ND-20-0572, ITAAC Closure Notification on Completion of ITAAC 3.3.00.02q (Index Number 775)

ITAAC Closure Notification on Completion of ITAAC 3.3.00.02q (Index Number 775)

ML20136A495
Person / Time
Site:	Vogtle
Issue date:	05/15/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0572
Download: ML20136A495 (6)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tel MAY 1 5 2020 Docket No.: 52-026 ND-20-0572 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 4 ITAAC Closure Notification on Completion of ITAAC 3.3.00.02q [Index Number 7751 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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.02g [Index Number 775]

for verifying the containment vessel maximum inside height from the operating deck is 146'-7" (with tolerance of +12", -6"), and the inside diameter is 130 feet nominal (with tolerance of +12", -6").

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, 14L Michael J. Yox Regulatory Affairs Directbr Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 3.3.00.02g [Index Number 775]

MJY/JFV/sfr

U.S. Nuclear Regulatory Commission ND-20-0572 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. D. H. Jones(w/o enclosures)

Mr. G. Chick Mr. M. Page Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak 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 M W. Jones (w/o enclosures)

M C. P. Patel M G. J. Khourl Ms. S. E. Temple M N. D. Karlovlch M . A. Lerch M C. J. Even M B. J. Kemker Ms. N. C. Coovert C. Welch J. Gaslevic V. Hall

. G. Armstrong Ms. T. Lamb M. Webb T. Fredette

. C. Weber

. S. Smith C. Santos

s. M. Bailey

. S. Rose B. Davis

. J. Vasquez J. Eargle Ms. K. Carrington P. Heher

. M. King E. Davidson

U.S. Nuclear Regulatory Commission ND-20-0572 Page 3 of 3 Qqiethorpe 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. C. Durham (w/o enclosures)

Mr. M. M. CorlettI Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hesler, 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 Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-20-0572 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-0572 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 3.3.00.02g [Index Number 775]

U.S. Nuclear Regulatory Commission ND-20-0572 Enclosure Page 2 of 3 ITAAC Statement Deslan Commitment 2.g) The containment vessel above the operating deck provides a heat transfer surface. A free volume exists inside the containment shell above the operating deck.

Inspections. Tests. Analvsis The maximum containment vessel inside height from the operating deck is measured and the inner radius below the spring line is measured at two orthogonal radial directions at one elevation.

Acceptance Criteria The containment vessel maximum inside height from the operating deck is 146'-7"(with tolerance of +12", -6"), and the inside diameter is 130 feet nominal (with tolerance of +12", -6").

ITAAC Determination Basis The as-built maximum containment vessel inside height from the operating deck and the inner radius below the spring line at two orthogonal radial directions at one elevation were measured to determine that the containment vessel above the operating deck provides a heat transfer surface and a free volume exists inside the containment shell above the operating deck.

The maximum containment vessel inside height was measured by first determining the elevation of the operating deck,from four surveyed measurement locations on elevation 107'-2". The elevation of the highest inside point of the containment vessel was surveyed to determine the highest Z-coordinate called the apex. The maximum containment vessel inside height was then calculated as the range in difference between the containment vessel apex measurement and the highest operating deck height and the lowest operating deck height. The range of maximum inside height measurements from the operating deck were determined to be within the ITAAC acceptance criteria tolerance. All containment vessel inside height measurements and operating deck measurements were taken using survey equipment in accordance with site survey procedures(Reference 1).

To measure the radius of containment, due to physical constraints that exist at the center of containment, the center was determined using a survey scanner that measured seventeen radial points within a 128-degree angle on the west side of the containment. Once the center of containment was established, the measured radii for seventeen different points on the inner containment surface were plotted. The seventeen points plotted were within the 128-degree arc which satisfies the requirement for the measured radii to be orthogonal. The maximum and the minimum diameter were determined by multiplying by 2 the smallest and largest radius and were found to be within the ITAAC acceptance criteria tolerance. All radii measurements were surveyed at an elevation of 107'-2" which is below the spring line. The spring line is the height where the containment becomes cylindrical at elevation 244-2 as shown on Reference 2.

Containment inside diameter measurements were taken using survey equipment in accordance with site survey procedures(Reference 1).

U.S. Nuclear Regulatory Commission ND-20-0572 Enclosure Page 3 of 3 The measurement results are documented in the Unit 4 Principal Closure Document(Reference

3) and confirm that the containment vessel maximum inside height from the operating deck is between 146'- 6 1/2" and 146'- 7 5/16", and the inside diameter is between 129'- 6 3/4" and 129'-11 1/16" which meets the ITAAC acceptance criteria.

References 1 through 3 are available for NRC inspection as part of the Unit 4 ITAAC completion package (Reference 4).

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 3.3.00.02g (Reference 4) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.02g was performed for VEGP Unit 4 and that the prescribed acceptance criteria were 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. 26139-000-4MP-T81C-N3201, Rev. 4,"Construction Survey"

2. SV4-1000-P2-901, Rev 5,"Nuclear Island General Arrangement, Sections A-A"

3. SV4-1000-FSK-800775, Rev. 0,"Vogtle Unit 4 Containment Vessel Inside Height from The Operating Deck and The Inside Diameter"

4. 3.3.00.02g-U4-CP-Rev0, ITAAC Completion Package