ND-18-0618, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.03a (Index Number 777)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.03a (Index Number 777)

ML18127A009
Person / Time
Site:	Vogtle
Issue date:	05/04/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0618
Download: ML18127A009 (10)

Text

j.l_ Kl I MichaelJ. Yox 7825 River Road jOUtnCrn NUCl0dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle3&4 706-848-6459 tel 410-474-8587 cell MAY 0 A 2018 fTiyox@soutfiernco.com Docket Nos.: 52-025 52-026 ND-18-0618 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 3.3.00.03a [Index Number 7771 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of May 1, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.03a [Index Number 777]

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 Direcfor Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.03a [Index Number 777]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0618 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

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

Mr. D. L. McKlnney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE; VND.LI.L06 File AR.01.02.06 cc:

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

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0618 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. Orlani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis 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-18-0618 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-18-0618 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.03a [Index Number 777]

U.S. Nuclear Regulatory Commission ND-18-0618 Enclosure Page 2 of 7 ITAAC Statement Desion 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.

Insoections/Tests/Analvses Inspection of the as-built nuclear island structureswall and floor thicknesses will be performed.

Acceptance Criteria a) A report exists and concludes that the shield walls and floors of the containment intemal 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 that the walls 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 an inspection ofthe as-built shield walls and floors of the containment internal structuresto verify they are consistent with the concrete wall thicknesses provided in COL Appendix C, Table 3.3-1, which is summarized in the Attachment.

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 ofthe 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.

The inspection results are documented in the Unit 3 and Unit 4 principal closure documents (References 2 and 3, respectively) and summarized in the Attachment which meets the ITAAC acceptance criteria.

References 1 thru 3 are available for NRG inspeciton as part of the Unit 3 and Unit 4 ITAAC 3.3.00.03a Completion Packages (Reference 4 and 5, 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-18-0618 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. Principal Closure Document (Unit 3)

3. Principal Closure Document (Unit 4)

4. 3.3.00.03a U3-CP-Rev 0 ITAAC Completion Package

5. 3.3.00.03a U4-CP-Rev 0 ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-18-0618 Enclosure Page 4 of 7 Attachment Table 3.3-1 Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Buiiding and Annex Buiiding Applicable Inspection Wall or Section Floor Elevation or Concrete Radiation results+

Column Lines*

Description* Elevation Range* Thickness Shielding Wall

• (2)(3)(4)(5)(8) Minimum Maximum (Yes/No)* recorded recorded thickness thickness Containment Building Internal Structure*

E-W wall parallel with column line 7 (Inside face is 3'-0" north of Shield Wall between column line 7. Width Reactor Vessel Cavity and of wall section with From 71'-6" to 83'-0" Yes X'-xx.x" Y'-yy.y ROOT Room stated thickness is defined by inside wall of reactor vessel cavity.)

N-S wall parallel with column line N (Width of wall section with West Reactor Vessel stated thickness is From 83'-0" to 98'-0" Yes X'-xx.x" Y'-yy.y" Cavity Wall defined by inside wall of reactor vessel cavity.)

U.S. Nuclear Regulatory Commission ND-18-0618 Enclosure Page 5 of 7 Attachment Table 3.3-1 Definition of Wall Thicknesses for Nuciear Isiand Buiidings, Turbine Building and Annex Building Applicable Inspection Wall or Section Floor Elevation or Concrete Radiation results+

Column Lines*

Description* Elevation Range* Thickness Shielding Wall

• (2)(3)(4)(5)(8) Minimum Maximum (Yes/No)* recorded recorded thickness thickness Containment Building Internal Structure*

E-W wall parallel with column line 7 (Width of North Reactor Vessel wall section with stated From 83'-0" to 98'-0" Yes X'-xx.x" Y'-yy.y" Cavity Wall thickness is defined by Inside wall of reactor vessel cavity.)

N-S wall parallel with column line N (Width of wall section with East Reactor Vessel stated thickness is From 83'-0" to 98'-0" 7'-6"(9) Yes X'-xx.x" Y'-yy.y" Cavity Wall defined by inside wall of reactor vessel cavity.)

West Refueling Cavity N-S wall parallel with From 98'-0" to 135'-3" 4'-0" Yes X'-xx.x" Y'-yy.y" Wall column line N North Refueling Cavity E-W wall parallel with From 98'-0" to 135'-3" 4'-0" Yes X'-xx.x" Y'-yy.y" Wall column line 7 N-S wall parallel with East Refueling Cavity Wall From 98'-0" to 135'-3" 4'-0" Yes X'-xx.x" Y'-yy.y" column line N South Refueling Cavity E-W wall parallel with From 98'-0" to 135'-3" 4'-0" Yes X'-xx.x" Y'-yy.y" Wall column line 7

U.S. Nuclear Regulatory Commission ND-18-0618 Enclosure Page 6 of 7 Attachment Table 3.3-1 Definition of Wall Thicknesses for Nuclear island Buildings, Turbine Building and Annex Building Applicable inspection Wall or Section Floor Elevation or Concrete Radiation results-f Column Lines*

Description* Elevation Range* Thickness Shielding Waii

• (2)(3)(4)(5)(8) Minimum Maximum (Yes/No)* recorded recorded thickness thickness Containment Building Internai Structure*

South wall of west steam Not Applicable From 103'-0" to 153'-0" 2'-6" Yes X'-xx.x" Y'-yy.y" generator compartment West wall of west steam N-S wall parallel with Yes X'-xx.x" Y'-yy.y" From 103'-0" to 153'-0" 2'-6" generator compartment column line N North wall of west steam Not Applicable From 103'-0" to 153'-0" 2'-6" Yes X'-xx.x" Y'-yy.y" generator compartment South wall of pressurizer Not Applicable From 103'-0"to 153'-6" 2'-6" Yes X'-xx.x" Y'-yy.y compartment West wall of pressurizer N-S wall parallel with Yes X'-xx.x" Y'-yy.y From 107'-2" to 160'-0" 2'-6" compartment column line N North wall of pressurizer E-W wall parallel Yes X'-xx.x" Y'-yy.y From 107'-2" to160'-0" 2'-6" compartment with column line 7 East wall of pressurizer N-S wall parallel with Yes X'-xx.x" Y'-yy.y From 118'-6"to 160'-0" 2'-6" compartment column line N South wall of east steam Not Applicable From 87'-6" to 153'-0" 2'-6"' Yes X'-xx.x" Y'-yy.y generator compartment East wall of east steam N-S wall parallel with From 94'-0" to 153'-0" 2'-6" Yes X'-xx.x" Y'-yy.y generator compartment column line N North wall of east steam From 87'-6" to 153'-0" Not Applicable 2'-6" Yes X'-xx.x" Y'-yy.y generator compartment with a 158'-0" portion

U.S. Nuclear Regulatory Commission ND-18-0618 Enclosure Page 7 of 7 Notes:

• Excerp from COL Appendix C, Table 3.3-1

+ Inspection results will be Unit specific

1. Thie column lines and floor elevations are identified and included on COL Appendix C, 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 wail 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. This wall thickness has a tolerance of +/- 1 -5/8 inch.