ND-18-0585, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08b.02 (Index Number 176)
| ML18243A028 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/30/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0585 | |
| Download: ML18243A028 (6) | |
Text
Southern Nuclear AU6 3 0 2018 Docket Nos.:
52-025 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road-Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0585 10 CFR 52.99(c)(1)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08b.02 [Index Number 1761 Ladies and Gentlemen:
Inaccordance 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 2.2.03.08b.02 [Index Number 176] forverifying that the elevation ofthe centerline ofthe Passive Residual Heat Removal Heat Exchanger (PRHR HX) upper channel head isgreaterthan the Hot Leg (HL) centerline byat least 26.3 ft. The closure process forthis ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52," which wasendorsed by the NRC in Regulatory Guide 1.215.
This lettercontains 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.
If there are any questions, please contact Tom Petrak at 706-848-1575.
Respectfully submitted.
Midhael J. Ybx/
Regulatory Affairs Dfi;6ctor Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08b.02 [Index Number 176]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0585 Page 2 of 3 To:
Southern Nuclear Operating Companv/ 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. C. T. Defnall 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. M. E. Ernstes 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 Oalethoroe Power Corporation 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-18-0585 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. 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. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0585 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0585 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08b.02 [Index Number 176]
U.S. Nuclear Regulatory Commission ND-18-0585 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment:
8.b) The PXS provides core decay heat removal during design basis events.
Insoections.Tests. Analvsis:
Acceptance Criteria:
- 2. The elevation of the centerline of the PRHR HX's upper channel head is greater than the HL centerline by at least 26.3 ft.
ITAAC Determination Basis Multiple ITAAC are performed to demonstrate thatthe Passive CoreCooling System(PXS) provides coredecayheat removal during design basis events. Thesubject ITAAC requires that an inspection be conducted of the PassiveResidual Heat Removal Heat Exchanger (PRHR HX) to confirmthat the centerline elevation of the PRHR HX's upper channel head is greater than the Hot Leg (HL) centerline by at least 26.3 ft.
The inspection ofthe centerline elevation ofthe PRHR HX's upperchannel head and the centerline elevation of the HL was performed, following installation of the PRHR HX and the main reactorcoolant loop piping, using surveyequipment in accordance with the site surveyand measurement procedure (Reference 1).Theelevation difference was determined bymeasuring the centerline elevation of the HLand the centerline elevation of the PRHR HX's upper channel head in relation to a common reference point, and comparing the results.
The inspection results documented in Reference 2, verify that theelevation of thecenterline of the PRHR HX's upper channel head is 26.4feetgreaterthanthe HL centerline, which meetsthe ITAAC acceptance criteria.
ITAAC Finding Review In accordance with plantproceduresfor ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review ofall findings pertaining tothe subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented inthe ITAAC Completion Packagefor ITAAC 2.2.03.08b.02 (Reference 3)and isavailable for NRC review.
U.S. Nuclear Regulatory Commission ND-18-0585 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRCthat ITAAC 2.2.03.08b.02 was performed for VEGP Unit 3 and that the prescribed acceptance criteriaare met.
Systems, structures, and components verified as part ofthis ITAAC are beingmaintained in their as-designed, ITAAC compliant condition in accordance with approved plant programsand procedures.
References favailable for NRG Inspection)
- 1. 26139-000-4MP-T81C-N3201 Rev 1 "Vogtle Units 3 and 4 Construction Completion Project
- Construction Survey" 2.
SV3-PXS-MEK-891997 Rev 1, "As-Built Elevation Comparison of PRHR Heat Exchanger Upper Channel Head Centerline to RCS Hot Leg Centerline"
- 3. 2.2.03.08b.02-U3-CP-Rev 0, "Completion Package for the Unit 3 ITAAC 2.2.03.08b.02
[Index Number 176]"