ND-18-0621, Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02a.ii.a (Index Number 764)
| ML18131A218 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/09/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0621 | |
| Download: ML18131A218 (12) | |
Text
A 1
Michael J. Yox 7825 River Road fSk. Southern Nuclear MAY 0 9 2018 Docket Nos.:
52-025 52-026 Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0621 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.a [Index Number 764]
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 3.3.00.02a.ii.a [Index Number 764] has not been completed greater than 225-days priorto initial fuel load. The Enclosure describes the plan for completingthis ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days priorto initial fuel load.
This notification is informed by the guidance described in NEI 08-01, Industry Guidelinefor 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 NRCto 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. Yo>c
/
Regulatory Affairs Dir/ectorVogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Completion Plan for Uncompleted ITAAC 3.3.00.02a.ii.a [Index Number 764]
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U.S. Nuclear Regulatory Commission ND-18-0621 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. McKinney Mr. M. J. Vox 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 Reaulatorv 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 Ooiethoroe Power Corporation Mr. R. B. Brinkman
U.S. Nuclear Regulatory Commission ND-18-0621 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros 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 Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, 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. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0621 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-18-0621 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Compietion Plan for Uncompleted ITAAC 3.3.00.02a.ii.a[Index Number 764]
U.S. Nuclear Regulatory Commission ND-18-0621 Enciosure Page 2 of 8 ITAAC Statement Desion Commitment 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category Iand 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.
Acceptance Criteria ii.a) A report exists that concludes that the containment internal structures as-built concrete thicknesses 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 listedin Combined License (COL) Appendix C, Table 3.3-7 (Attachment A), are seismic Category Iand are designed and constructed to withstand design basis loads as specified in the Design Description, without lossof structural integrity andthe safety-related functions. The subject ITAAC requires an inspection be performed anddocumented in a report thatconcludes the as-built containment internal structures concrete wall thicknesses conform to the building sections defined in COL Appendix C, Table 3.3-1 (Attachment B).
Theinspections are performed of theas-built sections (following concrete placement) in accordancewith the requirements ofmeasurement guideline APP-GW-IT-001 (Reference 1),
which identifies the location and frequency of inspection pointsfordetermining wall thickness to ensure the resulting measurementsare representative ofthe entire section being inspected.
The measurements are based on the size and construction type of each section. Measurements are taken using surveyequipment in accordance with site surveyprocedures.
The inspection results are documented in the Unit 3 and Unit 4 principal closure documents (References 2 and 3,respectively) and summarized in Attachment Bwhich meets the ITAAC acceptance criteria.
References 1 thru 3 are availablefor NRG inspectionas part ofthe Unit 3 and Unit 4 ITAAC 3.3.00.02a.ii.a Completion Packages (Reference 4 and 5, respectively).
List of ITAAC Findings In accordance with plantproceduresfor ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining tothesubject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.
U.S. Nuclear Regulatory Commission ND-18-0621 Enclosure Page 3 of 8 References (available 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.
3.3.00.02a.ii.a-U3-CP-Rev0, ITAAC Completion Package 5.
3.3.00.02a.ii.a-U4-CP-Rev0, 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-18-0621 Enclosure Page 4 of 8 Attachment A Table 3.3-7, Nuclear Island Critical Structural Sections*
Containment internal Structures South west wall of the refueling cavity South wail of the west steam generator compartment North east wall of the in-containment refueling water storage tank in-containment refueling water storage tank steei waii Column supporting the operating floor Excerpt from COL Appendix C, Table 3.3-7
U.S. Nuclear Regulatory Commission ND-18-0621 Enclosure Page 5 of 8 Attachment B 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*
Concrete Thickness*
(2)(3)(4)(5)(8)
Inspection results +
Minimum recorded thickness Maximum recorded thickness Containment Building Internal Structure*
Shield Wall between Reactor Vessel Cavity and RCDT Room E-W wall parallel with column line 7 (Inside face is 3-0" north of column line
- 7. Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 71'-6" to 83'-0" 3'-0" X'-xx.x" Y'-yy.y" West Reactor Vessel Cavity Wall N-S wall parallel with column line N (Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 83'-0" to 98'-0" 7'-6" X'-xx.x" Y'-yy.y" North Reactor Vessel Cavity Wall E-W wall parallel with column line 7 (Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 83'-0" to 98'-0" 9'-0" X'-xx.x" Y'-yy.y" East Reactor Vessel Cavity Wall N-S wall parallel with column line N (Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 83'-0" to 98'-0" 7'-6" X'-xx.x" Y'-yy.y" West Refueling Cavity Wall N-S wall parallel with column line N From 98'-0" to135'-3" 4'-0" X'-xx.x" Y'-yy.y" North Refueling Cavity Wall E-W wall parallel with column line 7 From 98'-0" to 135'-3" 4'-0" X'-xx.x" Y'-yy.y"
U.S. Nuclear Regulatory Commission ND-18-0621 Enclosure Page 6 of 8 Wall or Section Description'^
Column Lines*
Floor Elevation or Elevation Range*
Concrete Thickness*
(2)(3)(4)(5)(8) inspection results +
Minimum recorded thickness Maximum recorded thickness Containment Building internal Structure*
East Refueling Cavity Wall N-S wall parallel with column line N From 98'-0" to 135'-3" 4'-0" X'-xx.x" Y'-yy.y" South Refueling Cavity Wall E-W wall parallel with column line 7 From 98'-0" to135'-3" 4'-0" X'-xx.x" Y'-yy.y" South wall of west steam generator compartment Not Applicable From 103'-0" to153'-0" 2'-6" X'-xx.x" Y'-yy.y" West wall of west steam generator compartment N-S wall parallel with column line N From 103'-0" to 153'-0" 2'-6" X'-xx.x" Y'-yy.y" North wall of west steam generator compartment Not Applicable From 103'-0" to 153'-0" 2'-6" X'-xx.x" Y'-yy.y" South wall of pressurizer compartment Not Applicable From 103'-0"to 153'-6" 2'-6" X'-xx.x" Y'-yy.y" West wall of pressurizer compartment N-S wall parallel with column line N From 107'-2"to 160'-0" 2'-6" X'-xx.x" Y'-yy.y" North wall of pressurizer compartment E-W wall parallel with column line 7 From 107'-2"to 160'-0" 2'-6" X'-xx.x" Y'-yy.y" East wall of pressurizer compartment N-S wall parallel with column line N From118'-6"to160'-0" 2'-6" X'-xx.x" Y'-yy.y"
U.S. Nuclear Regulatory Commission ND-18-0621 Enclosure Page 7 of 8 Wall or Section Description*
Column Lines*
Floor Elevation or Elevation Range*
Concrete Thickness*
(2)(3)(4)(5)(8)
Inspection results +
Minimum recorded thickness Maximum recorded thickness Containment Building Internal Structure*
North-east wall of in-containment refueling water storage tank Parallel to column line N From 103'-0" to 135'-3" 2'-6" X'-xx.x" Y'-yy.y" West wall of in-containment refueling water storage tank Not applicable From 103'-0" to 135'-3" 5/8" steel plate with stiffeners X'-xx.x" Y'-yy.y" South wall of east steam generator compartment Not Applicable From 87'-6"to153'-0" 2'-6" X'-xx.x" Y'-yy.y" East wall of east steam generator compartment N-S wall parallel with column line N From94'-0"to 153'-0" Z-6" X'-xx.x" Y'-yy.y" North wall of east steam generator compartment Not Applicable From 87'-6"to153'-0" with a 158'-0" portion 2'-6" X'-xx.x" Y'-yy.y" Notes:
- Excerpt from COL Appendix C, Table 3.3-1
+ Inspection results are Unit specific 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 constructiontolerance of +/- 1 inch, except as noted and forexteriorwalls belowgrade where the tolerance is +12 inches, -1 inch. These tolerances are not applicable to the nuclear island basemat.
U.S. Nuclear Regulatory Commission ND-18-0621 Enclosure Page 8 of 8
- 3. For walls that are part ofstructural 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 thickerthan the nominal 0.5 inches are used inthe construction ofthe structuralwall modules, the wall thicknesses inthe 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 withsteel 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 ofan item intersecting otherwalls, roofe orfloors 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 portionsextend to their associated roofs, which may vary inelevation, 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.