ND-21-0328, 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)

ML21180A334
Person / Time
Site:	Vogtle
Issue date:	06/29/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0328
Download: ML21180A334 (6)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel JUN 2 9 2021 Docket No.: 52-026 ND-21-0328 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 4 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.iv.01 [Index 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 Vogtle Electric Generating Plant(VEGP) Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.iv.01 [Index Number 183]. The ITAAC verifies 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 Kelli A. Roberts at 706-848-6991.

Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 183]

MJY/RMS/sfr

U.S. Nuclear Regulatory Commission ND-21-0328 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKlnney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Requlatorv Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil M C. P. Patel M G. J. Khouri M C. J. Even M B. J. Kemker Ms. N. C. Coovert M C. Welch M J. Gaslevic M O. Lopez-Santiago M G. Armstrong M M. Webb M T. Fredette M C. Santos M B. Davis M J. Vasquez M J. Eargle M E. Davidson M T. Fanelli Ms. K. McCurry M J. Parent M B. Griman

U.S. Nuclear Regulatory Commission ND-21-0328 Page 3 of 3 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinohouse Electric Company. LLC Dr. L. OrlanI Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, 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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-0328 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-21-0328 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 183]

U.S. Nuclear Regulatory Commission ND-21-0328 Enclosure Page 2 of 3 ITAAC Statement Desian Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

inspections.Tests. Anaivses 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 of the 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 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 s 3.4 ft.

The inspection of the 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 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 IRWST Injection lines top inside surface, the DVI nozzle centerline, and IRWST connection to the DVI nozzles top inside surface is compared to the measured elevation of the IRWST bottom inside tank surface using a common reference point.

U.S. Nuclear Regulatory Commission ND-21-0328 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 well as the ITAAC 2.2.03.08c.iv.01 Completion Package.

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 is documented In the ITAAC Completion Package for ITAAC 2.2.03.08c.iv.01 (Reference 4)and available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.iv.01 was performed for VEGP Unit 4 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(available for NRC Inspection)

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

2. SV4-PXS-FSK-800183 Rev 0, "As-Built IRWST Injection Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface"

3. SV4-PXS-MTK-800183 Rev 1,"IRWST Floor Elevation Comparison to DVI Nozzle Centerline Elevation"

4. 2.2.03.08c.iv.01-U4-CP-Rev 0, ITAAC Completion Package