ND-18-1168, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.iv.04 (Index Number 186)
| ML18261A042 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/17/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.2.03.08c.iv.04, ND-18-1168 | |
| Download: ML18261A042 (6) | |
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Michael J. Yox 7825 River Road
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Southern Nuclear SEP 112018 Docket Nos.;52-025 Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-1168 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.04 [Index Number 1861 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.04 [Index Number 186]for verifying that the maximum elevation of the top inside surface of the Passive Residual Heat Removal Heat Exchanger (PRHR HX) outlet lineto Steam Generator (SG) connection is less than the elevation of the PRHR HX lower channel head top inside surface. The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAACClosure Process under 10 CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.
This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staffconfirmation ofthis determination and publication ofthe 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.
Michael J. Yox(
Regulatory Affairs Dir^6tor Vogtle 3 &4
/
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.04 [Index Number 186]
MJY/GDL/amw
U.S. Nuclear Regulatory Commission ND-18-1168 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. 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 OalethorDe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-1168 Page 3 of 3 Westinqhouse 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, Balch BIngham
U.S. Nuclear Regulatory Commission ND-18-1168 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-1168 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.iv.04 [Index No. 186]
U.S. Nuclear Regulatory Commission ND-18-1168 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment:
8.c) The PXS provides RCS makeup, boration, and safety Injection during design basis events.
Inspections.Tests. Analvsis:
iv) Inspections of the elevation ofthe following pipe lineswill be conducted;
iv) The maximum elevation of thetop inside surface of these lines islessthan theelevation of:
- 4. PRHR HX lower channel head top inside surface ITAAC Determination Basis Multiple ITAAC are performed todemonstrate thatthe Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, andsafety injection during design basis events. This ITAAC requiresinspections ofthe top inside surface ofthe Passive Residual Heat Removal Heat Exchanger (PRHR HX) outletline to Steam Generator (SG) connection.
The inspections of the PRHR HX outlet line to SG connection top-of-pipe surface was performed using survey equipment in accordance with the sitesurvey and measurement procedure (Reference 1). Theconservative wall thickness, derived from installed pipe data, was subtracted from the top-of-pipe surveydata to obtain the highest elevation ofthe inside surfaceofthese lines (Reference 2). The elevation ofthe PRHR HX lower channel head top outside surfacewas determined using survey equipment in accordancewith the site survey and measurement procedure (Reference 1). As-built manufacturer's datawas usedto derive the PRHR HX lower channel head wall thickness. The PRHR HX lower channel head top inside surface elevation was then determined bysubtracting the as-built manufactrurer's lower channel head wall thickness from the topoutside surfaceofthe lower channel head (Reference 2). The maximum derivedelevation of the top inside surface ofthe PRHR HX outletline to SG connection was compared tothe derived elevation ofthe top inside surface of the PRHR HX lower channel head.
Theinspection results documented in Reference 2, verify thatthe maximum elevation of the PRHR HX outletline to SG connection top insidesurface is 110.5feet and the elevation ofthe PRHR HX lower channel head top inside surface is 111.6feet, which meets the ITAAC acceptance criteria.
ITAAC Finding Review In accordancewith plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining tothe subject ITAAC and
U.S. Nuclear Regulatory Commission ND-18-1168 Enclosure Page 3 of 3 associated corrective actions. This review found there are no relevant ITAAC findings associated withthis ITAAC. The ITAAC completion review is documented inthe ITAAC Completion Package for ITAAC 2.2.03.08c.iv.04 (Reference3) and is available for NRC review.
ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.iv.04 was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.
Systems, structures, and componentsverified as part ofthis ITAAC are being maintained in theiras-designed, ITAAC compliant condition inaccordance with approvedplantprograms and procedures.
References favallable for NRC Inspection)
- 1. 26139-000-4MP-T81C-N3201 Rev 1 "Vogtle Units3 and 4 Construction Completion Project
- Construction Survey" 2.
SV3-PXS-FSK-800186 Rev 0, "As-Built PRHR HX Outlet Lines Elevation Comparison to PRHR HX Lower Channel Head Top Inside Surface Elevation"
- 3. 2.2.03.08c.iv.04-U3-CP-Rev 0, "Completion Package for the Unit3 ITAAC 2.2.03.08c.iv.04
[Index Number 186]"