ND-22-0876, ITAAC Closure Notification on Completion of ITAAC 3.3.00.02h 9Index Number 776)

ITAAC Closure Notification on Completion of ITAAC 3.3.00.02h 9Index Number 776)

ML23031A198
Person / Time
Site:	Vogtle
Issue date:	01/31/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0876, ITAAC 3.3.00.02h
Download: ML23031A198 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel January 31, 2023 Docket No.:

52-026 ND-22-0876 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 3.3.00.02h [Index Number 776]

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 3.3.00.02h [Index Number 776]. This ITAAC verified by inspection that the flood-up volume portion of the as-built containment is less than 71,960 ft3 to an elevation of 107.68. 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 3.3.00.02h [Index Number 776]

JMC/PAW/sfr

U.S. Nuclear Regulatory Commission ND-22-0876 Enclosure 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-22-0876 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0876 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 3.3.00.02h [Index Number 776]

U.S. Nuclear Regulatory Commission ND-22-0876 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 2.h) The free volume in the containment allows for floodup to support long-term core cooling for postulated loss-of-coolant accidents.

Inspections, Tests, Analyses An inspection will be performed of the as-built containment structures and equipment. The portions of the containment included in this inspection are the volumes that flood with a loss-of-coolant accident in passive core cooling system valve/equipment room B (11207). The in-containment refueling water storage tank volume is excluded from this inspection.

Acceptance Criteria A report exists and concludes that the floodup volume of this portion of the containment is less than 71,960 ft3 to an elevation of 107.68'.

ITAAC Determination Basis An inspection was performed of the as-built containment structures and equipment. The volumes included in the inspection and calculation are the volumes that flood with a loss-of-coolant accident (LOCA) in passive core cooling system (PXS) valve/equipment room B (11207). The In-containment Refueling Water Storage Tank (IRWST) volume is excluded from this inspection. The inspection report concluded that the floodup volume of this portion of the containment is less than 71,960 ft3 to an elevation of 107.68' which demonstrates the free volume in the containment allows for floodup to support long-term core cooling for postulated loss-of-coolant accidents.

The inspection consisted of measuring the areas in containment that flood with a LOCA in the PXS valve/equipment Room B (11207) using measurement equipment in accordance with site procedures.

These measurements were used to confirm the calculation inputs (Reference 1) to calculate the free volume available is less than 71,960 ft3 to an elevation of 107.68'.

The calculation (Reference 1) concluded that the floodup volume of the specified portion of containment to an elevation of 107.68 was 67,929 ft3 for Unit 4. This meets the ITAAC acceptance criterion of less than 71,960 ft3. The results verified that the free volume in the containment allows for floodup to support long-term core cooling for postulated loss-of-coolant accidents.

Reference 1 is available for NRC inspection as part of the Unit 4 ITAAC 3.3.00.02h Completion Package (Reference 2).

U.S. Nuclear Regulatory Commission ND-22-0876 Enclosure Page 3 of 3 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 associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.3.00.02h (Reference 2) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.02h 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-M3C-033 Rev.0, Containment Flood-Up Volume Calculation

2. 3.3.00.02h-U4-CP-Rev0, ITAAC Completion Package