ND-17-2139, Vogtie Electric Generating Plant Unit 3 - ITAAC Closure Notification on Completion of ITAAC C.2.6.12.05 (Index Number 675): Difference between revisions

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{{#Wiki_filter:Michael J. Yox               7825 River Road A South ern Nuclear                                        Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@soutfiernco.com DEC 2 9 2017 Docket No.;      52-025 ND-17-2139 10CFR 52.99(c)(1)
{{#Wiki_filter:A South ern Nuclear DEC 2 9 2017 Docket No.;
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC C.2.6.12.05 [Index Number 6751 Ladies and Gentlemen:
52-025 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@soutfiernco.com ND-17-2139 10CFR 52.99(c)(1)
Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC C.2.6.12.05 [Index Number 6751 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 Vogtie Electric Generating Plant (VEGP)
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 Vogtie Electric Generating Plant (VEGP)
Unit 3 and Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item C.2.6.12.05 [Index Number 675] for verifying the short circuit contribution of each as-built offsite circuit at the interface with the onsite ac power system is compatible with the interrupting capability of the onsite fault current interrupting devices. 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.
Unit 3 and Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item C.2.6.12.05 [Index Number 675] for verifying the short circuit contribution of each as-built offsite circuit at the interface with the onsite ac power system is compatible with the interrupting capabilityof the onsite fault current interrupting devices. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "IndustryGuideline 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.
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 Tom G. Petrak at 706-848-1575.
If there are any questions, please contact Tom G. Petrak at 706-848-1575.
Respectfully submitted.
Respectfully submitted.
Michael J. Yox Regulatory Affairs/Director Vogtie 3 & 4
Michael J. Yox Regulatory Affairs/Director Vogtie3 &4


==Enclosure:==
==Enclosure:==
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MJY/RAS/amw
MJY/RAS/amw


U.S. Nuclear   Regulatory Commission ND-17-2139 Page 2 of 3 To:
U.S. Nuclear ND-17-2139 Page 2 of 3 To:
Southern Nii clear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Southern Nii Regulatory Commission clear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Rauckhorst (w/o enclosures)
Mr. M. D. Rauckhorst (w/o enclosures)
Mr. M. D. Me er Mr. D. H. Jones (w/o enclosures)
Mr. M. D. Me er Mr. D. H. Jones (w/o enclosures)
Mr. D. L. MchJnney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Will s Ms. A. L. Puclh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Walshington Mr. J. P. Red Ms. A. C. Chkmberlain Mr. D. R. Cu ver Mr. R. L. Bel ke Mr. T. G. Pelrak Document S<5rvices RTYPE: VND.L1.L06 File AR.01.02.06 cc:
Mr. D. L. MchJnney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Will s Ms. A. L. Puclh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Walshington Mr. J. P. Red Ms. A. C. Chkmberlain Mr. D. R. Cu Mr. R. L. Bel ver ke Mr. T. G. Pelrak Document S<5rvices RTYPE: VND.L1.L06 File AR.01.02.06 cc:
Nuclear Rec uiatorv Commission Mr. W. Jones (w/o enclosures)
Nuclear Rec uiatorv Commission Jones (w/o enclosures)
Ms. J. M. He)sserer Mr. 0. P. Palel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E.Te nple Ms. P. Braxti Dn Mr. T. C. Brimfield Mr. A. J. Leroh Mr. 0. J. Even Mr. F. D. Brown Mr. B. J. Kernker Ms. A. E. Riyera-Varona Qqiethorpe Power Corporation Mr. K. T. Hayines Mr. R. B. Br ihkman Municipal Electric Authority of Georgia Mr. J. E. Ful er Mr. S. M. Ja ckson
M. He)sserer P. Palel E. Ernstes J. Khouri E. Chandler E.Te Braxti nple Dn Mr. W.
Ms. J.
Mr. 0.
Mr. M.
Mr. G.
Mr. T.
Ms. S.
Ms. P.
Mr. T.
Mr. A.
Mr. 0.
Mr. F.
Mr. B.
Ms. A.
C. Brimfield J. Leroh J. Even D. Brown J. Kernker E. Riyera-Varona Qqiethorpe Power Corporation Mr. K. T.
Mr. R. B. Br Hayines ihkman Municipal Electric Authority of Georgia Mr. J. E. Ful Mr. S. M. Ja er ckson


U.S. Nuclear Iflegulatory Commission ND-17-2139 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
U.S. Nuclear Iflegulatory Commission ND-17-2139 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC (w/o enclosures) rlliam (w/o enclosures) etti Dr. L. Oriani Mr. D. 0. Du Mr. M. M. Cor Ms. L. G. Iller Mr. D. Hawkir Ms. 8. DiTom Mr. J. L. Cow^
Mr. D. 0. Du rlliam (w/o enclosures)
Ms. N. E. De.
Mr. M. M. Cor etti Ms. L. G. Iller Mr. D. Hawkir s Ms. 8. DiTom (naso Mr. J. L. Cow^ rd Ms. N. E. De.dngelis Other Mr. J. E. Heslle r, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Other Mr. J. E. Heslle Ms. L. Matis, Dr. W. R. Jacbl Mr. 8. Roetge r, Ms. 8. W. Ken Mr. K. C. Greei Mr. 8. Blanton s
Dr. W. R. Jacblbs, Jr., Ph.D., GDS Associates, Inc.
(naso rd dngelis r, Bechtel Power Corporation Tetra Tech NUS, Inc.
Mr. 8. Roetge r,, Georgia Public Sen/ice Commission Ms. 8. W. Kennizan, Georgia Public Service   Commission Mr. K. C. Greeine, Troutman Sanders Mr. 8. Blanton Balch Bingham
bs, Jr., Ph.D., GDS Associates, Inc.
, Georgia Public Sen/ice Commission nizan, Georgia Public Service Commission ne, Troutman Sanders Balch Bingham


U.S. Nuclear Iflegulatory Commission ND-17-2139 Binclosure Page 1 of 3 Southern Nuclear Operating Company ND-17-2139 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC C.2.6.12.05 [Index Number 675]
U.S. Nuclear ND-17-2139 Bi Page 1 of 3 Iflegulatory Commission nclosure Southern Nuclear Operating Company ND-17-2139 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC C.2.6.12.05 [Index Number 675]


U.S. Nuclear Regulatory      Commission ND-17-2139E nclosure Page 2 of 3 ITAAC StateiTient Design Comm itment:
U.S. Nuclear ND-17-2139E Page 2 of 3 Regulatory Commission nclosure ITAAC StateiTient Design Comm itment:
: 5. The fault ciurrent  contribution of each offsite circuit is compatible with the interrupting capability of the onsite short circuit interrupting devices.
5.
The fault ci capability urrent contribution of each offsite circuit is compatible with the interrupting of the onsite short circuit interrupting devices.
Inspections. T(?sts. Analyses:
Inspections. T(?sts. Analyses:
Analyses of the as-built offsite circuit will be performed     to evaluate the fault current contribution of each offsite circuit at the interface with the onsite ac   power system.
Analyses of of each offsite the as-built offsite circuit will be performed to evaluate the fault current contribution circuit at the interface with the onsite ac power system.
Acceptance Ciiteria:
Acceptance Ciiteria:
A report exists and concludes the short circuit contribution of each as-built offsite circuit at the interface with t he onsite ac power system     is compatible with the interrupting capability of the onsite fault cu lirent interrupting devices.
A report exists interface with t onsite fault cu and concludes the short circuit contribution of each as-built offsite circuit at the he onsite ac power system is compatible with the interruptingcapability of the lirent interrupting devices.
ITAAC Determination Basis Analyses of the as-built offsite power system were performed to verify the fault current contribution of each as-built offsite circuit is compatible with the interrupting capability of the onsite short ci itcuit interrupting devices.
ITAAC Determination Basis Analyses of contribution of onsite short ci the as-built offsite power system were performed to verify the fault current each as-built offsite circuit is compatible with the interrupting capability of the itcuit interrupting devices.
The design of he as-built offsite circuits was reviewed and the fault current contribution of each offsite circuit w as analyzed for short-circuits under two operational scenarios of the offsite power system. The friSt scenario was based on Vogtle Units 1,2, and 3 in normal operation, which is the configuratibin that will exist once Vogtle Unit 3 is completed and prior to completion of Unit 4.
The design of offsite circuit w system. The the configuratibi The second sq offsite power Units 3 and 4 0.2.6.12.05-(Reference 1) he as-built offsite circuits was reviewed and the fault current contribution of each as analyzed for short-circuits under two operational scenarios of the offsite power St scenario was based on Vogtle Units 1,2, and 3 in normal operation, which is n that will exist once Vogtle Unit3 is completed and priorto completion of Unit 4.
The second sqenario was based on Vogtle Units 1, 2, 3, and 4 in normal operation, which is the offsite power  system configuration that will have the highest potential fault currents once Vogtle Units 3 and 4    ^re completed. The results of the analyses are provided in the report, 0.2.6.12.05--U3    PCD-Rev 0-01, "Vogtle 3&4 Offsite Power - Maximum Available Fault Currents" (Reference 1)
enario was based on Vogtle Units 1, 2, 3, and 4 in normal operation, which is the system configuration that will have the highest potential fault currents once Vogtle
The design of he onsite alternating current (AC) power system was reviewed to determine that the capabilities of the interrupting devices are compatible with the short circuit contribution of each as-built ciffsite circuit. The results of the design review are summarized in the report, PCD Summary Repp rt C.2.6.12.05-U3-SumRep-Rev 0, "Review of As-Designed Short-Circuit Capabilities of Onsite AC Power System" (Reference 2). The report concludes the analyses that determined the equipment ratings were performed with a conservative equivalent short-circuit impedatvce. The equipment rating requirements identified in those analyses were incorporated ir) the design specifications issued for procurement of the equipment.
^re completed. The results of the analyses are provided in the report, PCD-Rev 0-01, "Vogtle 3&4Offsite Power - Maximum Available Fault Currents" fri
The fault capa Dilities of the onsite AC power system are conservatively designed for fault currents greatrjir than the maximum expected fault currents of the offsite power system. The short-circuit cc ntribution of each as-built offsite circuit at the interface with the onsite AC power system is com patible with the interrupting capability of the onsite fault current interrupting devices.
-U3 The design of the capabilities each as-built ci Summary Repp Capabilities of that determined circuit impedatv incorporated ir) he onsite alternating current (AC) power system was reviewed to determine that of the interrupting devices are compatible with the short circuit contribution of ffsite circuit. The results of the design review are summarized in the report, PCD rt C.2.6.12.05-U3-SumRep-Rev 0, "Review of As-Designed Short-Circuit Onsite AC Power System" (Reference 2). The report concludes the analyses the equipment ratings were performed with a conservative equivalent short-ce. The equipment rating requirements identified in those analyses were the design specifications issued for procurement of the equipment.
Dilities of the onsite AC power system are conservatively designed for fault r than the maximum expected fault currents of the offsite power system. The ntribution of each as-built offsite circuit at the interface with the onsite AC power patible with the interrupting capability of the onsite fault current interrupting The fault capa currents greatrji short-circuit cc system is com devices.


U.S. Nuclear Regulatory  Commission ND-17-2139E nclosure 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 document number is included in the Vogtle Unit 3 ITAAC Completion Package for ITAAC C.2.6.12.05 (Reference 3) and available for NRC inspection.
U.S. Nuclear ND-17-2139E Page 3 of 3 Regulatory Commission nclosure 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 document number is included in the Vogtle Unit 3 ITAAC Completion Package for ITAAC C.2.6.12.05 (Reference 3) and available for NRC inspection.
ITAAC Completion Statement Based on the   above information, SNC hereby notifies the NRC that ITAAC C.2.6.12.05 was performed for ^/ogtle Unit 3 and that the prescribed acceptance criteria are met. Systems, structures, anc components verified as part of this ITAAC are being maintained in their as-designed, ITA^'C compliant condition in accordance with approved plant programs and procedures.
ITAAC Completion Statement Based on the performed for ^
References (a vailable for NRC inspection)
structures, anc designed, ITA^'
procedures.
above information, SNC hereby notifies the NRC that ITAAC C.2.6.12.05 was
/ogtle Unit3 and that the prescribed acceptance criteria are met. Systems, components verified as part of this ITAAC are being maintained in their as-C compliant condition in accordance with approved plant programs and References (available for NRC inspection)
: 1. C.2.6.12.0^-U3-PCD-Rev 0-01, "Vogtle 3&4 Offsite Power - Maximum Available Fault Currents"
: 1. C.2.6.12.0^-U3-PCD-Rev 0-01, "Vogtle 3&4 Offsite Power - Maximum Available Fault Currents"
: 2. C.2.6.12.0^-U3-SumRep-Rev 0, "Review of As-Designed Short-Circuit Capabilities of Onsite AC Power System"
: 2. C.2.6.12.0^-U3-SumRep-Rev 0, "Review of As-Designed Short-Circuit Capabilities of Onsite AC Power System"
: 3. Vogtle Unit 3 ITAAC Completion Package for ITAAC C.2.6.12.05}}
: 3. Vogtle Unit 3 ITAAC Completion Package for ITAAC C.2.6.12.05}}

Latest revision as of 07:49, 7 January 2025

Vogtie Electric Generating Plant Unit 3 - ITAAC Closure Notification on Completion of ITAAC C.2.6.12.05 (Index Number 675)
ML17363A288
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 12/29/2017
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC C.2.6.12.05, ND-17-2139
Download: ML17363A288 (6)
v • d • e


Text

A South ern Nuclear DEC 2 9 2017 Docket No.;52-025 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@soutfiernco.com ND-17-2139 10CFR 52.99(c)(1)

Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC C.2.6.12.05 [Index Number 6751 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 Vogtie Electric Generating Plant (VEGP)

Unit 3 and Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item C.2.6.12.05 [Index Number 675] for verifying the short circuit contribution of each as-built offsite circuit at the interface with the onsite ac power system is compatible with the interrupting capabilityof the onsite fault current interrupting devices. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "IndustryGuideline 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 Tom G. Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox Regulatory Affairs/Director Vogtie3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC C.2.6.12.05 [Index Number 675]

MJY/RAS/amw

U.S. Nuclear ND-17-2139 Page 2 of 3 To:

Southern Nii Regulatory Commission clear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Me er Mr. D. H. Jones (w/o enclosures)

Mr. D. L. MchJnney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Will s Ms. A. L. Puclh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Walshington Mr. J. P. Red Ms. A. C. Chkmberlain Mr. D. R. Cu Mr. R. L. Bel ver ke Mr. T. G. Pelrak Document S<5rvices RTYPE: VND.L1.L06 File AR.01.02.06 cc:

Nuclear Rec uiatorv Commission Jones (w/o enclosures)

M. He)sserer P. Palel E. Ernstes J. Khouri E. Chandler E.Te Braxti nple Dn Mr. W.

Ms. J.

Mr. 0.

Mr. M.

Mr. G.

Mr. T.

Ms. S.

Ms. P.

Mr. T.

Mr. A.

Mr. 0.

Mr. F.

Mr. B.

Ms. A.

C. Brimfield J. Leroh J. Even D. Brown J. Kernker E. Riyera-Varona Qqiethorpe Power Corporation Mr. K. T.

Mr. R. B. Br Hayines ihkman Municipal Electric Authority of Georgia Mr. J. E. Ful Mr. S. M. Ja er ckson

U.S. Nuclear Iflegulatory Commission ND-17-2139 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC (w/o enclosures) rlliam (w/o enclosures) etti Dr. L. Oriani Mr. D. 0. Du Mr. M. M. Cor Ms. L. G. Iller Mr. D. Hawkir Ms. 8. DiTom Mr. J. L. Cow^

Ms. N. E. De.

Other Mr. J. E. Heslle Ms. L. Matis, Dr. W. R. Jacbl Mr. 8. Roetge r, Ms. 8. W. Ken Mr. K. C. Greei Mr. 8. Blanton s

(naso rd dngelis r, Bechtel Power Corporation Tetra Tech NUS, Inc.

bs, Jr., Ph.D., GDS Associates, Inc.

, Georgia Public Sen/ice Commission nizan, Georgia Public Service Commission ne, Troutman Sanders Balch Bingham

U.S. Nuclear ND-17-2139 Bi Page 1 of 3 Iflegulatory Commission nclosure Southern Nuclear Operating Company ND-17-2139 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC C.2.6.12.05 [Index Number 675]

U.S. Nuclear ND-17-2139E Page 2 of 3 Regulatory Commission nclosure ITAAC StateiTient Design Comm itment:

5.

The fault ci capability urrent contribution of each offsite circuit is compatible with the interrupting of the onsite short circuit interrupting devices.

Inspections. T(?sts. Analyses:

Analyses of of each offsite the as-built offsite circuit will be performed to evaluate the fault current contribution circuit at the interface with the onsite ac power system.

Acceptance Ciiteria:

A report exists interface with t onsite fault cu and concludes the short circuit contribution of each as-built offsite circuit at the he onsite ac power system is compatible with the interruptingcapability of the lirent interrupting devices.

ITAAC Determination Basis Analyses of contribution of onsite short ci the as-built offsite power system were performed to verify the fault current each as-built offsite circuit is compatible with the interrupting capability of the itcuit interrupting devices.

The design of offsite circuit w system. The the configuratibi The second sq offsite power Units 3 and 4 0.2.6.12.05-(Reference 1) he as-built offsite circuits was reviewed and the fault current contribution of each as analyzed for short-circuits under two operational scenarios of the offsite power St scenario was based on Vogtle Units 1,2, and 3 in normal operation, which is n that will exist once Vogtle Unit3 is completed and priorto completion of Unit 4.

enario was based on Vogtle Units 1, 2, 3, and 4 in normal operation, which is the system configuration that will have the highest potential fault currents once Vogtle

^re completed. The results of the analyses are provided in the report, PCD-Rev 0-01, "Vogtle 3&4Offsite Power - Maximum Available Fault Currents" fri

-U3 The design of the capabilities each as-built ci Summary Repp Capabilities of that determined circuit impedatv incorporated ir) he onsite alternating current (AC) power system was reviewed to determine that of the interrupting devices are compatible with the short circuit contribution of ffsite circuit. The results of the design review are summarized in the report, PCD rt C.2.6.12.05-U3-SumRep-Rev 0, "Review of As-Designed Short-Circuit Onsite AC Power System" (Reference 2). The report concludes the analyses the equipment ratings were performed with a conservative equivalent short-ce. The equipment rating requirements identified in those analyses were the design specifications issued for procurement of the equipment.

Dilities of the onsite AC power system are conservatively designed for fault r than the maximum expected fault currents of the offsite power system. The ntribution of each as-built offsite circuit at the interface with the onsite AC power patible with the interrupting capability of the onsite fault current interrupting The fault capa currents greatrji short-circuit cc system is com devices.

U.S. Nuclear ND-17-2139E Page 3 of 3 Regulatory Commission nclosure 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 document number is included in the Vogtle Unit 3 ITAAC Completion Package for ITAAC C.2.6.12.05 (Reference 3) and available for NRC inspection.

ITAAC Completion Statement Based on the performed for ^

structures, anc designed, ITA^'

procedures.

above information, SNC hereby notifies the NRC that ITAAC C.2.6.12.05 was

/ogtle Unit3 and that the prescribed acceptance criteria are met. Systems, components verified as part of this ITAAC are being maintained in their as-C compliant condition in accordance with approved plant programs and References (available for NRC inspection)

1. C.2.6.12.0^-U3-PCD-Rev 0-01, "Vogtle 3&4 Offsite Power - Maximum Available Fault Currents"
2. C.2.6.12.0^-U3-SumRep-Rev 0, "Review of As-Designed Short-Circuit Capabilities of Onsite AC Power System"
3. Vogtle Unit 3 ITAAC Completion Package for ITAAC C.2.6.12.05
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