ND-18-0324, ITAAC Closure Notification on Completion of ITAAC 2.1.02.08c (Index Number 31)
| ML18087A016 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/27/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.1.02.08c, ND-18-0324 | |
| Download: ML18087A016 (6) | |
Text
Sk. Southern Nuclear MAK 2 7 2018 Docket No.:
52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 &4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox @southernco.com ND-18-0324 10CFR 52.99(c)(1)
Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.1.02.08c findex Number 311 Ladies and Gentlemen:
In accordance with 10 CFR 52.99(c)(1), the purpose ofthis letter is to notify the Nuclear Regulatory Commission (NRC) ofthe completion ofVogtie Electric Generating Plant (VEGP) Unit 4 Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) Item 2.1.02.08c [Index Number 31]
for verifying thateach Reactor Coolant Pump (RCP) flywheel assembly can withstand a design overspeed condition of no lessthan 125% of operating speed. 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.
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.
Michael J. Yo>
Regulatory Affairs DirectorVogtie 3 &4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.08c [Index Number 31]
MJY/LBP/amw
U.S. Nuclear Regulatory Commission ND-18-0324 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Rauckhorst (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. B. 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 Oaiethoroe Power Corporation Mr. R. B. Brinkman Municipal Eiectric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0324 Page 3 of 3 Dalton 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 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., 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-18-0324 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0324 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.08c [Index Number 31]
U.S. Nuclear Regulatory Commission ND-18-0324 Enclosure Page 2 of 3 ITAAC Statement Design Commitment B.c) Each RCP flywheel assembly can withstand a design overspeed condition.
Inspections. Tests. Analyses:
Shop testing of each RCP flywheel assembly will be performed at the vendor facility at overspeed conditions.
Acceptance Criteria:
Each RCP flywheel assembly has passed an overspeed condition of no less than 125% of operating speed.
ITAAC Determination Basis The Reactor Cooling System contains four pumps, and each pump contains an upper and a lowerflywheel assembly. The subject Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) requires each Reactor Coolant Pump (RCP)flywheel assembly pass an overspeed condition test of no less than 125% of operating speed to demonstrate each RCP flywheel can withstand a design overspeed condition.
An overspeed test has been performed by the vendor on each flywheel assembly at 2250 revolutions per minute (rpm) (125% of synchronous speed of 1800 rpm). Following the overspeed test, a visual inspection ofthe flywheel assembly and liquid penetrant tests ofthe outside diameter of the flywheel retaining rings and the inside diameter of the hubs was performed and results documented in a flywheel overspeed test report.
The flywheel assembly overspeed test reportsare documented inthe quality data packages for each RCP (Reference 1 to 4). The test reports show the RCP flywheel assemblies listed below passed the test which meets the ITAAC criteria.
1.
RCP Serial Number 509 Upper flywheel Serial Number: 250-6D71650G01-04 Lowerflywheel Serial Number: 287-6D71651G01-05 2.
RCP Serial Number 510 Upper flywheel Serial Number: 251-6D71650G01-04 Lower flywheel Serial Number: 288-6D71651G01-04 3.
RCP Serial Number 511 Upper flywheel Serial Number: 239-6D71650G01-05 LowerflywheelSerial Number: 281-6D71651G01-04 4.
RCP Serial Number 512 Upper flywheel Serial Number: 252-6D71650G01-05 Lower flywheel Serial Number: 286-6D71651G01-05
U.S. Nuclear Regulatory Commission ND-18-0324 Enclosure Page 3 of 3 ITAAC Finding Review Inaccordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a reviewof allfindings pertainingto the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated withthis ITAAC. This finding review is included in the Vogtle Unit4 ITAAC Completion Package for ITAAC 2.1.02.08c (Reference 5) and available for NRC inspection.
ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.08c was performed for VEGP Unit4 and that the prescribed acceptance criteria were met.
Systems, structures, and components verified as part ofthis ITAAC are being maintained in their as-designed, ITAAC compliantcondition in accordance with approved plant programs and procedures.
References (available for NRC Inspection)
- 1. SV4-MP01-VQQ-006 Revision 0, API 000 Vogtle Unit4 Quality Release and Certificate of Conformance, Reactor Coolant Pump (SN 509) 2.
SV4-MP01-VQQ-007 Revision 0, API000 Vogtle Unit4 Quality Release and Certificate of Conformance, Reactor Coolant Pump (SN 511) 3.
SV4-MP01-VQQ-008 Revision 0, API 000 Vogtle Unit4 Quality Release and Certificate of Conformance, Reactor Coolant Pump (SN 510) 4.
SV4-MP01-VQQ-009 Revision 0, API 000 Vogtle Unit4 Quality Release and Certificate of Conformance, Reactor Coolant Pump (SN 512)