01 c.ii-UO-CP-RevO, ITAAC Completion Package