ND-19-1423, ITAAC Closure Notification on Completion of ITAAC 3.3.00.02a.ii.e (Index Number 768)

ITAAC Closure Notification on Completion of ITAAC 3.3.00.02a.ii.e (Index Number 768)

ML19340A024
Person / Time
Site:	Vogtle
Issue date:	12/06/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1423
Download: ML19340A024 (11)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel DEC 0 6 2019 Docket No.: 52-025 ND-19-1423 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 3.3.00.02a.ii.e [Index Number 7681 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 3.3.00.02a.ii.e [Index Number 768]for verifying that the as-built concrete thicknesses of the annex building sections conform with the building sections defined in Table 3.3-1, except for designed openings or penetrations, or the report documents an evaluation of thickness deviations identified during construction and demonstrates that the as-built structures will withstand the design basis loads without loss of structural integrity and without impacting compliance with the radiation protection licensing basis.

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 3.3.00.02a.ii.e [Index Number 768]

MJY/PGL/sfr

U.S. Nuclear Regulatory Commission ND-19-1423 Page 2 of 3 To:

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

M . D. L. McKinney (w/o enclosures)

M M. D. Meier (w/o enclosures)

M D. H. Jones(w/o enclosures)

M G. Chick M M. Page M P. Martino M M. J. Yox M A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Mr. W. Jones (w/o enclosures)

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Mr. C. Santos Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1423 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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 Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS 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-19-1423 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-19-1423 Enclosure Vogtle Electric Generating Riant(VEGP) Unit 3 Completion of ITAAC 3.3.00.02a.ii.e [Index Number 768]

U.S. Nuclear Regulatory Commission ND-19-1423 Enclosure Page 2 of 8 ITAAC Statement Design Commitment 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category i and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions.

4.a) Wails and floors of the annex building as defined on Table 3.3-1 except for designed openings or penetrations provide shielding during normal operations.

inspections. Tests. Analvses ii) An inspection of the as-built concrete thickness will be performed.

Acceptance Criteria ii.e) A report exists that concludes that the as-built concrete thicknesses of the annex building sections conform with the building sections defined in Table 3.3-1, except for designed openings or penetrations, or the report documents an evaluation of thickness deviations identified during construction and demonstrates that the as-built structures will withstand the design basis loads without loss of structural integrity and without impacting compliance with the radiation protection licensing basis.

ITAAC Determination Basis Multiple ITAAC are performed to verify the nuclear island structures, including the critical sections listed in Combined License(COL) Appendix C, Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions. The subject ITAAC requires that an inspection be performed and documented in a report that exists and concludes that the as-built annex building sections concrete wall thicknesses conform with the building sections defined in COL Appendix C, Table 3.3-1 (Attachment A), except for designed openings or penetrations, or the report documents an evaluation of thickness deviations identified during construction and demonstrates that the as-built structures will withstand the design basis loads without loss of structural Integrity and without impacting compliance with the radiation protection licensing basis.

The inspections were performed of the as-built sections (following concrete placement) in accordance with the requirements of measurement guideline APP-GW-IT-001 (Reference 1),

which identified the location and frequency of inspection points for determining wall thickness to ensure the resulting measurements were representative of the entire section being inspected.

The measurements were based on the size and construction type of each section.

Measurements were taken using survey equipment in accordance with the site survey procedure (Reference 2).

U.S. Nuclear Regulatory Commission ND-19-1423 Enclosure Page 3 of 8 The inspection results contained in the Unit 3 Annex Building Concrete Thickness Verifications (Reference 3) and summarized in Attachment A conclude that the as-built concrete thicknesses of the annex building sections conform with the building sections defined in ITAAC Table 3.3-1, except for designed openings or penetrations.

References 1 through 3 are available for NRC inspection as part of the Unit 3 ITAAC 3.3.00.02a.ii.e 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 were no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.3.00.02a.ii.e (Reference 4)and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.02a.ii.e 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. APP-GW-IT-001, Revision 0,"Guidelines for Concrete Wall and Slab Thickness Measurements"

2. 26139-000-4MP-T81C-N3201, Rev. 5,"Construction Survey"

3. SV3-4000-ITR-800768, Rev. 0,"Unit 3 Annex Building Concrete Thickness Verifications"

4. 3.3.00.02a.ii.e-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-19-1423 Enclosure Page 4 of 8 Attachment A Excerpt from COL Appendix C, Table 3.3-1*

Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building'^'

Applicable Inspection results Wall or Section Floor Elevation or Concrete Column Lines* Radiation Description* (7) Elevation Range* Thickness* Shielding Wall Minimum Maximum (7)(8) (2){3)(4)(5)(9)(18)

(Yes/No)* reported reported thickness thickness Annex Building*

Column line 2 wall From 107'-2" to From E to H 19 3/4" Yes r-7.81" 135'-3" r- 8.50" Column line 4 wall From 107'-2" to From E to H 2'-0" Yes 1'-11.13" 162'-6" & 166'-0" 2'-0.98" N-S Shield Wall From 107'-2" to From 2 to 4 r-o" Yes 0'-11.50" between E and F 135'-3" 1'-0.19" Column line 4.1 wall From 107'-2" to From E to H 2'-0" Yes 1'-11.25" 135'-3" 2'-0.19" N-S Labyrinth Wall between column line From lOO'-O" to Not Applicable 2'-0" Yes r-11.44" 2'-0.25" 7.8 and 9 and G to H 112'-0" E-W Labyrinth Wall between column line From 10O'-O" to 7.1 and 7.8 and G to Not Applicable 2'-0" Yes 2'-0.06" 2'-0.38" 112'-0" H

U.S. Nuclear Regulatory Commission ND-19-1423 Enclosure Page 5 of 8 Attachment A Excerpt from COL Appendix C, Table 3.3-1*

Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building'^'

Applicable Inspection results Wall or Section Floor Elevation or Concrete Radiation Column Lines*

Description* (7) Elevation Range* Thickness* Shielding Wail Minimum Maximum (7)(8) (2)(3)(4)(5)(9)(18)

(Yes/No)* reported reported thickness thickness From E to Column Line 9 wall connecting wall From 107-2" to 2'-0" Yes 1'-11.25" T-11.98" between G and 117-6" H

From lOO'-O" to Column Line E wall From 9 to 13 2'-0" Yes 1'-11.75" 135'-3" 2'-0.88" From lOO'-O" to Column Line 13 wall From E to 1.1 2'-0" Yes 1'-11.50" 2'-0.69" 135'-3" From 11.09 to From lOO'-O" to Column Line 1.1 wall 2'-0" Yes 1'-11.04" 13 135'-3" 2'-0.13" Corridor Wall From 9 to near From 10O'-O" to between G and H 13 1'-6" Yes 1'-5.75" 1'-6.50" 117-6 Corridor Wall From 117-6" to From 9 to 13 r-6" Yes 1'-5.44" 1'-6.13" between G and H 135'-3 From 117-6" to Column Line 9 wall From E to H 2'-0" Yes 1'-11.13" 158'-0 2'-0.69" From 2 to 4 and Floor 135-3 0'-8" Yes EtoH 0'-7.88" 0'-8.31" From 4 to 4.1 Floor 135'-3 1'-0" (^2) Yes and E to H 0'-11.56" 1'-0.44"

U.S. Nuclear Regulatory Commission ND-19-1423 Enclosure Page 6 of 8 Attachment A Excerpt from COL Appendix C, Table 3.3-1*

Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building'^)

Appiicable Inspection results Wall or Section Floor Elevation or Concrete Radiation Column Lines*

Description* (7) Elevation Range* Thickness* Shielding Wali Minimum Maximum (7)(8) (2)(3){4)(5)(9)(18)

(Yes/No)* reported reported thickness thickness From 9 to 13 Floor 117'-6 0'-8" <^2)(13) Yes and E to 1.1 0'-7.50" 0'-8.94" From 9 to 13 Floor 135'-3 0'-8" (^2) Yes and E to 1.1 0'-7.69" 0'-8.75" Containment Filtration Between column From 135'-3" to Rms A and B (North r-o" Yes 0'-11.69" line E to H 158'-0 1'-0.38" Wall)

Containment Filtration Between column From 135'-3" to Rms A and 8(East r-o" Yes 1'-0.50" line E to F 158'-0 1'-0.94" wall)

Containment Filtration Between column 135'-3 1'-0" (12) Yes Rm A (Floor) line E to H 0'-11.56" 1'-0.44" Containment Filtration Between column Rm B (Floor) 150'-3 0'-8" Yes 0'-7.56" 0'-8.63" line E to H

U.S. Nuclear Regulatory Commission ND-19-1423 Enclosure Page 7 of 8 Attachment A

1. The column lines and floor elevations are identified and included on Figures 3.3-1 through 3.3-13.

2. These wall(and floor) thicknesses have a construction tolerance of +/- 1 inch, except as noted and for exterior walls below grade where the tolerance is +12 inches,-1 inch. These tolerances are not applicable to the nuclear island basemat.

3. For walls that are part of structural modules,the concrete thickness also includes the steel face plates. Where faceplates with a nominal thickness of 0.5 inches are used in the construction of the wall modules,the wall thicknesses in this column apply. Where faceplates thicker than the nominal 0.5 inches are used in the construction of the structural wall modules,the wall thicknesses in the area of the thicker faceplates are greater than indicated in this column by the amount of faceplate thickness increase over the nominal 0.5 inches Overlay plates are not considered part of the faceplates, and thus are not considered in the wall thicknesses identified in this column.

4. For floors with steel surface plates, the concrete thickness also includes the plate thickness.

5. Where a wall (or a floor) has openings,the concrete thickness does not apply at the opening.

6. Not used

7. The Wall or Section Description, Column Line information, and Floor Elevation or Elevation Ranges are provided as reference points to define the general location. The concrete thickness of an item intersecting other walls, roofs or floors at a designated location (e.g.,

column line) is not intended to be measured to the stated column line, but only to the point where the intersection occurs.

8. Where applicabie, the upper wall portions extend to their associated roofs, which may vary in elevation, e.g., sloped roofs.

9. From one wall/floor section to another,the concrete thickness transitions from one thickness to another, consistent with the confiaurations in Figures 3.3-1 through 3.3-14. ^

10. Not used

11. Not used

12. The concrete thickness is the total floor thickness, including the metal decking, where applicable.

13. The concrete in the kitchen and restroom areas is 2 inches thinner.

14. Not used

15. Not used

16. Construction deviations in the annex building from the thickness and tolerances specified in this table are evaluated in the thickness report to demonstrate that the as-built structures will withstand design basis loads without loss of structural integrity or safety functions and

U.S. Nuclear Regulatory Commission ND-19-1423 Enclosure Page 8 of 8 without impacting compliance with the radiation protection licensing basis, such as GDC 19, established radiological zoning and equipment qualification in accordance with ITAAC 3.3.00.02a.ii.e.

17. Not used

18. Nonconformances from the thicknesses and tolerances specified in Table 3.3-1 (i.e. out of tolerance conditions) are addressed under the 10 CFR Part 50, Appendix B process and subsequently are screened in accordance with the 10 CFR Part 52, Appendix D, Section VIII process,to ensure that the licensing basis is adequately maintained. Construction deviations will continue to be assessed against the licensing basis requirements and will be addressed in accordance with licensee procedures and regulatory requirements and if applicable, a license amendment will be obtained prior to implementation of the change.