ND-22-0531, ITAAC Closure Notification on Completion of ITAAC 3.3.00.02f (Index Number 774)

ITAAC Closure Notification on Completion of ITAAC 3.3.00.02f (Index Number 774)

ML22196A094
Person / Time
Site:	Vogtle
Issue date:	07/15/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-22-0531
Download: ML22196A094 (7)

Text

>-. Southern Nuclear Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel Docket No.: 52-026 ND-22-0531 JUL 15 2022 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 3.3.00.02f [Index Number 774]

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 3.3.00.02f [Index Number 774] for verifying that the key dimensions of the as-built nuclear island structures are consistent with the dimensions defined on VEGP Unit 4 Combined License (COL) Appendix C Table 3.3-5. 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 ,

~~

Ja}rr(e M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 3.3.00.02f [Index Number 774]

JMC/GES/sfr

U.S. Nuclear Regulatory Commission ND-22-0531 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. D. Pitts Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE : VND .LI.L06 File AR.01 .02.06 cc:

Nuclear Regulatory Commission Mr. M . King Mr. G. Bowman 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. 0. Lopez-Santiago Mr. G . Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-22-0531 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S . M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S.L. Zwack Other Mr. S. W . Kline , Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr. , Ph .D., GOS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton , Balch Bingham

U.S. Nuclear Regulatory Commission ND-22-0531 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0531 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 3.3.00.02f [Index Number 774]

U.S. Nuclear Regulatory Commission ND-22-0531 Enclosure Page 2 of 4 IT AAC Statement Design Commitment 2.f) The key dimensions of nuclear island structures are defined on Table 3.3-5 .

Inspections/Tests/Analyses An inspection will be performed of the as-built configuration of the nuclear island structures.

Acceptance Criteria A report exists and concludes that the key dimensions of the as-built nuclear island structures are consistent with the dimensions defined on Table 3.3-5.

ITAAC Determination Basis Inspections of the as-built configuration of the nuclear island structures were conducted to confirm that the key dimensions of the as-built nuclear island structures are consistent with the dimensions defined on VEGP Unit 4 Combined License (COL) Appendix C Table 3.3-5 (Attachment A).

Inspection of the distance from the bottom of containment sump to top surface of embedded containment shell key dimension was performed per ITAAC 3.3.00.09 and is documented in the ITAAC Completion Package for ITAAC 3.3.00.09 (Reference 1). Inspection of the site grade level relative to the design plant grade floor elevation key dimension was performed per ITAAC 3.3.00.02b and is documented in the ITAAC Completion Package for ITAAC 3.3.00.02b (Reference 2). For the remainder of the key dimensions identified in Attachment A inspections were performed by surveying the as-built configuration of the nuclear island structures using survey equipment in accordance with site survey and measurement procedures. The results of the as-built measured dimensions are summarized in Attachment A. The as-built measured dimension inspection results were compared to the nominal dimensions defined in Attachment A to validate that the dimensions of the as-built nuclear island structures are consistent with the nominal dimensions defined on Attachment A.

The as-built measured dimension inspection results are documented in the Principal Closure Documents SV4-1000-ITR-800774 and SV4-1000-801774 (References 3 & 4) supporting the ITAAC 3.3.00.02f Completion Package (Reference 5) and verify that the key dimensions of the as-built nuclear island structures are consistent with the dimensions defined on VEGP Unit 4 COL Appendix C Table 3.3-5.

Principal Closure Documents SV4-1 000-ITR-800774 and SV4-1000-801774 (References 3 & 4) are available for NRG inspection as part of the ITAAC 3.3.00.02f Completion Package.

U.S. Nuclear Regulatory Commission ND-22-0531 Enclosure Page 3 of 4 ITAAC Finding Review 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. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.3.00.02f (Reference 5) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.02f 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. SV4-1100-ITR-800000, "ITAAC Summary Report for Vogtle Unit 4 ITAAC 3.3.00.09 (Unit 4 Concrete Thicknes from Containment Sump to Top Surface of Containment Shell)"

2. 3.3.00.02b-U4-CP-Rev0, ITAAC Completion Package

3. SV4-1000-ITR-80077 4, Rev. 0, "Unit 4 Key Dimensions of Nuclear Island Structures: (X1-X7) ITAAC 3.3.00.02f (774)"

4. SV4-1000-ITR-801774, Rev. 0, "Unit 4 Key Dimensions of Nuclear Island Structures:

(Vertical Dimensions) ITAAC 3.3.00.02f (774)"

5. 3.3.00.02f-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0531 Enclosure Page 4 of 4 Attachment A: Excerpt from VEGP Unit 4 COL Appendix C -Table 3.3-5 Nominal

• As-built Measured Tolerance

• Dimension Key Dimension Dimension Distance between Outside Surface of 91 ft-0 in +3 ft 90 ft-10 13/16 in walls at Column Line I & N when

-1 ft X1 (Ref. 3)

Measured at Column Line 1 Distance from Outside Surface of wall 138 ft-0 in +3 ft 138 ft-0 in at Column Line 1 to Column Line 7

-1 ft X2 (Ref. 3) when Measured at Column Line I Distance from Outside Surface of wall 118 ft-0 in +3 ft 117 ft-10 13/16 in at Column Line 11 to Column Line 7

-1 ft X3 (Ref. 3) when Measured at Column Line I Distance between Outside Surface of 117 ft-6 in +3 ft 117 ft-4 13/1 6 in walls at Column Line I & Q when

-1 ft X4 (Ref. 3)

Measured at Column Line 11 Distance from Outside Surface of wall 29 ft-0 in +3 ft 28 ft-10 13/16 in at Column Line Q to Column Line N

-1 ft X5 (Ref. 3) when Measured at Column Line 11 Distance between Outside Surface of 72 ft-6 in +3 ft 72 ft-6 in shield building wall to shield building

-1 ft X6 (Ref. 3) centerline when Measured on West Edqe of Shield Buildinq Distance between shield building 7 ft-6 in +/- 3 in 7 ft-6 in centerline to Reactor Vessel centerline X7 (Ref. 3) when Measured along Column Line N in North-South Direction Distance from Bottom of Containment 2 ft-8 in +/- 3 in 2 ft-8 7/8 in Sump to Top Surface of Embedded See Reference 1 Containment Shell Distance from top of Basemat to Design 33 ft-6 in +/- 1 ft Max 33 ft-6 1/4 in Plant Grade Min 33 ft-5 13/16 in (Ref. 4)

Distance of Design Plant Grade (Floor 0 ft +/- 3 ft-6 in elevation 100'-0") relative to Site Grade See Reference 2 Distance from Design Plant Grade to 229 ft-0 in +/- 1 ft Max 229 ft-0 7/16 in Top Surface of Shield Building Roof Min 228 ft-9 5/16 in (Ref. 4)

• Excerpt from VEGP Unit 4 COL Appendix C - Table 3.3-5