ND-19-1253, Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.3.00.02a.ii.f (Index Number 769)

Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.3.00.02a.ii.f (Index Number 769)

ML19288A220
Person / Time
Site:	Vogtle
Issue date:	10/15/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-1253
Download: ML19288A220 (8)

Text

C -S-l-a ki I Michael J. Yox 7825 River Road

^OUtilGrn NUCi03r Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel OCT 1 5 2019 Docket No.: 52-025 ND-19-1253 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle 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 October 14, 2019, Vogtle 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.

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. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

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

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-19-1253 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. M. J. Vox 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 Requlatorv 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 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1253 Page 3 of 3 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 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., 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-1253 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-19-1253 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-19-1253 Enclosure Page 2 of 5 ITAAC Statement Desion 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.

I nspections.Tests.Analyses ii) 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.

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).

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 are taken using survey equipment in accordance with site survey procedure (Reference 2).

The inspection results are documented in Reference 3 and summarized in Attachment A which meets the ITAAC acceptance criteria.

References 1 thru 3 are available for NRG 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-19-1253 Enclosure Page 3 of 5 References ^available for NRG inspection)

1. APP-GW-IT-001,"Guidelines for Concrete Wall and Slab Thickness Measurements"

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

3. Principal Closure Document(Unit 3)

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

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

U.S. Nuclear Regulatory Commission ND-19-1253 Enclosure Page 4 of 5 Attachment A Table 3.3-1, Definition of Waii Thicknesses for Nuclear Island Buildings, Turbine Buiiding, and Annex Building*

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

Description* Elevation Range* (2)(3)(6) Minimum Maximum recorded recorded thickness thickness Turbine Buiiding*

Wail 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 Waii aiong 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 Waii adjacent to From Coi. Line 11.2 to Col. Line 11.02 From lOO'-O" to 169'-0" 3'-0" X'-xx.x" Y'-yy.y" Coiumn Line R Waii along Column From near Col. Line R to near Col. Line From lOO'-O" to 169'-0" 2'-0" X'-xx.x" Y'-yy.y" Line 11.02 Q Waii aiong Column From Col. Line K.4 to near Coi. Line 1.2 From lOO'-O" to 169'-0" 2'-0" X'-xx.x" Y'-yy.y" Line 11.05 Notes:

• Excerpt from COL Appendix C, Tabie 3.3-1 (Oniy iisted notes that appiy)

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

2. These waii (and fioor) thicknesses have a construction tolerance of +/- 1 inch, except as noted and for exterior waiis beiow grade where the toierance is +12 inches, -1 inch. These toierances are not appiicabie to the nuciear isiand basemat.

U.S. Nuclear Regulatory Commission ND-19-1253 Enclosure Page 5 of 5

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

4. 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 wails, 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.

5. Where applicable, the upper wail portions extend to their associated roofs, which may vary in elevation, e.g., sloped roofs.

6. 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.