ND-20-0655, 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)

ML20314A250
Person / Time
Site:	Vogtle
Issue date:	11/06/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0655
Download: ML20314A250 (7)

Text

Michael J. Yox 7825 River Road Sk Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel NOV 0 6 2020 Docket No.: 52-025 ND-20-0655 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 3 ITAAC Closure Notification on Completion of ITAAC 3.3.00.02f [Index Number 7741 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 3 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 3 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 Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 3.3.00.02f [Index Number 774]

MJY/JFV/sfr

U.S. Nuclear Regulatory Commission ND-20-0655 Page 2 of3 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. 8. Stimac Mr. P. Martino Mr. M. J. Vox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. 0. T. Defnall Mr. C. E. Morrow Mr. R. L. Beiike Mr. 8. Leighty Ms. A. 0. 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)

M M. King M H. K. Nieh 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 8. Smith M C. Santos M s. M. Bailey M B. Davis M J. Vasquez M J. Eargle M E. Davidson M T. Fanelli M 8. Rose Ms. K. McCurry

U.S. Nuclear Regulatory Commission ND-20-0655 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 Dalton Utilities Mr. T. Bundros Westinqhouse 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, Batch Bingham

U.S. Nuclear Regulatory Commission ND-20-0655 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-0655 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Compietion of ITAAC 3.3.00.02f[Index Number 774]

U.S. Nuclear Regulatory Commission ND-20-0655 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 2.f) The key dimensions of nuclear island structures are defined on Table 3.3-5.

I nspections/Tests/Analvses 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 3 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 SV3-1000-ITR-800774 and SV3-1000-801774(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 3 COL Appendix C Table 3.3-5.

Principal Closure Documents SV3-1000-ITR-800774 and SV3-1000-801774(References 3 & 4) are available for NRC inspection as part of the ITAAC 3.3.00.02f Completion Package.

U.S. Nuclear Regulatory Commission ND-20-0655 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 ComDietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.02f was performed for VEGP Unit 3 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. SVP_SV0_002198, Attachment 2, ITAAC 3.3.00.09 Unit 3 Completion Package.

2. 3.3.00.02b-U3-CP-Rev0, ITAAC Completion Package.

3. SV3-1000-ITR-800774, Rev. 0; Unit 3 Key Dimensions of Nuclear Island Structures:(X1-X7)

ITAAC 3.3.00.02f (774).

4. SV3-1000-ITR-801774, Rev. 1; Unit 3 Key Dimensions of Nuclear Island Structures:

(Vertical Dimensions) ITAAC 3.3.00.02f (774).

5. 3.3.00.02f-U3-CP-Rev0 ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-20-0655 Enclosure Page 4 of 4 Attachment A: Excerpt from VEGP Unit 3 COL Appendix 0- Table 3.3-5 Nominal 1

• As-built Measured

• Tolerance Key Dimension Dimension Dimension Distance between Outside Surface 91 ft-0 in +3 ft 90 ft-9 5/8 in of walls at Column Line 1 & N when Measured at Column Line 1 -1 ft XI (Ref. 3)

Distance from Outside Surface of 138 ft-0 in +3 ft 138 ft-0 in wall at Column Line 1 to Column Line 7 when Measured at Column -1 ft X2(Ref. 3)

Line 1 Distance from Outside Surface of 118 ft-0 in +3 ft 118 ft-0 in wall at Column Line 11 to Column Line 7 when Measured at Column -1 ft X3(Ref. 3)

Line 1 Distance between Outside Surface 117ft-6 in +3 ft 116ft-7 3/16in of walls at Column Line 1 &0 when Measured at Column Line 11 -1 ft X4(Ref. 3)

Distance from Outside Surface of 29 ft-0 in +3 ft 29 ft-0 in wall at Column Line 0 to Column Line N when Measured at Column -1 ft X5(Ref. 3)

Line 11 Distance between Outside Surface 72 ft-6 in +3 ft 72 ft-6 in of shield building wall to shield building centerline when Measured -1 ft X6 (Ref. 3) on West Edge of Shield Building Distance between shield building 7 ft-6 in +/-3 in 7 ft-6 in centerline to Reactor Vessel centerline when Measured along X7(Ref. 3)

Column Line N in North-South Direction Distance from Bottom of 2 ft-8 in +/-3 in 2ft-10in Containment Sump to Top Surface of Embedded Containment Shell See Reference 1 Distance from top of Basemat to 33 ft-6 in +/- 1 ft Max 33 ft-6 1/4 in Design Plant Grade Min 33ft-5 13/16 in (Ref. 4)

Distance of Design Plant Grade Oft +/- 3ft-6 in (Floor elevation 100'-0") relative to Site Grade See Reference 2 Distance from Design Plant Grade 229 ft-0 in +/-1 ft Max 229 ft-0 1/16 in to Top Surface of Shield Building Min 228 ft-8 13/16 in Roof (Ref. 4) 1 Excerpt from VEGP Unit 3 COL Appendix C - Table 3.3-5