ND-23-0078, ITAAC Closure Notification on Completion of ITAAC 2.2.02.06b (Index Number 133)

From kanterella
(Redirected from ML23027A118)
Jump to navigation Jump to search

ITAAC Closure Notification on Completion of ITAAC 2.2.02.06b (Index Number 133)
ML23027A118
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 01/27/2023
From: Coleman J
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0078, ITAAC 2.2.02.06b
Download: ML23027A118 (1)


Text

Jamie M. Coleman 7825 River Road

>. Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel

January 27, 2023

Docket No.: 52-026

ND-23-0078 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 2.2.02.06b [Index Number 133]

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 2.2.02.06b [Index Number 133]. This ITAAC confirms that the Class 1E Passive Containment Cooling System (PCS) components identified in Combined License (COL) Table 2.2.2-1 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 4 Completion of ITAAC 2.2.02.06b [Index Number 133]

JMC/CSS/sfr U.S. Nuclear Regulatory Commission ND-23-0078 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-23-0078 Enclosure Page 1 of 4

Southern Nuclear Operating Company ND-23-0078 Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.02.06b [Index Number 133]

U.S. Nuclear Regulatory Commission ND-23-0078 Enclosure Page 2 of 4

ITAAC Statement Design Commitment

6.b) The Class 1E components identified in Table 2.2.2-1 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 components identified in Table 2.2.2-1 when the assigned Class 1E division is provided the test signal.

ITAAC Determination Basis

Testing was performed on the Class 1E components identified in the VEGP Unit 4 COL Appendix C Table 2.2.2-1 (Attachment A) to demonstrate they are powered from their respective Class 1E division. This ITAAC performs testing on the components identified in Table 2.2.2-1 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, was verified as documented in SV4-PCS-ITR-800133 (Reference 1) and confirms the PMS cabinets are powered from their respective Class 1E division. Reference 1 first verified that power supply cables/wiring were installed and terminated from the applicable Class 1E division distribution panel power supply to the PMS cabinets providing power to the components in Attachment A using approved construction drawings and cable/wiring termination documentation. Reference 1 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, confirm that the PMS cabinets providing power to components identified in Attachment A are powered from their respective Class 1E division.

SV4-PCS-ITR-800133 (Reference 1) also documents completion of power verification activities from the PMS cabinets and the Class 1E power distribution panels/motor control centers to the components identified in Attachment A. Reference 1 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 1 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 components identified in Appendix A are powered from their respective Class 1E d ivision.

SV4-PCS-ITR-800133 (Reference 1) confirmed that a simulated test signal exists at the Class 1E components identified in Table 2.2.2-1 when the assigned Class 1E division is provided the test signal.

U.S. Nuclear Regulatory Commission ND-23-0078 Enclosure Page 3 of 4

Reference 1 is available for NRC inspection as part of the Unit 4 ITAAC 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.

The ITAAC completion review is documented in the Vogtle Unit 4 ITAAC Completion Package for ITAAC 2.2.02.06b (Reference 2) and is available for NRC inspection.

ITAAC Completion Statement

Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.02.06b 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-PCS-ITR-800133 Rev0 Unit 4 Passive Containment Cooling System (PCS) Class 1E Equipment Signaled from Assigned Division: ITAAC 2.2.02.06b
2. 2.2.02.06b-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0078 Enclosure Page 4 of 4

Attachment A

COL Appendix C Table 2.2.2-1

Component Name* Tag No.*

PCCWST Isolation Valve PCS-PL-V001A

PCCWST Isolation Valve PCS-PL-V001B

PCCWST Isolation Valve MOV PCS-PL-V001C

PCCWST Isolation Block MOV PCS-PL-V002A

PCCWST Isolation Block MOV PCS-PL-V002B

PCCWST Isolation Block MOV PCS-PL-V002C

PCS Water Delivery Flow Sensor PCS-001

PCS Water Delivery Flow Sensor PCS-002

PCS Water Delivery Flow Sensor PCS-003

PCS Water Delivery Flow Sensor PCS-004

Containment Pressure Sensor PCS-005

Containment Pressure Sensor PCS-006

Containment Pressure Sensor PCS-007

Containment Pressure Sensor PCS-008

PCCWST Water Level Sensor PCS-010

PCCWST Water Level Sensor PCS-011

High-range Containment Pressure Sensor PCS-012

High-range Containment Pressure Sensor PCS-013

High-range Containment Pressure Sensor PCS-014

  • Excerpted from COL Appendix C Table 2.2.2-1