ND-23-0563, ITAAC Closure Notification on Completion of ITAAC 2.2.02.10c (Index Number 153)

ITAAC Closure Notification on Completion of ITAAC 2.2.02.10c (Index Number 153)

ML23181A181
Person / Time
Site:	Vogtle
Issue date:	06/30/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-23-0563
Download: ML23181A181 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 June 30, 2023 Docket No.:

52-026 ND-23-0563 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 2.2.02.10c [Index Number 153]

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 2.2.02.10c [Index Number 153], to verify that the remotely operated valves identified in Combined License (COL)

Appendix C Table 2.2.2-1 as having Diverse Actuation System (DAS) control perform an active function after receiving a signal from the DAS. 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 2.2.02.10c [Index Number 153]

JMC/KIK/sfr

U.S. Nuclear Regulatory Commission ND-23-0563 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-23-0563 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-23-0563 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.02.10c [Index Number 153]

U.S. Nuclear Regulatory Commission ND-23-0563 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 10.c) The valves identified in Table 2.2.2-1 as having DAS control perform an active safety function after receiving a signal from the DAS.

Inspections/Tests/Analyses Testing will be performed on remotely operated valves listed in Table 2.2.2-1 using real or simulated signals into the DAS.

Acceptance Criteria The remotely operated valves identified in Table 2.2.2-1 as having DAS control perform the active function identified in the table after receiving a signal from the DAS.

ITAAC Determination Basis Testing was performed in accordance with Unit 4 preoperational test procedure and documented in Reference 1 to verify that the remotely operated valves identified in Combined License (COL) Appendix C Table 2.2.2-1 (Attachment A) as having Diverse Actuation System (DAS) control perform an active safety function after receiving a signal from DAS. Real signals were provided into the DAS and the valves in Attachment A were confirmed to perform the active function after receiving a signal from the DAS.

The preoperational testing confirms that each of the Passive Containment Cooling Water Storage Tank (PCCWST) isolation valves that have DAS control receive a signal from DAS and perform the required active function. Initially, the valves were verified to be in the non-actuated position (closed). The valves were remotely operated by manually initiating a containment cooling signal at the DAS panel in the Main Control Room (MCR) and verifying the valves perform their active function (transfer open). Each valve was verified to open using the Main Control Room (MCR) display as well as local inspection of each valve.

The Unit 4 preoperational test results in Reference 1 documented that the remotely operated valves listed in Attachment A as having DAS control perform the active function identified in Attachment A after receiving a signal from the DAS.

Reference 1 is available for NRC inspection as part of the ITAAC 2.2.02.10c 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 were no relevant findings associated with this ITAAC. The review is documented in the ITAAC Completion Package (Reference 2) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-23-0563 Enclosure Page 3 of 4 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.02.10c 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-800153, Rev. 0, Unit 4 Passive Containment Cooling System Valve Testing:

ITAAC 2.2.02.10c NRC Index Number: 153

2. ITAAC 2.2.02.10c-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0563 Enclosure Page 4 of 4 Attachment A

• Excerpt from COL Appendix C Table 2.2.2-1 Tag No.*

Component Name*

Active Function*

PCS-PL-V001A PCCWST Isolation Valve Transfer Open PCS-PL-V001B PCCWST Isolation Valve Transfer Open PCS-PL-V001C PCCWST Isolation Valve MOV Transfer Open