View source for ND-22-0105, ITAAC Closure Notification on Completion of ITAAC 3.3.00.02b (Index Number 770)

{{Adams
| number = ML22066A764
| issue date = 03/07/2022
| title = ITAAC Closure Notification on Completion of ITAAC 3.3.00.02b (Index Number 770)
| author name = Yox M
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05200026
| license number = 
| contact person = 
| case reference number = ITAAC 3.3.00.02b, ND-22-0105
| document type = Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Closure Notification (ICN), Letter type:ND
| page count = 8
}}

=Text=
{{#Wiki_filter:>-   Southern Nuclear                                Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4                706-848-6459 tel MAR O*7 2022 Docket No.:     52-026 ND-22-0105 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 3.3.00.02b [Index Number 770]
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 3.3.00.02b [Index Number 770]. This ITAAC verified that as-built site grade is consistent with design plant grade within the dimension 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 is 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 ,
Michael J. Yox Regulatory Affairs Direc or Vogtle 3 & 4

==Enclosure:==
Vogtle Electric Generating Plant (VEGP) Unit 4 Closure Notification on Completion of ITAAC 3.3.00.02b [Index Number 770]
MJY/TST/sfr

U.S. Nuclear Regulatory Commission ND-22-0105 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. J.B. Williams Mr. M. J. Yox 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 Nuclear Regulatory Commission Ms. M. Bailey 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 Mr. T. Fanelli Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-22-0105 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 Mr. J. L. Coward 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-22-0105 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-22-0105 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 3.3.00.02b [Index Number 770]

U.S. Nuclear Regulatory Commission ND-22-0105 Enclosure Page 2 of 5 ITAAC Statement Design Commitment:
2.b) Site grade level is located relative to floor elevation 100'-0" per Table 3.3-5.
Inspections, Tests, Analyses:
Inspection of the as-built site grade will be conducted.
Acceptance Criteria:
Site grade is consistent with design plant grade within the dimension defined on Table 3.3-5.
ITAAC Determination Basis Inspection of the as-built site grade was conducted to confirm that the site grade is consistent with design plant grade within the dimension defined on VEGP Unit 4 Combined License (COL)
Appendix C Table 3.3-5, row 1O (Attachment A) (Reference 1). VEGP Unit 4 COL Appendix C Section 1.1 , Definitions, defines site grade as the as-built elevation of the soil to the west side of the nuclear island (Reference 1). The design plant grade for VEGP is defined as 220'-0" above mean sea level (MSL) , which is equivalent to the 100'-0" elevation for the standard plant design (Reference 2).
An as-built site grade inspection was performed to demonstrate that the as-built elevation of the area to the west side of the nuclear island is at elevation 220' MSL within a tolerance of +/-3'-6". The tolerance of +/-3'-6" defined in the COL Appendix C is based on seismic and soil structure interaction considerations for the Auxiliary Building, Shield Building, and Containment (Reference
: 3) . The zone of influence of soil characteristics on the structural response of an embedded structure is generally considered to extend horizontally away from the structure the same distance as the depth of the embedment. For VEGP, this distance is approximately 40 feet from the auxiliary and shield buildings (Reference 3). The Power Block Grading Plan (Reference 5) has details of the site grading in the vicinity of the nuclear island , including local slope to encourage runoff away from the doorways of the buildings.
The site grade was determined with a walkdown and field survey of locations of as-built structures that are at elevations of 100'-0" or lower (see Attachment Band Figure 1). The inspection involved a survey of storm drain covers using the Power Block Grading Plan (Reference 5) . Measurements were taken using survey equipment in accordance with site survey procedures (Reference 6). The measured elevations of the four storm drain covers were compared to floor elevation 100'-0" and within a tolerance of+/- 3'-6".
The as-built site grade inspection results are documented in Attachment B and Principal Closure Document "ITAAC Technical Report, Unit 4 Inspection of the As-Built Site Grade: ITAAC 3.3.00.02b" (Reference 4) . The inspection determined that the as-built site grade is consistent with design plant grade within the dimension defined on Table 3.3-5 (+/- 3'-6").

U.S. Nuclear Regulatory Commission ND-22-0105 Enclosure Page 3 of 5 The inspection Principal Closure Document (Reference 4) is available for NRC inspection as part of the ITAAC Completion Package (Reference 7).
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 3.3.00.02b (Reference 7) and is available for NRC review.
ITAAC Completion Statement Based on the above information , SNC hereby notifies the NRC that ITAAC 3.3.00.02b was performed for VEGP Unit 4 and that the prescribed acceptance criteria are 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. Combined License Vogtle Electric Generating Plant Unit 4 Appendix C, Amendment 186
: 2. VEGP 3&4 Updated Final Safety Analysis Report, Revision 10.1
: 3. NUREG-1793 Supplement 2, Final Safety Evaluation Report Related to Certification of the AP1000 Standard Plant Design Docket No. 52-006
: 4. SV4-0000-ITR-800770, Rev. 0, "Unit 4 Inspection of the As-Built Site Grade: ITAAC 3.3.00.02b, NRC Index Number: 770"
: 5. SV0-000-XG-800009 , Rev. 5, Power Block Grading Plan
: 6. 26139-000-4MP-T81 C-N3201, "Construction Survey" , Rev. 7
: 7. 3.3.00.02b-U4-CP-Rev0, ITAAC Completion Package
: 8. NEI 08-01 Rev. 5 corrected 6-30-2014, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52

U.S. Nuclear Regulatory Commission ND-22-0105 Enclosure Page 4 of 5 Attachment A Excerpt from VEGP Unit 4 COL Appendix C - Table 3.3-5*
Table 3.3-5*
Kev Dimensions of Nuclear Island Building Features Nominal Dimension
* Kev Dimension*                                               Tolerance*
Distance of Design Plant Grade                  0 ft                  +/- 3 ft-6 in (Floor elevation 100'-0") relative to Site Grade Attachment B Unit 4 Grading Plan Elevations for As-Built Structures Location west of      Distance from      Site Grading    Surveyed        Within+/- 3'-6" Nuclear Island      Nuclear Island     Plan Elevation    Elevation       tolerance of (approximate)      (in feet MSL) (in feet MSL)     Plant Grade?
Y/N Site Drainage cover           100'              218.50'       218.30'               y plate DI-Nl -15 Site Drainage cover           100'              218 .50'      217.93'               y plate DI-N 1-16 Site Drainage cover            80'              218.50'       218.04'               y plate DI-Nl-17 Site Drainage cover            90'              218.25'       218.07'               y plate DI-Nl-19 Note : Design Plant Grade is defined as 220'-0" MSL.

U.S. Nuclear Regulatory Commission ND-22-0105 Enclosure Page 5 of 5 Figure 1: Unit 4 Power Block Grading Plan with Survey Locations (Excerpt from Reference 5)
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FOR U IT 4 SITE GRAD ING E LARGEO AR EA CONDENSATE STOR AGE TA PJ ACILLAR
                                                         ~ATER STORAGE A EX BU I l TA&deg; K EL 220. 00 Vl 0..
I BE REMOVED STALLAT IO
: -800002)
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