ND-19-1494, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02a.ii.f (Index Number 769)

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Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02a.ii.f (Index Number 769)
ML19350C589
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 12/16/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1494
Download: ML19350C589 (8)
v • d • e


Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tel DEC 1 6 2019 Docket No.: 52-025 ND-19-1494 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 Notice of Uncompleted ITAAC 225-davs Prior to initial Fuel Load Item 3.3.00.02a.ii.f [Index Number 7691 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 9, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.02a.ii.f [Index Number 769] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

Southern Nuclear Operating Company(SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to initial Fuel Load for Item 3.3.00.02a.ii.f [Index Number 769] ND-19-1253

[ML19288A220], dated October 15, 2019. This resubmittal supersedes letter number ND-19-1253 in its entirety.

This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yoxf: ^

Regulatory AffairslDirector Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 Completion Plan for Uncompleted ITAAC 3.3.00.02a.ii.f [Index Number 769]

MJY/JV/sfr

U.S. Nuclear Regulatory Commission ND-19-1494 Page 2 of 3 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. 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. 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 Regulatory 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 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1494 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. 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-1494 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-19-1494 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion Plan for Uncompleted ITAAC 3.3.00.02a.ii.f [Index Number 769]

U.S. Nuclear Regulatory Commission ND-19-1494 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 2.a) The nuclear island structures, including the critical sections listed In 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.

Inspections.Tests. Analyses

11) An inspection of the as-built concrete thickness will be performed.

Acceptance Criteria ii.f) A report exists that concludes that the as-built concrete thicknesses of the turbine building sections conform to the building sections defined in Table 3.3-1, except for designated 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.

ITAAC Completion Description 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 an inspection be performed and documented in a report that concludes the as-built concrete thicknesses of the turbine building conform to 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.

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

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

The measurements are based on the size and construction type of each section. Measurements were taken using survey equipment in accordance with site survey procedures (Reference 2).

The inspection results are documented in the Unit 3 Turbine Building Concrete Thickness Verification (Reference 3) and summarized in Attachment A which meet the ITAAC acceptance criteria of COL Appendix C, Table 3.3-1. References 1 through 3 are available for NRC inspection as part of the Unit 3 ITAAC 3.3.00.02a.ii.f Completion Package (Reference 4).

List of ITAAC Findings 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.

U.S. Nuclear Regulatory Commission ND-19-1494 Enclosure Page 3 of 5 References(available for NRG inspection)

1. APP-GW-IT-001, Rev. 0,"Guidelines for Concrete Wall and Slab Thickness Measurements"
2. 26139-000-4MP-T81C-N3201, Rev. 5,"Construction Survey"
3. SV3-2100-ITR-800769, Rev. 0,"Unit 3 Turbine Building Concrete Thickness Verification"
4. 3.3.00.02a.ii.f-U3-CP-Rev 0, ITAAC Completion Package
5. NEI 08-01, Rev. 5,"Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-1494 Enclosure Page 4 of 5 Attachment A Table 3.3-1, Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building*'^^

Inspection results Concrete Wall or Section Floor Elevation or Column Lines* Thickness*

Description* Elevation Range* (2)(3)(4){5)(9)(18) Minimum Maximum recorded recorded thickness thickness Turbine Building*<")

Wall adjacent to From Col. Line 11.05 to 11.2 From lOO'-O" to 169'-0" 3'-0" X'-xx.x" Y'-yy.y" Column Line 1.2 Wall along Column From near 1.2 to near Col. Line R From lOO'-O" to 169'-0" 2'-0" X'-xx.x" Y'-yy.y" Line 11.2 Wall adjacent to From Col. Line 11.2 to Col. Line From lOO'-O" to 169'-0" 3'-0" X'-xx.x" Y'-yy.y" Column Line R 11.02 Wall along Column From near Col. Line R to near Col.

From lOO'-O" to 169'-0" 2'-0" X'-xx.x" Y'-yy.y" Line 11.02 Line Q Wall along Column From Col. Line K.4 to near Col.

From lOO'-O" to 169'-0" 2'-0" X'-xx.x" Y'-yy.y" Line 11.05 Line 1.2 Notes:

  • Excerpt from COL Appendix C, Table 3.3-1
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.

U.S. Nuclear Regulatory Commission ND-19-1494 Enclosure Page 5 of 5

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 Applicable in Turbine Building
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 applicable, 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 configurations in Figures 3.3-1 through 3.3-14.
10. Not Applicable in Turbine Building
11. Not Applicable in Turbine Building
12. Not Applicable in Turbine Building
13. Not Applicable in Turbine Building
14. Not Applicable in Turbine Building
15. Not Applicable in Turbine Building
16. Not Applicable in Turbine Building
17. Construction deviations in the turbine 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 of safety functions in accordance with ITAAC 3.3.00.02a.ii.f.
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 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 license procedures and regulatory requirements and, if applicable, a license amendment will be obtained prior to implementation of the change.
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