ND-22-0118, ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813)

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ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813)
ML22110A231
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 04/20/2022
From: Coleman J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 3.3.00.08, ND-22-0118
Download: ML22110A231 (6)
v • d • e


Text

A Southern Nuclear APR 2 0 2022 Docket No.:

52-025 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-22-0118 1 O CFR 52.99(c)(1)

ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 8131 Ladies and Gentlemen:

In accordance with 1 O 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 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.08 (Index Number 8131.

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 1 O CFR 52.99.

If there are any questions, please contact Kelli A. Roberts at 706-848-6991.

Respectfully submitted,

~~

Ja

  • M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

JMC/JFV/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC Item 3.3.00.08 (Index Number 8131

U.S. Nuclear Regulatory Commission ND-22-0118 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J.C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. 8. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Mccurry Mr. J. Parent Mr. 8. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-22-0118 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S.L. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GOS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-22-0118 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0118 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC Item 3.3.00.08 [Index Number 813]

U.S. Nuclear Regulatory Commission ND-22-0118 Enclosure Page 2 of 3 IT AAC 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 SV3-GW-GLR-275, Vogtle Unit 3 AP1000 Pipe Rupture Hazards Analysis (PRHA) As-Built Summary Report for the Auxiliary Building

- All Levels (Reference 1 ), and SV3-GW-GLR-276, Vogtle Unit 3 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 3 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-22-0118 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 3 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. SV3-GW-GLR-275, Rev. 1, "Vogtle Unit 3 AP1000 Pipe Rupture Hazards Analysis (PRHA) As-Built Summary Report for the Auxiliary Building - All Levels"
2. SV3-GW-GLR-276, Rev. 1, "Vogtle Unit 3 AP1000 Pipe Rupture Hazards Analysis (PRHA) As-Built Summary Report for Containment Building - All Levels"
3. 3.3.00.08-U3-CP-Rev0, ITAAC Completion Package
4. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 1 0 CFR Part 52"
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