ND-23-0225, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.xiii (Index Number 198)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.xiii (Index Number 198)

ML23159A256
Person / Time
Site:	Vogtle
Issue date:	06/08/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0225
Download: ML23159A256 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel June 8, 2023 Docket No.: 52-026 ND-23-0225 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 2.2.03.08c.xiii [Index Number 198]

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 2.2.03.08c.xiii [Index Number 198] for verifying the surfaces in the vicinity of the containment recirculation screens in the Passive Core Cooling System (PXS) are stainless steel. 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 A. 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 2.2.03.08c.xiii [Index Number 198]

JMC/PAW/sfr

U.S. Nuclear Regulatory Commission ND-23-0225 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-23-0225 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-23-0225 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.03.08c.xiii [Index Number 198]

U.S. Nuclear Regulatory Commission ND-23-0225 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

Inspections, Tests, Analyses xiii) Inspections will be conducted of the surfaces in the vicinity of the containment recirculation screens. The surfaces in the vicinity of the containment recirculation screens are the surfaces located above the bottom of the recirculation screens up to and including the bottom surface of the plate discussed in Table 2.2.3-4, item 8.c.vii, out at least 8 ft, 3 in perpendicular to the front and at least 7 feet to the side of the face of the screens.

Acceptance Criteria xiii) These surfaces are stainless steel.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. For this ITAAC, inspections are performed to verify that the surfaces in the vicinity of the containment recirculation screens in the PXS are stainless steel.

The surfaces in the vicinity of the containment recirculation screens in the PXS are defined as the surfaces located above the bottom of the containment recirculation screens up to and including the bottom surface of the plate discussed in Vogtle Electric Generating Plant (VEGP)

Combined License Appendix C, Table 2.2.3-4 item 8.c.vii, out at least 8 ft, 3 in perpendicular to the front and at least 7 feet to the side of the face of the screens.

The results of the inspections of the surfaces in the vicinity of the containment recirculation screens in the PXS as defined above are documented in the Unit 4 Principal Closure Document (Reference 1) supporting the Unit 4 ITAAC 2.2.03.08c.xiii Completion Package (Reference 2).

The inspection confirmed that the surfaces in the vicinity of the containment recirculation screens are stainless steel.

The Unit 4 Principal Closure Document (Reference 1) is available for NRC inspection as part of the Unit 4 ITAAC 2.2.03.08c.xiii 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 ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings

U.S. Nuclear Regulatory Commission ND-23-0225 Enclosure Page 3 of 3 associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.03.08c.xiii (Reference 2) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.xiii 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-PXS-ITR-800198, Rev. 0,Unit 4 PXS ITAAC Inspection of Room 11202: ITAAC 2.2.03.08c.xiii NRC Index Number 198

2. 2.2.03.08c.xiii-U4-CP-Rev0, ITAAC Completion Package