ND-19-0390, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02a.ii.e (Index Number 768)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02a.ii.e (Index Number 768)

ML19108A264
Person / Time
Site:	Vogtle
Issue date:	04/18/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0390
Download: ML19108A264 (11)

Text

&. Southern Nuclear APR 1 8 2019 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket Nos.: 52-025 52-026 ND-19-0390 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 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.3.00.02a.ii.e [Index Number 7681 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 11, 2019, Vogtle Electric Generating Plant (VEGP) Unit 3 and IJnit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.02a.ii.e [Index Number 768] 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.

vyi Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.02a.ii.e [Index Number 768]

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U.S. Nuclear Regulatory Commission ND-19-0390 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (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. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown Ms. J. M. Heisserer 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. I. Cozens Mr. J. Gaslevic Mr. V. Hall Qqiethorpe 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

U.S. Nuclear Regulatory Commission ND-19-0390 Page 3 of 3 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 Ms. J. Monahan 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., GDS 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-19-0390 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-19-0390 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.02a.ii.e [Index Number 768]

U.S. Nuclear Regulatory Commission ND-19-0390 Enclosure Page 2 of 7 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.

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

Acceotance 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.

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 that an inspection be performed and documented in a report that 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).

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 procedures (Reference 2).

The inspection results contained in the Unit 3 and Unit 4 principal closure documents (References 3 and 4, respectively) 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.

References 1 thru 4 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 3.3.00.02a.ii.e Completion Packages (Reference 5 and 6, respectively).

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

U.S. Nuclear Regulatory Commission ND-19-0390 Erurfosure Page 3 of 7 associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References (available for NRG inspection)

1. APP-GW-IT-001, Revision 0, "Guidelines for Concrete Wall and Slab Thickness Measurements"

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

3. Principal Closure Document (Unit 3)

4. Principal Closure Document (Unit 4)

5. 3.3.00.02a.ii.e-U3-CP-Rev0, ITAAC Completion Package

6. 3.3.00.02a.ii.e-U4-CP-Rev0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0390 Enciosure Page 4 of 7 Attachment A Excerpt from COL Appendix C, Table 3.3-1*

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

Wall or Section Description*

Column Lines*

Floor Elevation or Elevation Range*

(6)(7)

Concrete Thickness*

(2)(3)(4)(5)(8)

Inspection results +

Minimum recorded thickness Maximum recorded thickness Annex Building*

Column line 2 wall From E to H From 107'-2" to 135'-3" 19 3/4" X'-xx.x" Y'-yy.y Column line 4 wall From E to H From 107'-2" to 162'-6" & 166'-0" 2'-0" X'-xx.x" Y'-yy.y" N-S Shield Wall between E and F From 2 to 4 From 107'-2" to 135'-3" r-o" X'-xx.x" Y'-yy.y" Column line 4.1 wall From E to H From 107'-2" to 135'-3" 2'-0" X'-xx.x" Y'-yy.y N-S Labyrinth Wall between column line 7.8 and 9 and G to H Not Applicable From lOO'-O" to 112'-0" 2'-0" X'-xx.x" Y'-yy.y E-W Labyrinth Waii between column line 7.1 and 7.8 and G to H Not Applicable From lOO'-O" to 112'-0" 2'-0" X'-xx.x" Y'-yy.y

U.S. Nuclear Regulatory Commission ND-19-0390 Enclosure Page 5 of 7 Wall or Section Description*

Column Lines*

Floor Elevation or Elevation Range*

(6)(7)

Concrete Thickness*

(2)(3)(4)(S)(8)

Inspection results +

Minimum recorded thickness Maximum recorded thickness Annex Building*

Column Line 9 wall From E to connecting wall between G and H From 107'-2" to 117'-6" 2'-0" X'-xx.x" Y'-yy.y" Column Line E wall From 9 to 13 From lOO'-O" to 135'-3" 2'-0" X'-xx.x" X'-xx.x" Column Line 13 wall From E to 1.1 From lOO'-O" to 135'-3" 2'-0" X'-xx.x" X'-xx.x" Column Line 1.1 wall From 11.09 to 13 From lOO'-O" to 135'-3" 2'-0" X'-xx.x" X'-xx.x" Corridor Wall between G and H From 9 to near 13 From lOO'-O" to 117'-6 r-6" X'-xx.x" X'-xx.x" Corridor Wall between G and H From 9 to 13 From 117'-6" to 135"-3 r-6" X'-xx.x" X'-xx.x" Column Line 9 wall From E to H From 117'-6" to 158'-0 2'-0" X'-xx.x" X'-xx.x" Floor From 2 to 4 and E to H

135'-3 0'-8" X'-xx.x" X'-xx.x" Floor From 4 to 4.1 and E toH 135'-3

\\ '-0" X'-xx.x" X'-xx.x"

U.S. Nuclear Regulatory Commission ND-19-0390 Enclosure Page 6 of 7 Wall or Section Description*

Column Lines*

Floor Elevation or Elevation Range*

(6)(7)

Concrete Thickness*

(2)(3)(4)(S)(8)

Inspection resuits +

Minimum recorded thickness Maximum recorded thickness Annex Buiiding*

Floor From 9 to 13 and E to 1.1 117'-6 O'-S" X'-xx.x" X'-xx.x" Floor From 9 to 13 and E to 1.1 135'-3 00 I

o X'-xx.x" X'-xx.x" Containment Filtration Rms A and B (North Wall)

Between column line E to H From 135'-3" to 158'-0 r-0" X'-xx.x" X'-xx.x" Containment Filtration Rms A and B (East wall)

Between column line E to F From 135'-3" to 158'-0 r-o" X'-xx.x" X'-xx.x" Containment Filtration Rm A (Floor)

Between column line E to H 135'-3 "1 '-0" X'-xx.x" X'-xx.x" Containment Filtration Rm B (Floor)

Between column line E to H 150'-3 pO o

X'-xx.x" X'-xx.x"

U.S. Nuclear Regulatory Commission ND-19-0390 Enclosure Page 7 of 7 Notes:

-I-Inspection results are Unit specific

• 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.

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. 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.

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

8. 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.

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

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