ND-18-1394, Ittac Closure Notification on Completion of ITAAC 2.2.03.8c.iv.01 (Index Number 183)
| ML18316A008 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/09/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.2.03.08c.iv.01, ND-18-1394 | |
| Download: ML18316A008 (6) | |
Text
A MiehaelJ.Yox 7825 River Road SOU'tn0rn Nucl0dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tel 0 Otno 410-474-8587 cell NOV 0 9 2018 myox@southernco.conn Docket Nos.:
52-025 ND-18-1394 10CFR 52.99(G)(1)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 1831 Ladies and Gentlemen:
In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.iv.01 [Index Number 183] for verifying that the maximum elevation of the top inside surface of the In-containment Refueling Water Storage Tank (IRWST) injection lines and IRWST connection to Direct Vessel Injection (DVI) nozzles is less than the elevation of IRWST bottom inside surface and that the elevation of the IRWST bottom inside tank surface is higher than the DVI nozzle centerlines by s 3.4 ft. The closure process for this ITAAC is based on 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.
Southern Nuclear Operating Company (SNC) previously submitted ITAAC Closure Notice of Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 183] ND-18-1289 [ML18299A203] dated October 25, 2018. This resubmittal supersedes ND-18-1289 in its entirety.
This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.
Ifthere are any questions, please contact Tom Petrak at 706-848-1575.
Respectfully submitted, 7^
Michael J. Vox
^
)X Regulatory Affairs Director Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 183]
MJY/GDL/amw
U.S. Nuclear Regulatory Commission ND-18-1394 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. A. L. Pugh 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 Reaulatorv Commission Mr.W. Jones (w/o enclosures)
Mr. F. D. Brown Ms. J. M. Heisserer Ms. A. E. Rivera-Varona Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Oaiethoroe Power Corooration Mr. R. B. Brinkman Mr. E. Rasmussen MuniclDal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-1394 Page 3 of 3 Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan Mr. J. L. Coward Other Mr. J. E. Hesler, 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-18-1394 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-1394 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.01 [Index Number 183]
U.S. Nuclear Regulatory Commission ND-18-1394 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.C) The PXS provides RCS makeup, boration, and safety injection during design basis events.
Insoections.Tests. Analvsis iv) Inspections ofthe elevation ofthe following pipe lineswill be conducted:
- 1. IRWST injection lines; IRWST connection to DVI nozzles v) Inspections ofthe elevation ofthe following tanks will be conducted:
- 2. IRWST Acceptance Criteria iv) Themaximum elevation of thetop inside surface of these lines is lessthan the elevation of:
- 1. IRWST bottom inside surface v) Theelevation of the bottom inside tank surface ishigher thanthedirect vessel injection nozzle centerline by the following:
- 2. IRWST >3.4 ft ITAAC Determination Basis Multiple ITAAC are performed todemonstrate that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, andsafety injection during design basis events. This ITAAC requiresthat inspectionsbe conducted to verify that the maximum elevation of thetopinside surface of the In-containment Refueling Water Storage Tank (IRWST) injection lines and iRWST connection to Direct Vessel Injection (DVI) nozzles is less than the elevation of IRWSTbottom inside surface and that the elevation of the IRWSTbottom inside tank surface is higherthan the DVI nozzlecenterlines by > 3.4 ft.
Theinspection of the IRWST injection lines topinside surface, IRWST connection tothe DVI nozzles top inside surface, the DVI nozzle centerline, andthe IRWST bottom inside tank surface elevations were performed using survey equipment in accordancewith the site survey and measurement procedure (Reference 1). Theconservative wall thickness, derived from installed pipe data, wassubtracted from thetop-of-pipe survey datato obtain the highest elevation of the inside surface of these lines. The maximum derived elevation of the IRWST injection lines top inside surface, the DVI nozzle centerline, and IRWST connectionto the DVI nozzles top inside surface iscompared to the measuredelevation ofthe IRWST bottom inside tanksurface using a common reference point.
U.S. Nuclear Regulatory Commission ND-18-1394 Enclosure Page 3 of 3 The inspection results are documented inthe Principal Closure Documents (References 2 and 3), supporting the ITAAC 2.2.03.08c.iv.01 Completion Package (Reference 4). Reference 2 determined that the maximum elevation of the top inside surface of the IRWST injection lines and IRWST connection to the DVI nozzles is 100.7 feet and are lower than the 103.0 foot elevation of the IRWST bottom inside surface. Reference 3 determined that both DVI nozzle centerline elevations are 99.6 feet, which are 3.4 feet below the 103.0 foot elevation of IRWST bottom inside surface, and therefore both Acceptance Criteria are met.
The Principal Closure Documents exists and are availablefor NRC inspection as part of the ITAAC 2.2.03.08c.iv.01 Completion Package.
ITAAC Finding Review Inaccordance with plant procedures for ITAAC completion. Southern NuclearOperating Company (SNC) performed a review ofall ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAACfindings associated withthis ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.03.08c.iv.01 (Reference4) and available for NRC review.
ITAAC Compietlon Statement Based on the above information, SNC hereby notifiesthe NRCthat ITAAC 2.2.03.08c.iv.01 was performed forVEGP Unit 3 and that the prescribed acceptance criteria are met.
Systems, structures, andcomponents verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.
References (available for NRC inspection) 1.
4MP-T81C-N3201 Rev 1 "Construction Survey"
- 2. SV3-PXS-FSK-800183 Rev 1, "As-Built IRWST Injection Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface"
- 3. SV3-PXS-MTK-891586 Rev 0, "IRWST Bottom Inside Tank Surface Comparison to DVI Nozzle Centerline Elevation" 4.
2.2.03.08c.iv.01-U3-CP-Rev 1, ITAAC Completion Package