ND-18-1289, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.iv.01 (Index Number 183)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.iv.01 (Index Number 183)

ML18299A203
Person / Time
Site:	Vogtle
Issue date:	10/25/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.03.08c.iv.01, ND-18-1289
Download: ML18299A203 (6)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii OCT 2 5 2018 myox@southernco.com Docket Nos.: 52-025 ND-18-1289 10CFR 52.99(c)(1)

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 2.2.03.08c.iv.01 flndex Number 1831 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 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.iv.01 [Index Number 183] for verifying that the maximum elevation of the top inside surface of the In-containment Refueling Water Storage Tank (IRWST) injection lines and IRWST connection to Direct Vessel Injection (DVI) nozzles is less than the elevation of IRWST bottom inside surface and that the elevation of the IRWST bottom inside tank surface is higher than the DVI nozzle centerlines by > 3.4 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 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 Direbtor Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 183]

MJY/GDL/amw

U.S. Nuclear Regulatory Commission ND-18-1289 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. Vox 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. J. C. Haswell Document Services RTYPE; VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown Ms. J. M. Heisserer Ms. A. E. Rivera-Varona 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 Ooiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Munlcipai Eiectric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-1289 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, Batch BIngham

U.S. Nuclear Regulatory Commission ND-18-1289 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-1289 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 183]

U.S. Nuclear Regulatory Commission ND-18-1289 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

Insoections.Tests. Analvsis iv) Inspections of the elevation of the following pipe lines will be conducted:

1. IRWST injection lines; IRWST connection to DVI nozzles v) Inspections of the elevation of the following tanks will be conducted:

2. IRWST Acceptance Criteria iv) The maximum elevation of the top inside surface of these lines is less than the elevation of:

1. IRWST bottom inside surface v) The elevation ofthe bottom inside tank surface is higher than the direct vessel injection nozzle centerline by the following:

2. IRWST >3.4 ft 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 ofthe top inside surfaceofthe In-containment Refueling Water StorageTank (IRWST) injection lines and IRWST connection to Direct Vessel Injection (DVI) nozzles is less than the elevation of IRWST bottom inside surface and that the elevation of the IRWST bottom inside tank surface is higher than the DVI nozzle centerlines by s 3.4 ft.

The inspection ofthe IRWST injection lines top inside surface, IRWST connection to the DVI nozzles top inside surface, the DVI nozzle centerline, and the IRWST bottom inside tank surface elevations were performed using survey equipment in accordance with the site surveyand 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 ofthe inside surface of these lines. The maximum derived elevation of the IRWST injection lines top inside surface, the DVI nozzle centerline, and IRWSTconnection to the DVI nozzles top inside surface is comparedto the measured elevation ofthe IRWST bottom inside tank surface using a common reference point.

U.S. Nuclear Regulatory Commission ND-18-1289 Enclosure Page 3 of 3 The inspection results are documented in the Principal Closure Documents (References 2 and 3), supporting the ITAAC 2.2.03.08c.iv.01 Completion Package (Reference 4). Reference 2 determined that the maximum elevation of the top inside surface of the IRWST injection lines and IRWST connection to the DVI nozzles is 100.7 feet and are lower than the 103.0 foot elevation of the IRWST bottom inside surface. Reference 3 determined that both DVI nozzle centerline elevations are 99.6 feet, which are 3.4 feet below the 103.0 foot elevation of IRWST bottom inside surface, and therefore both Acceptance Criteria are met.

The Principal Closure Documents exists and are available for NRC inspection as part of the ITAAC 2.2.03.08c.iv.01 Completion Package.

ITAAC Finding Review In accordance with plant procedures for ITAAC completion. Southern NuclearOperating 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 is documented in the ITAAC Completion Package for ITAAC 2.2.03.08c.iv.01 (Reference4) and available for NRC review.

ITAAC ComDietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.iv.01 was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.

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

References (available for NRC inspection)

1. 4MP-T81C-N3201 Rev 1 "Construction Survey"

2. SV3-PXS-FSK-800183 Rev 0, "As-Built IRWST Injection Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface"

3. SV3-PXS-MTK-891586 Rev 0, "IRWST Bottom Inside Tank Surface Comparison to DVI Nozzle Centerline Elevation"

4. 2.2.03.08c.iv.01-U3-CP-Rev 0, ITAAC Completion Package