ND-20-0023, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02f (Index Number 774)
| ML20022A177 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/21/2020 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ND-20-0023 | |
| Download: ML20022A177 (7) | |
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Southern Nuclear JAN 2 1 202>>
Docket No.:
52-026 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-20-0023 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.3.00.02f [Index Number 7741 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 21, 2020, Vogtle Electric Generating Plant (VEGP) Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.02f [Index Number 774] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 3.3.00.02f [Index Number 774]. 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 the 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 Direct! r Vogtle 3 & 4
Enclosure:
MJYA/K/sfr Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.02f [Index No. 774]
U.S. Nuclear Regulatory Commission ND-20-0023 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)
Mr. D. L. McKlnney (w/o enclosures)
Mr. M. D. Meier (w/o enclosures)
Mr. D. H. Jones (w/o enclosures)
Mr. G. Chick Mr. M. Page Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Requlatorv Commission M
M M
Ms. S. E. Temple M
M M
M Ms. N. C. Coovert M
M M
M
. W. Jones (w/o enclosures)
C. P. Patel G. J. Khourl
. N. D. Karlovlch
. A. Lerch
. C. J. Even
. B. J. Kemker
. C. Welch
. J. Gaslevic
. V. Hall
. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Mr. C. Santos Mrs. M. Bailey Mr. S. Rose Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Carrlngton Mr. P. Heher
U.S. Nuclear Regulatory Commission ND-20-0023 Page 3 of 3 Mr. M. King Mr. E. Davidson Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Mr. M. M. Corletti Mr. Z. 8. Harper 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-20-0023 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-0023 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.02f [Index No. 774]
U.S. Nuclear Regulatory Commission ND-20-0023 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 2.f)
The key dimensions of nuclear island structures are defined on Table 3.3-5.
Inspections/T ests/Analvses An inspection will be performed of the as-built configuration of the nuclear island structures.
Acceptance Criteria A report exists and concludes that the key dimensions of the as-built nuclear island structures are consistent with the dimensions defined on Table 3.3-5.
ITAAC Completion Description Inspection of the as-built configuration of the nuclear island structures is conducted to confirm that the key dimensions of the as-built nuclear island structures are consistent with the dimensions defined on VEGP Unit 4 Combined License (COL) Appendix C Table 3.3-5 (Attachment A).
Inspection of the distance from bottom of containment sump to top surface of embedded containment shell key dimension is performed per ITAAC 3.3.00.09 and is documented in ITAAC Closure Notification Letter ND-14-1936, Vogtle Electric Generating Plant Unit 4 Completion of ITAAC 3.3.00.09 [Index Number 814] (Reference 1). Inspection of the site grade level relative to the design plant grade floor elevation key dimension is performed per ITAAC 3.3.00.02b and is documented in the ITAAC Completion Package for ITAAC 3.3.00.02b (Reference 2). For the remainder of the key dimensions identified in Attachment A an inspection is performed by surveying the as-built configuration of the nuclear island structures using survey equipment in accordance with site survey and measurement procedures. The results of the as-built measured dimensions are summarized in Attachment A. The as-built measured dimension inspection results are compared to the dimensions defined in Attachment A to validate that the dimensions of the as-built nuclear island structures are consistent with the dimensions defined on Attachment A.
The as-built measured dimension inspection results are documented in the Principal Closure Document XXX (Reference 3) supporting the ITAAC 3.3.00.02f Completion Package (Reference
- 4) and verify that the key dimensions of the as-built nuclear island structures are consistent with the dimensions defined on VEGP Unit 4 COL Appendix C Table 3.3-5.
Principal Closure Document XXX is available for NRC inspection as part of the ITAAC 3.3.00.02f Completion Package.
U.S. Nuclear Regulatory Commission ND-20-0023 Enclosure Page 3 of 4 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.
References favaiiabie for NRG inspection)
- 1. ND-14-1936, Vogtle Electric Generating Plant Unit 4 Completion of ITAAC 3.3.00.09 [Index Number 814]
- 2. 3.3.00.02b-U4-CP-Rev0, ITAAC Completion Package
- 3. Principal Closure Document XXX
- 4. 3.3.00.02f-U4-CP-Rev0, ITAAC Completion Package
- 5. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-20-0023 Enclosure Page 4 of 4 Attachment A Table 3.3-5, Key Dimensions of Nuclear Island Building Features*
Key Dimension*
Nominal Dimension*
Toierance*
As-buiit Measured Dimension Distance between Outside Surface of walls at Column Line 1 & N when Measured at Column Line 1 91 ft-0 in
+3 ft
-1 ft XX ft-yy in Distance from Outside Surface of wall at Column Line 1 to Column Line 7
when Measured at Column Line 1 138ft-0 in
+3 ft
-1 ft XX ft-yy in Distance from Outside Surface of wall at Column Line 11 to Column Line 7 when Measured at Column Line 1 118ft-0 in
+3 ft
-1 ft XX ft-yy in Distance between Outside Surface of walls at Column Line 1 & 0 when Measured at Column Line 11 117ft-6 in
+3 ft
-1 ft XX ft-yy in Distance from Outside Surface of wall at Column Line 0 to Column Line N when Measured at Column Line 11 29 ft-0 in
+3 ft
-1 ft XX ft-yy in Distance between Outside Surface of shield building wall to shield building centerline when Measured on West Edge of Shield Building 72 ft-6 in
+3 ft
-1 ft XX ft-yy in Distance between shield building centerline to Reactor Vessel centerline when Measured along Column Line N in North-South Direction 7
ft-6 in
+/- 3 in XX ft-yy in Distance from Bottom of Containment Sump to Top Surface of Embedded Containment Shell 2
ft-8 in
+/- 3 in See Reference 1 Distance from top of Basemat to Design Plant Grade 33 ft-6 in
+/-1 ft XX ft-yy in Distance of Design Plant Grade (Floor elevation 10O'-O") relative to Site Grade Oft
+/- 3 ft-6 in See Reference 2 Distance from Design Plant Grade to Top Surface of Shield Building Roof 229 ft-0 in
+/- 1 ft XX ft-yy in Notes:
Excerpt from COL Appendix C, Table 3.3-5