ND-21-0155, Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.iv.02 (Index Number 184)

Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.iv.02 (Index Number 184)

ML21070A335
Person / Time
Site:	Vogtle
Issue date:	03/11/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0155
Download: ML21070A335 (6)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tel MAR I 1 2021 Docket No.: 52-026 ND-21-0155 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.iv.02 [Index Number 1841 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 10, 2021, Vogtie Electric Generating Plant(VEGP) Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.iv.02 [Index Number 184] has not been completed greater than 225-days prior to initial fuel load. Enclosure 1 describes the plan for completing ITAAC 2.2.03.08c.iv.02 [Index Number 184]. Southern Nuclear Operating Company will at a later date provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Kelli Roberts 706-848-6991.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtie 3&4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.2.03.08c.iv.02 [Index Number 184]

MJY/RMS/sfr

U.S. Nuclear Regulatory Commission ND-21-0155 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

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

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

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. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Ms. M. Bailey (w/o enclosures)

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

U.S. Nuclear Regulatory Commission ND-21-0155 Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

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

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., GDS 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0155 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-21-0155 Enclosure 1 Vogtle Electric Generating Riant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.2.03.08c.iv.02[Index No. 184]

U.S. Nuclear Regulatory Commission ND-21-0155 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

I nspections/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 Completion Description 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 is performed using survey equipment in accordance with site survey and measurement procedure (Reference 1). The conservative wall thickness, derived from installed pipe data, is 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 is compared to the elevation of the bottom inside surface of the IRWST using a common reference point.

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

References 1 and 2 are available for NRC inspection as part of Unit 4 ITAAC 2.2.03.08c.iv.02 Completion Package (Reference 3).

U.S. Nuclear Regulatory Commission ND-21-0155 Enclosure Page 3 of 3 List of ITAAC Findings 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.

References favaiiable for NRG inspection)

1. 26139-000-4MP-T81C-N3201,"Construction Survey"

2. SV4-PXS-FSK-800184 Rev X,"As-Built IRWST Injection/Recirculation Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface"

3. ITAAC 2.2.03.08c.iv.02-U4-CP-Rev 0, ITAAC Completion Package

4. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"