ND-19-0622, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.06a (Index Number 687)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.06a (Index Number 687)

ML19193A204
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-19-0622
Download: ML19193A204 (7)

Text

A Michael J. Yox 7325 River Road SOUtuBrn Nucl63r Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel JUL I 2 2019 Docket Nos.: 52-025 52-026 ND-19-0622 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 2.7.01.06a findex Number 6871 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 2.7.01.06a [Index Number 687] 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 2.7.01.06a [Index Number 687]

MJY/RLB/sfr

U.S. Nuclear Regulatory Commission ND-19-0622 Page 2 of 3 To:

Southern Nuclear Operating ComDanv/ Georgia Power Company Mr. R.G. West(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. 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.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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0622 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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. 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., CDS 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-19-0622 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0622 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.06a [Index Number 687]

U.S. Nuclear Regulatory Commission ND-19-0622 Enclosure Page 2 of 4 ITAAC Statement Desian Commitment 6.a) The Class 1E components identified in Table 2.7.1-1 are powered from their respective Class 1E division.

Insoections/Tests/Analvses Testing will be performed on the VBS 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 2.7.1-1 when the assigned Class 1E division is provided the test signal.

ITAAC Completion Description Testing is performed on the Class 1E components(equipment) identified in the VEGP Unit 3 and Unit 4 COL Appendix C Table 2.7.1-1 (Attachment A)to demonstrate they are powered from their respective Class 1E division. This ITAAC performs testing on the Nuclear Island Nonradioactive Ventilation System (VBS)and Sanitary Drainage System (SDS)equipment identified in Table 2.7.1-1 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 SNC922114 and SNCXXXXXX (References 2 and 3, respectively) document completion of power verification activities from the PMS cabinets and the Class 1E motor control centers to the equipment identified in Attachment A. References 2 and 3first verify that power supply cables/wiring are installed and terminated from the applicable PMS cabinet and Class 1E motor control center to the respective component 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 flow within the installed cable/wiring. The combination of cable/wiring installation and termination verification, with the installed cable/wiring continuity testing, confirms that 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 2.7.1-1 when the assigned Class 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).

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

U.S. Nuclear Regulatory Commission ND-19-0622 Enclosure Page 3 of 4 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. SNC922114,"VBS Component Power Verification Test- ITAAC: SV3-2.7.01.06a"

3. SNCXXXXXX,"VBS Component Power Verification Test- ITAAC: SV4-2.7.01.06a"

4. 2.7.01.06a-U3-CP-Rev 0, ITAAC Completion Package

5. 2.7.01.06a-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-19-0622 Enclosure Page 4 of 4 Attachment A COL Appendix C Table 2.7.1-1 Equipment Name* Tag No.*

MCR Supply Air Isolation Valve VBS-PL-V186 MCR Supply Air Isolation Valve VBS-PL-V187 MCR Return Air Isolation Valve VBS-PL-V188 MCR Return Air Isolation Valve VBS-PL-V189 MCR Exhaust Air Isolation Valve VBS-PL-V190 MCR Exhaust Air Isolation Valve VBS-PL-V191 MCR SDS(Vent) Isolation Valve SDS-PL-V001 MCR SDS (Vent) Isolation Valve SDS-PL-V002 Excerpted from COL Appendix C Table 2.7.1-1