ND-22-0796, ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813)

ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813)

ML23201A171
Person / Time
Site:	Vogtle
Issue date:	07/20/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0796, ITAAC Item 3.3.00.08
Download: ML23201A171 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel July 20, 2023 Docket No.:

52-026 ND-22-0796 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 Item 3.3.00.08 [Index Number 813]

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 3.3.00.08 [Index Number 813].

This ITAAC concludes that systems, structures, and components identified as essential targets in the as-built Pipe Rupture Hazard Analysis Report can withstand the effects of postulated pipe rupture without loss of required safety function. 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 Item 3.3.00.08 [Index Number 813]

JMC/ALH/sfr

U.S. Nuclear Regulatory Commission ND-22-0796 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-22-0796 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0796 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC Item 3.3.00.08 [Index Number 813]

U.S. Nuclear Regulatory Commission ND-22-0796 Enclosure Page 2 of 3 ITAAC Statement Design Commitment

8. Systems, structures, and components identified as essential targets are protected from the dynamic and environmental effects of postulated pipe ruptures.

Inspections/Tests/Analyses Following as-built reconciliation, an inspection will be performed of the as-built high and moderate energy pipe rupture mitigation features for systems, structures, and components identified as essential targets.

Acceptance Criteria An as-built Pipe Rupture Hazard Analysis Report exists and concludes that systems, structures, and components identified as essential targets can withstand the effects of postulated pipe rupture without loss of required safety function.

ITAAC Determination Basis Following as-built reconciliation, an inspection was performed of the as-built high and moderate energy pipe rupture mitigation features for systems, structures, and components (SSCs) identified as essential targets. An as-built Pipe Rupture Hazard Analysis (PRHA) report was produced which concluded that SSCs identified as essential targets can withstand the effects of postulated pipe rupture without loss of required safety function.

The results of these as-built inspections were documented in SV4-GW-GLR-275, Vogtle Unit 4 AP1000 Pipe Rupture Hazards Analysis (PRHA) As-Built Summary Report for the Auxiliary Building

- All Levels (Reference 1), and SV4-GW-GLR-276, Vogtle Unit 4 AP1000 Pipe Rupture Hazards Analysis (PRHA) As-Built Summary Report for the Containment Building - All Levels (Reference 2).

These as-built reports were prepared in consideration of the criteria and methods defined in Updated Final Safety Analysis Report (UFSAR) subsections 3.6.1.3.2 and 3.6.2.5, and SSCs that are required to be functional during and following a design basis event were confirmed to remain protected against or remain designed to withstand the dynamic and environmental effects of postulated failure in high and moderate energy piping. The as-built PRHA reports document and conclude the reconciliation of the as-built SSCs identified as essential targets can withstand the effects of postulated pipe rupture without loss of required safety function.

References 1 and 2 are available for NRC inspection as part of the Unit 4 ITAAC 3.3.00.08 Completion Package (Reference 3).

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 3.3.00.08 Completion Package (Reference 3) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-22-0796 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.08 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-GW-GLR-275, Rev. 0, Vogtle Unit 4 AP1000 As Built Pipe Rupture Hazards Analysis (PRHA) Summary Report for the Auxiliary Building - All Levels

2. SV4-GW-GLR-276, Rev. 0, Vogtle Unit 4 AP1000 As Built Pipe Rupture Hazards Analysis (PRHA) Summary Report for the Containment Building - All Levels

3. 3.3.00.08-U4-CP-Rev0, ITAAC Completion Package