ND-18-1168, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.iv.04 (Index Number 186)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.iv.04 (Index Number 186)

ML18261A042
Person / Time
Site:	Vogtle
Issue date:	09/17/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.03.08c.iv.04, ND-18-1168
Download: ML18261A042 (6)

Text

A _ , k1 I 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 SEP 112018 Docket Nos.;52-025 ND-18-1168 10CFR 52.99(G)(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.iv.04 [Index Number 1861 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 2.2.03.08c.iv.04 [Index Number 186] for verifying that the maximum elevation of the top inside surface of the Passive Residual Heat Removal Heat Exchanger (PRHR HX) outlet line to Steam Generator (SG) connection is less than the elevation of the PRHR HX lower channel head top 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 Dir^6tor Vogtle 3 &4

/

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.04 [Index Number 186]

MJY/GDL/amw

U.S. Nuclear Regulatory Commission ND-18-1168 Page 2 of 3 To:

Southern Nuclear Operating Company/ 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 OalethorDe 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

U.S. Nuclear Regulatory Commission ND-18-1168 Page 3 of 3 Westinqhouse 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, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-1168 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-1168 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.04 [Index No. 186]

U.S. Nuclear Regulatory Commission ND-18-1168 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment:

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

Inspections.Tests. Analvsis:

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

4. PRHR HX outlet line to SG connection Acceotance Criteria:

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

4. PRHR HX lower channel head top inside surface ITAAC Determination Basis Multiple ITAAC are performed to demonstrate thatthe Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, andsafety injection during design basis events. This ITAAC requires inspections of the top inside surface ofthe Passive Residual Heat Removal Heat Exchanger (PRHR HX) outlet line to Steam Generator (SG) connection.

The inspections of the PRHR HX outlet line to SG connection top-of-pipe surface was performed using survey equipment in accordance with the site survey and measurement procedure (Reference 1). The conservative wall thickness, derived from installed pipe data, was subtracted from the top-of-pipe surveydata to obtain the highest elevation of the inside surface ofthese lines (Reference 2). The elevation of the PRHR HX lower channel head top outside surface was determined using survey equipment in accordance with the site survey and measurement procedure (Reference 1). As-built manufacturer's data was used to derive the PRHR HX lower channel head wall thickness. The PRHR HX lower channel head top inside surface elevation was then determined bysubtracting the as-built manufactrurer's lower channel head wall thickness from the top outside surface ofthe lower channel head (Reference 2). The maximum derived elevation of the top inside surface of the PRHR HX outlet line to SG connection was compared to the derived elevation ofthe top inside surface of the PRHR HX lower channel head.

The inspection results documented in Reference 2, verify thatthe maximum elevation of the PRHR HX outlet line to SG connection top inside surface is 110.5 feet and the elevation of the PRHR HX lower channel head top inside surface is 111.6feet, which meets the ITAAC acceptance criteria.

ITAAC Finding Review In accordancewith plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining tothe subject ITAAC and

U.S. Nuclear Regulatory Commission ND-18-1168 Enclosure Page 3 of 3 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.04 (Reference3) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.iv.04 was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part ofthis ITAAC are being maintained in their as-designed, ITAAC compliant condition inaccordance with approved plant programs and procedures.

References favallable for NRC Inspection)

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

- Construction Survey"

2. SV3-PXS-FSK-800186 Rev 0, "As-Built PRHR HX Outlet Lines Elevation Comparison to PRHR HX Lower Channel Head Top Inside Surface Elevation"

3. 2.2.03.08c.iv.04-U3-CP-Rev 0, "Completion Package for the Unit3 ITAAC 2.2.03.08c.iv.04

[Index Number 186]"