ND-21-0241, Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.iv.01 (Index Number 183)

Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.iv.01 (Index Number 183)

ML21075A026
Person / Time
Site:	Vogtle
Issue date:	03/15/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0241
Download: ML21075A026 (6)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel MAR 1 5 2021 Docket No.: 52-026 ND-21-0241 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.iv.01 [Index Number 1831 Ladles and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 10, 2021, Vogtle Electric Generating Plant (VEGP) Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.lv.01 [Index Number 183] 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.lv.01

[Index Number 183]. 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, emu Michael J. Yox Regulatory Affairs Director Vogtle 3&4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.2.03.08c.lv.01 [Index Number 183]

MJY/RMS/sfr

U.S. Nuclear Regulatory Commission ND-21-0241 Page 2 of 3 To:

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

Mr. D. L. McKinney (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 Requlatorv Commission Ms. M. Bailey (w/o enclosures)

Mr. M. King 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 M S. Rose Ms. K. McCurry Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-21-0241 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinohouse Electric Company. LLC Dr. L. OrianI (w/o enclosures)

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

Mr. M. M. Corletti Mr. Z. S. 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-0241 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-21-0241 Enclosure 1 Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC item 2.2.03.08c.lv.01 [Index No. 183]

U.S. Nuclear Regulatory Commission ND-21-0241 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:

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 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 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 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 are 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 IRWST injection lines top inside surface, the DVI nozzle centerline, and the 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-21-0241 Enclosure Page 3 of 3 The Inspection results are documented in the Principle Closure Documents(References 2 and 3). Reference 2 determined that the maximum elevation of the top inside surface of the IRWST injection lines and IRWST connection to DVI nozzles is xxx feet and are lower than the xxx foot elevation of the IRWST bottom inside surface. Reference 3 determined that both the DVI nozzle centerline elevations are xxx feet, which are xxx feet below the xxx foot elevation of IRWST bottom inside surface, and therefore both Acceptance Criteria are met.

Principal Closure Documents exist and are available for NRC inspection as well as the ITAAC 2.2.03.08c.iv.01 Completion Package.

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 lavaiiabie for NRC inspection)

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

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

3. SV4-PXS-MTK-xxxxxx Rev x, "IRWST Bottom Inside Tank Surface Comparison to DVI Nozzle Centerline Elevation"

4. 2.2.03.08c.iv.01-U4-CP-Rev 1, ITAAC Completion Package