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 Docket Nos.: 52-025 APR 1 3 2022 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-22-0188 10 CFR 52.99(c)(1)

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 1 E Passive Core Cooling System (PXS) components identified in Combined License (COL) Table 2.2.3-1 are powered from their respective Class 1 E 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 1 O 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:

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

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 1 E components identified in Table 2.2.3-1 are powered from their respective Class 1 E division.

Inspections/Tests/ Analyses Testing will be performed by providing a simulated test signal in each Class 1 E division.

Acceptance Criteria 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.

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 1 E 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 1 E division. Unit 3 SV3-PXS-ITR-800172 (Reference 2) documents completion of power verification activities from the PMS cabinets and the Class 1 E 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 1 E 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.

IT AAC 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 Equipment 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 1 E 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*

CMT A Inlet Isolation Motor-operated Valve CMT B Inlet Isolation Motor-operated Valve CMT A Discharge Isolation Valve CMT B Discharge Isolation Valve CMT A Discharge Isolation Valve CMT B Discharge Isolation Valve Nitrogen Supply Containment Isolation Valve PRHR HX Inlet Isolation Motor-operated Valve PRHR HX Control Valve PRHR HX Control Valve Containment Recirculation A Isolation Motor-operated Valve Containment Recirculation B Isolation Motor-operated Valve Containment Recirculation A Squib Valve Containment Recirculation B Squib Valve Containment Recirculation A Squib Valve Containment Recirculation B Squib Valve IRWST Injection A Squib Valve IRWST Injection B Squib Valve IRWST Injection A Squib Valve IRWST Injection B Squib Valve IRWST Gutter Isolation Valve Tag No.*

PXS-PL-V002A PXS-PL-V002B PXS-PL-V014A PXS-PL-V014B PXS-PL-V015A PXS-PL-V015B PXS-PL-V042 PXS-PL-V101 PXS-PL-V1 OBA PXS-PL-V108B PXS-PL-V117A PXS-PL-V117B PXS-PL-V118A PXS-PL-V118B PXS-PL-V120A PXS-PL-V120B PXS-PL-V123A PXS-PL-V123B PXS-PL-V125A PXS-PL-V125B PXS-PL-V130A

U.S. Nuclear Regulatory Commission ND-22-0188 Enclosure Page 5 of 6 IRWST Gutter Isolation Valve CMT A Level Sensor CMT A Level Sensor CMT A Level Sensor CMT A Level Sensor CMT B Level Sensor CMT B Level Sensor CMT B Level Sensor CMT B Level Sensor CMT A Level Sensor CMT A Level Sensor CMT A Level Sensor CMT A Level Sensor CMT B Level Sensor CMT B Level Sensor CMT B Level Sensor CMT B Level Sensor I RWST Wide Range Level Sensor I RWST Wide Range Level Sensor I RWST Wide Range Level Sensor PRHR HX Flow Sensor PRHR HX Flow Sensor Containment Flood-up Level Sensor Containment Flood-up Level Sensor PXS-PL-V130B PXS-011A PXS-011 B PXS-011C PXS-011 D PXS-012A PXS-012B PXS-012C PXS-012D PXS-013A PXS-013B PXS-013C PXS-013D PXS-014A PXS-014B PXS-014C PXS-014D PXS-046 PXS-047 PXS-048 PXS-049A PXS-049B PXS-050 PXS-051

U.S. Nuclear Regulatory Commission ND-22-0188 Enclosure Page 6 of 6 Containment Flood-up Level Sensor IRWST Lower Narrow Range Level Sensor IRWST Lower Narrow Range Level Sensor I RWST Lower Narrow Range Level Sensor I RWST Lower Narrow Range Level Sensor

• Excerpted from COL Appendix C Table 2.2.3-1 PXS-052 PXS-066 PXS-067 PXS-068 PXS-069