ND-18-1290, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.lv.02 (Index Number 184)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.lv.02 (Index Number 184)

ML19210D557
Person / Time
Site:	Vogtle
Issue date:	07/26/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-1290
Download: ML19210D557 (6)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel JUL 2 6 2019 Docket No.: 52-025 ND-18-1290 10CFR 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 2.2.03.08c.lv.02 [Index Number 1841 Ladles 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 2.2.03.08c.Iv.02[Index Number 184]for verifying that the maximum elevation of the top Inside surface of the Containment reclrculatlon lines and the Containment to the In-contalnment Refueling Water Storage Tank (IRWST) lines Is less than the elevation of the IRWST bottom Inside surface. 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 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 Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox ^

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.Iv.02 [Index Number 184]

MJY/GDL/sfr

U.S. Nuclear Regulatory Commission ND-18-1290 Page 2 of 3 To:

Southern Nuclear Operating Companv/ Georgia Power Company Mr. R. G. West(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. Vox Mr. A. 8. Parton Ms. K. A. Roberts 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. 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 Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. P. O'Bryan Mr. T. Fredette Mr. C. Weber Qqiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-18-1290 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Orlani(w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Mails, Tetra Tech NUS, Inc.

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

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

U.S. Nuclear Regulatory Commission ND-18-1290 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-1290 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 Completion of ITAAC 2.2.03.08c.iv.02[Index No. 184]

U.S. Nuclear Regulatory Commission ND-18-1290 Enclosure Page 2 of 3 ITAAC Statement Desian Commitment:

8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

Insoections.Tests. Analvses:

iv) Inspections of the elevation of the following pipe lines will be conducted:

2. Containment recirculation lines; containment to IRWST lines Acceptance Criteria:

iv) The maximum elevation of the top inside surface of these lines is less than the elevation of:

2. IRWST bottom inside surface ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. This ITAAC requires that inspections be conducted to verify that the maximum elevation of the top inside surface of the Containment recirculation lines and the Containment to the In-containment Refueling Water Storage Tank(IRWST) lines is less than the elevation of the IRWST bottom inside surface.

The inspection of the elevations of the top inside surface of the Containment recirculation lines, the Containment to IRWST lines, and the IRWST bottom inside surface was performed using survey equipment in accordance with site survey and measurement procedure (Reference 1).

The conservative wall thickness, derived from installed pipe data, was subtracted from the top-of-pipe survey data to obtain the highest elevation of the inside surface of these lines. The maximum derived elevation of the top inside surface of the Containment recirculation lines and the Containment to IRWST lines was compared to the elevation of the bottom inside surface of the IRWST using a common reference point.

The inspection results documented in Reference 2, verified that the maximum elevation of the top inside surface of the containment recirculation lines is 102.3 feet; the maximum elevation of the top inside surface of the containment to IRWST lines is 100.7 feet, and the elevation of the IRWST bottom inside surface is 103.0 feet, which meets the ITAAC acceptance criteria.

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 2.2.03.08c.iv.02(Reference 3)and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-18-1290 Enclosure Page 3 of 3 ITAAC ComDietion Statement Based on the above information, SNC hereby notifies the NRG that ITAAC 2.2.03.08c.iv.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. 4MP-T81C-N3201 Rev 5 "Construction Survey"

2. SV3-PXS-FSK-800184 Rev 0,"As-Built IRWST Injection/Recirculation Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface"

3. 2.2.03.08c.iv.02-U3-CP-Rev0, ITAAC Completion Package