ND-23-0173, ITAAC Closure Notification on Completion of ITAAC 2.3.09.02b (Index Number 422)

ITAAC Closure Notification on Completion of ITAAC 2.3.09.02b (Index Number 422)

ML23061A171
Person / Time
Site:	Vogtle
Issue date:	03/03/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0173
Download: ML23061A171 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel March 2, 2023 Docket No.:

52-026 ND-23-0173 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 4 ITAAC Closure Notification on Completion of ITAAC 2.3.09.02b [Index Number 422]

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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.09.02b [Index Number 422]. This ITAAC verified that testing was performed on Containment Hydrogen Control System components, each non-Class 1E power group is powered from their respective non-Class 1E power group, and simulated test signal exists at the containment hydrogen control component when the assigned non-Class 1E power group is provided the test signal.

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 4 Completion of ITAAC 2.3.09.02b [Index Number 422]

JMC/CSS/sfr

U.S. Nuclear Regulatory Commission ND-23-0173 Page 2 of 2 cc:

Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-23-0173 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-23-0173 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.09.02b [Index Number 422]

U.S. Nuclear Regulatory Commission ND-23-0173 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 2.b) The components identified in Table 2.3.9-2 are powered from the respective non-Class 1E power group.

Inspections, Tests, Analyses Testing will be performed by providing a simulated test signal in each non-Class 1E power group.

Acceptance Criteria A simulated test signal exists at the equipment identified in Table 2.3.9-2 when the assigned non-Class 1E power group is provided the test signal.

ITAAC Determination Basis Testing is performed on the components (equipment) identified in the VEGP Unit 4 COL Appendix C Table 2.3.9-2 (Attachment A) to demonstrate they are powered from their respective non-Class 1E power group. This ITAAC performs testing on the equipment identified in Attachment A by providing a simulated test signal in each non-Class 1E power group.

The Unit 4 work packages identified in Reference 1 document completion of power verification activities for the equipment identified in Attachment A. Reference 1 first verifies that power supply cables/wiring are installed and terminated from the applicable non-Class 1E power group distribution panels to the equipment identified in Attachment A using approved construction drawings and cable/wiring termination documentation. Reference 1 then confirms, 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, confirms that the equipment identified in Attachment A is powered from its respective non-Class 1E power group.

The Unit 4 work packages documented in Reference 1 confirm that a simulated test signal exists at the equipment identified in Table 2.3.9-2 when the assigned non-Class 1E power group is provided the test signal.

Reference 1 is available for NRC inspection, as well as the Unit 4 ITAAC 2.3.09.02b Completion Package (Reference 2).

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 associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-23-0173 Enclosure Page 3 of 5 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.09.02b was performed for VEGP Unit 4 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. SV4-VLS-ITR-800422, Rev0, Unit 4 Containment Hydrogen Control System (VLS): ITAAC 2.3.09.02b NRC Index Number 422

2. 2.3.09.02b-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0173 Enclosure Page 4 of 5 Attachment A COL Appendix C Table 2.3.9-2 Equipment Name*

Tag Number*

Power Group Number*

Hydrogen Igniter 01 VLS-EH-01 1

Hydrogen Igniter 02 VLS-EH-02 2

Hydrogen Igniter 03 VLS-EH-03 1

Hydrogen Igniter 04 VLS-EH-04 2

Hydrogen Igniter 05 VLS-EH-05 1

Hydrogen Igniter 06 VLS-EH-06 2

Hydrogen Igniter 07 VLS-EH-07 2

Hydrogen Igniter 08 VLS-EH-08 1

Hydrogen Igniter 09 VLS-EH-09 1

Hydrogen Igniter 10 VLS-EH-10 2

Hydrogen Igniter 11 VLS-EH-11 2

Hydrogen Igniter 12 VLS-EH-12 1

Hydrogen Igniter 13 VLS-EH-13 1

Hydrogen Igniter 14 VLS-EH-14 2

Hydrogen Igniter 15 VLS-EH-15 2

Hydrogen Igniter 16 VLS-EH-16 1

Hydrogen Igniter 17 VLS-EH-17 2

Hydrogen Igniter 18 VLS-EH-18 1

Hydrogen Igniter 19 VLS-EH-19 2

Hydrogen Igniter 20 VLS-EH-20 2

Hydrogen Igniter 21 VLS-EH-21 1

Hydrogen Igniter 22 VLS-EH-22 1

Hydrogen Igniter 23 VLS-EH-23 2

Hydrogen Igniter 24 VLS-EH-24 2

Hydrogen Igniter 25 VLS-EH-25 2

Hydrogen Igniter 26 VLS-EH-26 2

Hydrogen Igniter 27 VLS-EH-27 1

Hydrogen Igniter 28 VLS-EH-28 1

Hydrogen Igniter 29 VLS-EH-29 1

Hydrogen Igniter 30 VLS-EH-30 2

Hydrogen Igniter 31 VLS-EH-31 1

Hydrogen Igniter 32 VLS-EH-32 1

Hydrogen Igniter 33 VLS-EH-33 2

Hydrogen Igniter 34 VLS-EH-34 1

Hydrogen Igniter 35 VLS-EH-35 1

U.S. Nuclear Regulatory Commission ND-23-0173 Enclosure Page 5 of 5 Equipment Name*

Tag Number*

Power Group Number*

Hydrogen Igniter 36 VLS-EH-36 2

Hydrogen Igniter 37 VLS-EH-37 1

Hydrogen Igniter 38 VLS-EH-38 2

Hydrogen Igniter 39 VLS-EH-39 1

Hydrogen Igniter 40 VLS-EH-40 2

Hydrogen Igniter 41 VLS-EH-41 2

Hydrogen Igniter 42 VLS-EH-42 1

Hydrogen Igniter 43 VLS-EH-43 1

Hydrogen Igniter 44 VLS-EH-44 1

Hydrogen Igniter 45 VLS-EH-45 2

Hydrogen Igniter 46 VLS-EH-46 2

Hydrogen Igniter 47 VLS-EH-47 1

Hydrogen Igniter 48 VLS-EH-48 2

Hydrogen Igniter 49 VLS-EH-49 1

Hydrogen Igniter 50 VLS-EH-50 2

Hydrogen Igniter 51 VLS-EH-51 1

Hydrogen Igniter 52 VLS-EH-52 2

Hydrogen Igniter 53 VLS-EH-53 2

Hydrogen Igniter 54 VLS-EH-54 1

Hydrogen Igniter 55 VLS-EH-55 1

Hydrogen Igniter 56 VLS-EH-56 2

Hydrogen Igniter 57 VLS-EH-57 2

Hydrogen Igniter 58 VLS-EH-58 1

Hydrogen Igniter 59 VLS-EH-59 2

Hydrogen Igniter 60 VLS-EH-60 1

Hydrogen Igniter 61 VLS-EH-61 1

Hydrogen Igniter 62 VLS-EH-62 2

Hydrogen Igniter 63 VLS-EH-63 1

Hydrogen Igniter 64 VLS-EH-64 2

Hydrogen Igniter 65 VLS-EH-65 1

Hydrogen Igniter 66 VLS-EH-66 2

• Excerpted from COL Appendix C Table 2.3.9-2