ND-23-0392, ITAAC Closure Notification on Completion of ITAAC 2.2.05.09c (Index Number 877)

ITAAC Closure Notification on Completion of ITAAC 2.2.05.09c (Index Number 877)

ML23132A327
Person / Time
Site:	Vogtle
Issue date:	05/12/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0392
Download: ML23132A327 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel May 12, 2023 Docket No.: 52-026 ND-23-0392 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 2.2.05.09c [Index Number 877]

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) 2.2.05.09c [Index Number 877]. This ITAAC confirms that Main Control Room (MCR) Load Shed Panels identified in Combined License Appendix C Table 2.2.5-1 perform their active safety function after receiving a signal from the Protection and Safety Monitoring System (PMS). The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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 2.2.05.09c [Index Number 877]

JMC/KIK/sfr

U.S. Nuclear Regulatory Commission ND-23-0392 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-23-0392 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-23-0392 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.05.09c [Index Number 877]

U.S. Nuclear Regulatory Commission ND-23-0392 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 9.c) The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS.

Inspections, Tests, Analyses Testing will be performed on the MCR Load Shed Panels listed in Table 2.2.5-1 using real or simulated signals into the PMS.

Acceptance Criteria The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function identified in the table after receiving a signal from the PMS.

ITAAC Determination Basis Testing was performed to demonstrate the Main Control Room (MCR) Load Shed Panels identified in Combined License (COL) Appendix C Table 2.2.5-1 (Attachment A) performed their active safety function after receiving a signal from the Protection and Safety Monitoring System (PMS).

Testing was performed in accordance with the Unit 4 procedure listed in Reference 1 and confirmed that the MCR Load Shed Panels identified in Attachment A performed their active safety function to de-energize MCR loads after receiving a signal from the PMS.

An actuation signal from PMS was generated using the PMS Maintenance and Test Panel (MTP) to actuate the MCR Load Shed Panel 1, Division A. The MCR Load Shed Panel was verified locally to have actuated after the receipt of the actuation signal and the stage 1 and stage 2 loads were verified to be de-energized. The MCR Load Shed Panel 1, Division A was reset and the loads were verified to be energized. This methodology was repeated for MCR Load Shed Panel 2, Division A, MCR Load Shed Panel 1, Division C, and MCR Load Shed Panel 2, Division C.

The completed Unit 4 test results (Reference 1) confirmed that the MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function identified in the table after receiving a signal from the PMS.

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 ITAAC Completion Package for ITAAC 2.2.05.09c Completion Package (Reference 2) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-23-0392 Enclosure Page 3 of 4 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.05.09c was performed for VEGP Unit 4 and that the associated acceptance criteria is 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-VES-ITR-800877, Rev 0, Unit 4 Recorded Results of Main Control Room Load Shed:

ITAAC 2.2.05.09c, NRC Index Number: 877

2. 2.2.05.09c-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0392 Enclosure Page 4 of 4 Attachment A

• Excerpt from COL Appendix C Table 2.2.5-1

• Equipment Name *Tag No. *Active Function De-energize MCR Load Shed Panel 1 VES-EP-01 MCR Loads De-energize MCR Load Shed Panel 2 VES-EP-02 MCR Loads