ND-18-0618, 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
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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 Unit4 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 NuclearOperating Company hereby notifiesthe 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 laterdate, provide additional notifications for ITAAC that have not beencompleted 225-days prior to initial fuel load.
This notification is informed by the guidance described in NEI 08-01, IndustryGuideline for the ITAACClosure 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 provideshieldingduring normal operations.
Insoections/Tests/Analvses Inspection ofthe as-built nuclear island structureswall and floor thicknesses will be performed.
Acceptance Criteria a) Areport existsand concludesthat the shield walls and floors ofthe 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 thatthe walls of the nuclear island structures as defined on Combined License (COL) Appendix C, Table 3.3-1 except fordesigned openings or penetrations provide radiation shielding during normal operation. Thesubject ITAAC requires an inspection ofthe as-built shield walls and floors ofthe 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.
Theinspections are performed ofthe as-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 pointsfor determining wall thickness to ensurethe 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 usingsurvey equipment inaccordance with site survey procedures.
The inspection results are documented in the Unit 3 and Unit 4 principal closure documents (References 2 and3, respectively) andsummarized in theAttachment 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 NuclearOperating Company (SNC) performed a review ofall findings pertaining tothe subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings 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 Wall or Section Description*
Column Lines*
Floor Elevation or Elevation Range*
Concrete Thickness
- (2)(3)(4)(5)(8)
Applicable Radiation Shielding Wall (Yes/No)*
Inspection results+
Minimum recorded thickness Maximum recorded thickness Containment Building Internal Structure*
Shield Wall between Reactor Vessel Cavity and ROOT 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" Yes 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" Yes X'-xx.x" Y'-yy.y"
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 Wall or Section Description*
Column Lines*
Floor Elevation or Elevation Range*
Concrete Thickness
- (2)(3)(4)(5)(8)
Applicable Radiation Shielding Wall (Yes/No)*
Inspection results+
Minimum recorded thickness Maximum recorded thickness Containment Building Internal Structure*
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" Yes 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"(9)
Yes X'-xx.x" Y'-yy.y" West Refueling Cavity Wall N-S wall parallel with column line N From 98'-0" to 135'-3" 4'-0" Yes 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" Yes X'-xx.x" Y'-yy.y" East Refueling Cavity Wall N-S wall parallel with column line N From 98'-0" to 135'-3" 4'-0" Yes X'-xx.x" Y'-yy.y" South Refueling Cavity Wall E-W wall parallel with column line 7 From 98'-0" to 135'-3" 4'-0" Yes X'-xx.x" Y'-yy.y"
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 Wall or Section Description*
Column Lines*
Floor Elevation or Elevation Range*
Concrete Thickness
- (2)(3)(4)(5)(8)
Applicable Radiation Shielding Waii (Yes/No)*
inspection results-f Minimum recorded thickness Maximum recorded thickness Containment Building Internai Structure*
South wall of west steam generator compartment Not Applicable From 103'-0" to 153'-0" 2'-6" Yes 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" Yes X'-xx.x" Y'-yy.y" North wall of west steam generator compartment Not Applicable From 103'-0" to 153'-0" 2'-6" Yes X'-xx.x" Y'-yy.y" South wall of pressurizer compartment Not Applicable From 103'-0"to 153'-6" 2'-6" Yes 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" Yes X'-xx.x" Y'-yy.y North wall of pressurizer compartment E-W wall parallel with column line 7 From 107'-2" to160'-0" 2'-6" Yes X'-xx.x" Y'-yy.y East wall of pressurizer compartment N-S wall parallel with column line N From 118'-6"to 160'-0" 2'-6" Yes X'-xx.x" Y'-yy.y South wall of east steam generator compartment Not Applicable From 87'-6" to 153'-0" 2'-6"'
Yes X'-xx.x" Y'-yy.y East wall of east steam generator compartment N-S wall parallel with column line N From 94'-0" to 153'-0" 2'-6" Yes X'-xx.x" Y'-yy.y North wall of east steam generator compartment Not Applicable From 87'-6" to 153'-0" with a 158'-0" portion 2'-6" Yes X'-xx.x" Y'-yy.y
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.