ND-22-0188, ITAAC Closure Notification on Completion of ITAAC 2.2.03.07b (Index Number 172)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.07b (Index Number 172)

ML22103A222
Person / Time
Site:	Vogtle
Issue date:	04/13/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-22-0188
Download: ML22103A222 (9)

Text

>-. Southern Nuclear Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro , GA 30830 Vogtle 3 & 4 706-848-6926 tel Docket Nos.: 52-025 APR 1 3 2022 ND-22-0188 10 CFR 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 ITAAC Closure Notification on Completion of ITAAC 2.2.03 .07b [Index Number 1721 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 Inspections, Tests , Analyses , and Acceptance Criteria (ITAAC) Item 2.2.03.07b [Index 1721. This ITAAC confirms that the Class 1E Passive Core Cooling System (PXS) components identified in Combined License (COL) Table 2.2.3-1 are powered from their respective Class 1E division. The closure process for this ITAAC is based on 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.

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 Kelli Roberts at 706-848-6991 .

Respectfully submitted ,

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.07b [Index Number 1721 JMC/HGT/sfr

U.S. Nuclear Regulatory Commission ND-22-0188 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI .L06 File AR.01 .02 .06 Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelli Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall Oglethorpe Power Corporation

U.S. Nuclear Regulatory Commission ND-22-0188 Page 3 of 3 Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S.L. Zwack Other Mr. S. W . Kline , Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D ., GOS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey , Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton , Balch Bingham

U.S. Nuclear Regulatory Commission ND-22-0188 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-22-0188 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.07b [Index Number 172]

U.S. Nuclear Regulatory Commission ND-22-0188 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.

Inspections/Tests/Analyses 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 Determination Basis Testing was performed on the Class 1 E components (equipment) identified in the VEGP Unit 3 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 1 E division .

Class 1 E power verification testing of the Protection and Safety Monitoring System (PMS) cabinets, associated with the equipment identified in Attachment A, was verified through applicable portions of ITAAC 2.5.02.05a component testing (Reference 1) and confirms the PMS cabinets are powered from their respective Class 1E division . Unit 3 SV3-PXS-ITR-800172 (Reference 2) documents 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. Reference 2 first verified 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 . Reference 2 then confirmed ,

via cable/wiring termination inspection documentation , that continuity testing was 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 , confirmed that the equipment identified in Appendix A is powered from its respective Class 1 E division.

The Unit 3 technical reports (References 1 and 2) confirm that a simulated test signal exists at the Class 1 E equipment identified in Table 2.2.3-1 when the assigned Class 1 E division is provided the test signal.

References 1 and 2 are available for NRC inspection as part of Unit 3 ITAAC Completion Package (Reference 3).

ITAAC Finding Review 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-22-0188 Enclosure Page 3 of 6 associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

ITAAC Completion Statement Based on the above information , SNC hereby notifies the NRC that ITAAC 2.2.03.07b was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

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

References (available for NRC inspection)

1. SV3-PMS-ITR-800527-1 Rev. 0, "Unit 3 Protection & Safety Monitoring (PMS) System Equ ipment by Assigned Class 1 E Division: ITAAC 2.5.02.05a"

2. SV3-PXS-ITR-800172 Rev. 0, "Unit 3 Passive Core Cooling System (PXS) Class 1E Equipment Signaled from Assigned Division: ITAAC 2.2.03.07b"

3. 2.2 .03.07b-U3-CP-Rev0 , ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0188 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-V1 OBA 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-22-0188 Enclosure Page 5 of 6 IRWST Gutter Isolation Valve PXS-PL-V130B CMT A Level Sensor PXS-011A CMT A Level Sensor PXS-011 B CMT A Level Sensor PXS-011C CMT A Level Sensor PXS-011 D CMT B Level Sensor PXS-012A CMT B Level Sensor PXS-012B CMT B Level Sensor PXS-012C CMT B Level Sensor PXS-012D CMT A Level Sensor PXS-013A CMT A Level Sensor PXS-013B CMT A Level Sensor PXS-013C CMT A Level Sensor PXS-013D CMT B Level Sensor PXS-014A CMT B Level Sensor PXS-014B CMT B Level Sensor PXS-014C CMT B Level Sensor PXS-014D IRWST Wide Range Level Sensor PXS-046 IRWST Wide Range Level Sensor PXS-047 I RWST 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-22-0188 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