ND-19-0185, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.03b (Index Number 778)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.03b (Index Number 778)

ML19059A376
Person / Time
Site:	Vogtle
Issue date:	02/28/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0185
Download: ML19059A376 (10)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel FEB 2 8 2019 Docket Nos.: 52-025 52-026 ND-19-0185 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 3.3.00.03b findex Number 7781 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 21, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.03b

[Index Number 778] 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 hJotifications 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 i/ v Regulatory Affairs Directo/Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.03b [Index Number 778]

MJY/PGUsfr

U.S. Nuclear Regulatory Commission ND-19-0185 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 Reoulatorv 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 Oolethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-19-0185 Page 3 of 3 Westinahouse Electric Company. LLC Dr. L. Oriani(w/o enclosures)

Mr. D. C. 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, Balch BIngham

U.S. Nuclear Regulatory Commission ND-19-0185 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-19-0185 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Pian for Uncompleted ITAAC 3.3.00.03b [Index Number 778]

U.S. Nuclear Regulatory Commission NE)-19-0185 Enctosure Page 2 of 7 ITAAC Statement Design Commitment

3. Walls and floors of the nuclear island structures as defined on Table 3.3-1 except for designed openings or penetrations provide shielding during normal operations.

I nspections/Tests/Analvses Inspection of the as-built nuclear island structures wall and floor thicknesses will be performed.

Acceptance Criteria b) A report exists and concludes that the shield walls of the shield building structures as defined in Table 3.3-1 except for designed openings or penetrations are consistent with the concrete wall thicknesses provided in Table 3.3-1.

ITAAC Completion Description Multiple ITAAC are performed to verify the walls and floors of the nuclear island structures as defined on Combined License(COL)Appendix C, Table 3.3-1 except for designed openings or penetrations provide radiation shielding during normal operation. The subject ITAAC requires that an inspection be performed and documented in a report that concludes that the shield walls of the shield building structures as defined in Table 3.3-1 except for designed openings or penetrations are consistent with the concrete wall thicknesses provided 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 shield walls of the shield building structures as defined in Table 3.3-1 except for designed openings or penetrations are consistent with the concrete wall thicknesses provided in Table 3.3-1.

References 1 thru 4 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 3.3.00.03b 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 associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-19-0185 Enclosure Page 3 of 7 References favailable 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. 3.3.00.03b U3-CP-Rev 0 ITAAC Completion Package

6. 3.3.00.03b U4-CP-Rev 0 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-19-0185 Enclosure Page 4 of 7 Attachment A Excerpt from COL Appendix C, Table 3.3-1*

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

Applicable Inspection results +

Wall or Radiation Column Floor Elevation or Concrete Thickness*

Section (2)(3)(4)(5)(9) Shielding Lines* Elevation Range*

Description* Wail Minimum Maximum (Yes/No)* recorded recorded thickness thickness Shieid Building*

Shield Not From 100'-0"to248'-6" 3'-0" (including Yes X'-xx.x" Y'-yy.y" Building Applicable 3/4 inch thick min.

Cylinder steel plate liner on each face on portion not protected by auxiliary building)

U.S. Nuclear Regulatory Commission ND-19-0185 Enclosure Page 5 of 7 Applicable Inspection results +

Wall or Radiation Column Floor Elevation or Concrete Thickness*

Section (2)(3)(4)(5)(9) Shielding Lines* Elevation Range*

Description* Wall Minimum Maximum (Yes/No)* recorded recorded thickness thickness Shield Building*

Air Inlet Not From248'-6" to 251'-6" 3'-0" (Including Yes X'-xx.x" Y'-yy.y" Applicable 3/4 inch thick min.

steel plate liner on each face)

From 251'-6" to 254'-6" 3'-0" to 4'-6" Yes X'-xx.x" Y'-yy.y" (including 1 inch thick steel plate liner on each face)

From 254'-6" to 266'-4" 4'-6" (including 1 inch X'-xx.x" Y'-yy.y" thick min. steel plate Yes liner on each face)

Tension Ring Not From 266'-4"to27r-6" 4'-6" (including Yes X'-xx.x" Y'-yy.y" Applicable (at top of 1-1/2 inch thick steel plate) plate liner on each face)

U.S. Nuclear Regulatory Commission ND-19-0185 Enclosure Page 6 of 7 Applicable Inspection results +

Wall or Radiation Column Floor Elevation or Concrete Thickness*

Section (2)(3)(4)(5)(9) Shielding Lines* Elevation Range*

Description* Wall Minimum Maximum (Yes/No)* recorded recorded thickness thickness Shield Building* <^)

Conical Roof Not From271'-6"to293'-9" 3'-0" (Including Yes X'-xx.x" Y'-yy.y" Applicable 1/2 Inch thick min.

steel plate liner on bottom face, outside of PCS tank exterior wall)

PCS Tank Not From 293'-9" to 328'-9" 2'-0" Yes X'-xx.x" Y'-yy.y" External Applicable Cylindrical Wall PCS Tank Not From 309'-4" to 329'-0" r-6" Yes X'-xx.x" Y'-yy.y" Internal Applicable Cylindrical Wall

U.S. Nuclear Regulatory Commission ND-19-0185 Enclosure Page 7 of 7 Notes:

+ 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 wails 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 elevation ranges for the shield building items are rounded to the nearest inch.

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.