ND-19-0614, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.07b (Index Number 172)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.07b (Index Number 172)

ML19225C195
Person / Time
Site:	Vogtle
Issue date:	08/12/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0614
Download: ML19225C195 (9)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei AUG t 2 2019 Docket Nos.: 52-025 52-026 ND-19-0614 10 CFR 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 2.2.03.07b rindex Number 1721 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of August 8, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.07b

[Index Number 172] 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.

tichael J. Yox ii£^ /Mviy Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.07b [Index Number 172]

MJY/RLB/sfr

U.S. Nuclear Regulatory Commission ND-19-0614 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Companv Mr. P. 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. J. Vox 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 Qqiethorpe Power Corooration Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-19-0614 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0614 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-19-0614 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.07b [Index Number 172]

U.S. Nuclear Regulatory Commission ND-19-0614 Enclosure Page 2 of 6 ITAAC Statement Design Commitment 7.b) The Class 1E components identified in Table 2.2.3-1 are powered from their respective Class 1E division.

I nspections/Tests/Analvses Testing will be performed 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 2.2.3-1 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 2.2.3-1 (Attachment A)to demonstrate they are powered from their respective Class 1E division. This ITAAC performs testing on the Passive Core Cooling System (PXS)equipment identified in Table 2.2.3-1 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 SNC921610 and SNCXXXXXX (References 2 and 3, respectively) document completion of power verification activities from the PMS cabinets and the Class 1E power distribution panels/motor control centers to 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 panel/motor control center to the respective component identified in Attachment A using approved construction drawings and cable/wiring termination documentation. References 2 and 3 then 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 IE 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 2.2.3-1 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-19-0614 Enclosure Page 3 of 6 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. SNC921610,"PXS Component Power Verification Test- ITAAC: SV3-2.2.03.07b"

3. SNCXXXXXX,"PXS Component Power Verification Test- ITAAC: SV4-2.2.03.07b"

4. 2.2.03.07b-U3-CP-Rev0, ITAAC Completion Package

5. 2.2.03.07b-U4-CP-Rev0, 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-19-0614 Enclosure Page 4 of 6 Attachment A COL Appendix C Table 2.2.3-1 Equipment Name* Tag No.*

CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B CMT A Discharge Isolation Valve PXS-PL-V014A CMT B Discharge Isolation Valve PXS-PL-V014B CMT A Discharge Isolation Valve PXS-PL-V015A CMT B Discharge Isolation Valve PXS-PL-V015B Nitrogen Supply Containment Isolation Valve PXS-PL-V042 PRHR HX Inlet Isolation Motor-operated Valve PXS-PL-V101 PRHR HX Control Valve PXS-PL-V108A PRHR HX Control Valve PXS-PL-V108B Containment Recirculation A Isolation PXS-PL-V117A Motor-operated Valve Containment Recirculation B Isolation PXS-PL-V117B Motor-operated Valve Containment Recirculation A Squib Valve PXS-PL-V118A Containment Recirculation B Squib Valve PXS-PL-V118B Containment Recirculation A Squib Valve PXS-PL-V120A Containment Recirculation B Squib Valve PXS-PL-V120B IRWST Injection A Squib Valve PXS-PL-V123A IRWST Injection B Squib Valve PXS-PL-V123B IRWST Injection A Squib Valve PXS-PL-V125A IRWST Injection B Squib Valve PXS-PL-V125B IRWST Gutter Isolation Valve PXS-PL-V130A

U.S. Nuclear Regulatory Commission ND-19-0614 Enclosure Page 5 of 6 IRWST Gutter Isolation Valve PXS-PL-V130B GMT A Level Sensor PXS-011A GMT A Level Sensor PXS-011B GMT A Level Sensor PXS-011G GMT A Level Sensor PXS-011D GMT B Level Sensor PXS-012A GMT B Level Sensor PXS-012B GMT B Level Sensor PXS-012G GMT B Level Sensor PXS-012D GMT A Level Sensor PXS-013A GMT A Level Sensor PXS-013B GMT A Level Sensor PXS-013G GMT A Level Sensor PXS-013D GMT B Level Sensor PXS-014A GMT B Level Sensor PXS-014B GMT B Level Sensor PXS-014G GMT B Level Sensor PXS-014D IRWST Wide Range Level Sensor PXS-046 IRWST Wide Range Level Sensor PXS-047 IRWST Wide Range Level Sensor PXS-048 PRHR HX Flow Sensor PXS-049A PRHR HX Flow Sensor PXS-049B Containment Flood-up Level Sensor PXS-050 Containment Flood-up Level Sensor PXS-051

U.S. Nuclear Regulatory Commission ND-19-0614 Enclosure Page 6 of 6 Containment Flood-up Level Sensor PXS-052 IRWST Lower Narrow Range Level Sensor PXS-066 IRWST Lower Narrow Range Level Sensor PXS-067 IRWST Lower Narrow Range Level Sensor PXS-068 IRWST Lower Narrow Range Level Sensor PXS-069 Excerpted from COL Appendix C Table 2.2.3-1