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

From kanterella
Revision as of 07:49, 7 January 2025 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
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)


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