ND-18-0709, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.07.1 (Index Number 78)
| ML18179A080 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/27/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.1.03.07.i, ND-18-0709 | |
| Download: ML18179A080 (7) | |
Text
^ Southern Nuclear JUN 2 7 2018 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtle 3 &4 7825 River Road Waynesboro, GA30830 706-848-6459 tel 410-474-8587 cell myox @southernco.com ND-18-0709 10CFR 52.99(G)(3)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.03.07.1 [Index Number 781 Ladies and Gentlemen:
Pursuant to 10 CFR52.99(c)(3), Southern Nuclear Operating Companyhereby notifies the NRC that as ofJune 13, 2018, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) Item 2.1.03.07.1 [Index Number 78]
has not been completedgreater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. 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 bythe guidance described in NEI 08-01, Industry Guideline forthe 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, oranalyses 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, MichaelJ. Yox Regulatory Affairs Director Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.1.03.07.1 [Index Number 78]
MJY/PGL/amw
U.S. Nuclear Regulatory Commission ND-18-0709 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. 8. 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 Reouiatorv 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 Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0709 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (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. 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-18-0709 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0709 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.03.07.1 [index Number 78]
U.S. Nuclear Regulatory Commission ND-18-0709 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment
- 7. The reactor internals will withstand the effects of flow induced vibration.
- 10. The reactor lower internals assembly is equipped with holders for at least eight capsules for storing material surveillance specimens.
Insoections/Tests/Analvses i) Avibration type test will be conducted on the (first unit) reactor internals representative of API 000.
ii) A pre-test inspection, a flow test and a post-test inspectionwill be conducted on the as-built reactor internals.
Inspection ofthe reactor lower intemalsassembly forthe presence ofcapsules will be performed.
Acceptance Criteria i) Areport existsand concludes thatthe (first unit) reactor internals have noobservable damage or loose parts as a result of the vibration type test.
ii) The as-built reactor internals have no observable damage or loose parts.
At least eight capsules are inthe reactor lowerinternals assembly.
ITAAC Completion Description This ITAAC requires that tests and inspections be performed and documented to ensure the reactor internals will withstand the effects of flow induced vibration and that the reactor lower internals assembly is equippedwith holdersforat least eightcapsules forstoring material surveillance specimens.
7.i1 A report exists and concludes that the (first unit) reactor internals have no obsen/able damaoe or loose parts as a result of the vibration tvpe test.
Avibration typetest isconducted on the first API000 unit (i.e., Unit 3) reactor vessel internals during the hot functional test (HFT). Apost-HFT inspection of the internals isthenperformed to check forobservable damage or loose parts. The inspection is documented on data sheets included in the inspection procedure (Reference 1), and concludes that the first unit reactor internals have no observable damage or loose parts as a result ofthe vibration type test.
This vibration typetest and inspection are performed consistent with the guidelines of Regulatory Guide 1.20, Rev 2 as described in the Updated Final SafetyAnalysis Report (UFSAR) Section 3.9.2.4. Per UFSAR Section 14.2.9.1.9, thistesting is required for thefirst plant only (Unit 3), therefore the Unit 3 inspection results (Reference 1)are usedto closethis portion of the ITAAC for Unit4.
U.S. Nuclear Regulatory Commission ND-18-0709 Enclosure Page 3 of 4 7.ii) The as-built reactor internals have no observable damage or loose parts.
A pre-HFT inspection is performed to document tfie initial condition of the reactor internals, including all major load-bearing elements that retain the position of the core support structure; lateral, vertical, and torsional restraints; locking and bolting components; contact surfaces; and the reactor vessel interior. Next, a flow test is conducted on the reactor vessel internals during the HFT. Apost-HFT inspection is then performed on the reactor internals to check for observable damage or loose parts. These inspections are documented on data sheets included inthe inspection procedures (References 1 and 2). The test and inspections, described in UFSAR Section 3.9.2.4, are performed consistent with the guidelines of Regulatory Guide 1.20, Rev 2.
The inspection results, as documented inthe Unit 3 and Unit 4 inspection procedures (References 1 and 2), conclude the as-built reactor internals have no observable damage or loose parts.
- 10. At least eight capsules are in the reactor lower internals assemblv.
An inspection ofthe reactor lower internalsassembly is performed to confirm that at least eight material surveillance specimen capsules are installed in holders for that purpose, in accordance with the installation manuals (References 3 and 4). These inspections are documented on data sheets inciuded in the inspection procedures (References 1 and 2).
The inspection results, as documented inthe Unit 3 and Unit 4 inspection procedures (References 1 and 2),conclude that at least eight capsules are in the reactor lower internals assembly.
References 1 and 2 provide evidence that the ITAAC Acceptance Criteria requirements are met; Areport existsand concludesthat the (first unit) reactorinternals have no observable damage or loose parts as a result of the vibration type test; The as-built reactor internals have no observable damage or loose parts; and Atleast eight capsules are inthe reactor lower internals assembly.
References 1 through 4 are available for NRG inspection as partofthe Unit 3 and Unit 4 ITAAC 2.1.03.07.1Completion Packages (References 5 and 6, respectively).
List of ITAAC Findings Inaccordance with plant procedures for ITAAC completion. Southern NuclearOperating Company (SNC) performed a review ofall findings pertaining to the subjectITAAC and associated corrective actions. This review, which included now-consolidated ITAAC Indexes 79 and 85, found there are no relevant ITAAC findings associated with this ITAAC.
U.S. Nuclear Regulatory Commission ND-18-0709 Enclosure Page 4 of 4 References (available for NRG inspection)
- 1. 3-RXS-ITPP-501, "Pre-and Post-Hot Functional Test Inspection of Reactor Vessel Internals" 2.
4-RXS-ITPP-501, "Pre-and Post-Hot Functional Test Inspection of Reactor Vessel Internals" 3.
SV3-MI01-Z0M-001, "AP1000 RVI Installation Requirements Manual" 4.
SV4-MI01-ZOM-001, "AP1000 RVI Installation Requirements Manual" 5.
2.1.03.07.i-U3-CP-Rev0, ITAAC Completion Package 6.
2.1.03.07.i-U4-CP-Rev0, ITAAC Completion Package 7.
NEI 08-01, "Industry Guideline for tfie ITAAC Closure Process Under 10 CFR Part 52"