ND-19-0505, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.01.03a (Index Number 582)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.01.03a (Index Number 582)

ML19193A202
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-19-0505
Download: ML19193A202 (7)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Southern Nuclear Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei JUL 1 2 2019 Docket Nos.: 52-025 52-026 ND-19-0505 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control 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 Initial Fuel Load Item 2.6.01.03a [Index Number 5821 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, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.6.01.03a [Index Number 582] 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 submit^.

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 2.6.01.03a [Index Number 582]

MJY/RLB/sfr

U.S. Nuclear Regulatory Commission ND-19-0505 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. Vox 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.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 Oalethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0505 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton 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. Hosier, 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0505 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0505 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.6.01.03a [Index Number 582]

U.S. Nuclear Regulatory Commission ND-19-0505 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 3.a) The Class 1E breaker control power for the equipment identified in Table 2.6.1-1 are powered from their respective Ciass 1E division.

Insoections/Tests/Analvses Testing will be performed on the ECS by providing a simulated test signal in each Class 1E division.

Acceptance Criteria A simulated test signal exists at the Class 1E equipment identified in Table 2.6.1-1 when the assigned Class 1E division is provided the test signai.

ITAAC Completion Description Testing is performed on the Class 1E breaker control power for the equipment identified in the VEGP Unit 3 and Unit 4 COL Appendix C Table 2.6.1-1 (Attachment A)to demonstrate the breaker control power is powered from its respective Class 1E division. This ITAAC performs testing on the Main ac Power System (ECS)equipment identified in Table 2.6.1-1 by providing a simulated test signal in each Class 1E division.

Class 1E power verification testing of the Protection and Safety Monitoring System (PMS) cabinets, associated with the equipment identified in Attachment A, is verified through ITAAC 2.5.02.05a component testing (Reference 1) and confirms the PMS cabinets are powered from their respective Class 1E division. Unit 3 and Unit 4 component test package work orders SNC921169 and SNCXXXXXX (References 2 and 3, respectively) document completion of power verification activities from the PMS cabinets and the Class 1E power distribution panels for the breaker control power for the equipment identified in Attachment A. References 2 and 3 first verify that power supply cables/wiring are installed and terminated from the applicable PMS cabinet and Class 1E power distribution panels to the respective circuit breaker identified in Attachment A using approved construction drawings and cable/wiring termination documentation. References 2 and 3then confirm, via cable/wiring termination inspection documentation, that continuity testing is performed on each of the installed cables/wiring to confirm current fiow within the instailed cable/wiring. The combination of cable/wiring installation and termination verification, with the instalied cable/wiring continuity testing, confirms that the breaker controi power for the equipment identified in Appendix A is powered from its respective Class 1E division.

The Unit 3 and Unit 4 component test package work orders (References 2 and 3, respectively) confirm that a simulated test signal exists at the Class 1E equipment identified in Table 2.6.1-1 when the assigned Ciass 1E division is provided the test signal.

References 2 and 3 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC Completion Packages(References 4 and 5).

U.S. Nuclear Regulatory Commission ND-19-0505 Enclosure Page 3 of 4 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Soutfiern 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(available for NRG inspection)

1. ITAAC 2.5.02.05a Closure Notification

2. SNC921169,"ECS Component Power Verification Test- ITAAC; SV3-2.6.01.03a"

3. SNCXXXXXX,"ECS Component Power Verification Test- ITAAC: SV4-2.6.01.03a"

4. 2.6.01.03a-U3-CP-Rev 0, ITAAC Completion Package

5. 2.6.01.03a-U4-CP-Rev 0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0505 Enclosure Page 4 of 4 Attachment A COL Appendix C Table 2.6.1-1 Equipment Name* Tag No.*

Reactor Coolant Pump(RCP) Circuit ECS-ES-31 Breaker RCP Circuit Breaker ECS-ES-32 RCP Circuit Breaker ECS-ES-41 RCP Circuit Breaker ECS-ES-42 RCP Circuit Breaker ECS-ES-51 RCP Circuit Breaker ECS-ES-52 RCP Circuit Breaker ECS-ES-61 RCP Circuit Breaker ECS-ES-62 Excerpted from COL Appendix C Table 2.6.1-1