ND-18-0585, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08b.02 (Index Number 176)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08b.02 (Index Number 176)

ML18243A028
Person / Time
Site:	Vogtle
Issue date:	08/30/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0585
Download: ML18243A028 (6)

Text

Michael J. Yox 7825 River Road-Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@southernco.com AU6 3 0 2018 Docket Nos.: 52-025 ND-18-0585 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 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08b.02 [Index Number 1761 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 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08b.02 [Index Number 176] for verifying that the elevation of the centerline ofthe Passive Residual Heat Removal Heat Exchanger (PRHR HX) upper channel head is greater than the Hot Leg (HL) centerline by at least 26.3 ft. 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 lettercontains 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 Petrak at 706-848-1575.

Respectfully submitted.

Midhael J. Ybx/

Regulatory Affairs Dfi;6ctor Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08b.02 [Index Number 176]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0585 Page 2 of 3 To:

Southern Nuclear Operating Companv/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

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

Mr. D. H. Jones (w/o enclosures)

Mr. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Parton Ms. A. L. Pugh Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. C. T. Defnall Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reaulatorv Commission Mr. W. Jones (w/o enclosures)

Mr. F. D. Brown Ms. J. M. Heisserer Ms. A. E. Rivera-Varona Mr. M. E. Ernstes Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen MuniclDal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-0585 Page 3 of 3 Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. CorlettI Ms. L. G. Iller Ms. J. Monahan Mr. J. L. Coward Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0585 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0585 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08b.02 [Index Number 176]

U.S. Nuclear Regulatory Commission ND-18-0585 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment:

8.b) The PXS provides core decay heat removal during design basis events.

Insoections.Tests. Analvsis:

2. Inspection of the elevation of the PRHR HX will be conducted.

Acceptance Criteria:

2. The elevation of the centerline of the PRHR HX's upper channel head is greater than the HL centerline by at least 26.3 ft.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Passive Core Cooling System (PXS) provides core decay heat removal during design basis events. The subject ITAAC requires that an inspection be conducted of the Passive Residual Heat Removal Heat Exchanger (PRHR HX) to confirm that the centerline elevation of the PRHR HX's upper channel head is greater than the Hot Leg (HL) centerline by at least 26.3 ft.

The inspection of the centerline elevation ofthe PRHR HX's upper channel head and the centerline elevation of the HL was performed, following installation of the PRHR HX and the main reactor coolant loop piping, using survey equipment in accordance with the site survey and measurement procedure (Reference 1). The elevation difference was determined by measuring the centerline elevation of the HL and the centerline elevation of the PRHR HX's upper channel head in relation to a common reference point, and comparing the results.

The inspection results documented in Reference 2, verify that the elevation of the centerline of the PRHR HX's upper channel head is 26.4feet greaterthan the HL centerline, which meets the ITAAC acceptance criteria.

ITAAC Finding Review In accordance with plantprocedures 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 Packagefor ITAAC 2.2.03.08b.02 (Reference 3) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-18-0585 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRG that ITAAC 2.2.03.08b.02 was performed for VEGP Unit 3 and that the prescribed acceptance criteria are 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 favailable for NRG Inspection)

1. 26139-000-4MP-T81C-N3201 Rev 1 "Vogtle Units 3 and 4 Construction Completion Project

- Construction Survey"

2. SV3-PXS-MEK-891997 Rev 1, "As-Built Elevation Comparison of PRHR Heat Exchanger Upper Channel Head Centerline to RCS Hot Leg Centerline"

3. 2.2.03.08b.02-U3-CP-Rev 0, "Completion Package for the Unit 3 ITAAC 2.2.03.08b.02

[Index Number 176]"