ND-17-1533, ITAAC Closure Notification on Completion of ITAAC 2.2.04.08b.ii (Index Number 2381)
| ML17262A674 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/19/2017 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-17-1533 | |
| Download: ML17262A674 (7) | |
Text
Southern Nuclear SEP ! 9 2017 Docket No.:
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-17-1533 10CFR 52.99(c)(1)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit3 ITAAC Closure Notification on Completion of ITAAC 2.2.04.08b.ii [Index Number 2381 Ladies and Gentlemen:
In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notifythe Nuclear Regulatory Commission (NRC) ofthe completion ofVogtle Electric Generating Plant (VEGP)
Unit 3 Inspections, Tests, Analyses, and AcceptanceCriteria (ITAAC) Item 2.2.04.08b.ii [Index Number 238] for verifying that a report exists to indicate the installed flow limiting orifice within the Steam Generator (SG) main steam line discharge nozzle does not exceed 1.4 square feet (sq. ft.). Theclosure processfor this ITAAC is based on the guidance described in Nuclear Energy Institute (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 letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation ofthis determination and publication ofthe required notice in the Federal Register per 10 CFR 52.99.
If there are any questions, please contact David Woods at 706-848-6903.
Respectfully submitted, Michael J. Yox
^
Regulatory Affairs DirectorVogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit3 Completion of ITAAC 2.2.04.08b.ii [Index Number 238]
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U.S. Nuclear Regulatory Commission ND-17-1533 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. D. Williams Mr. D. F. Woods Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Reaulatorv 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. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Ms. V. L. Ordaz Mr. B. J. Davis Mr. B. J. Kemker Ooiethorpe Power Corporation Mr. K. T. Haynes Mr. R. B. Brinkman Municlpai Eiectric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-17-1533 Page 3 of 3 Dalton Utilities Mr. T. Bundros WECTEC Mr. 0. A. Castell Westlnahouse Electric Company. LLC Mr. R. Easteriing (w/o enclosures)
Mr. G. Koucheravy (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Ms. L. G. Iller Mr. J. Hopkins Mr. D. Hawkins Mr. 0. F. Landon Mr. M. L. Clyde Ms. 8. DiTommaso Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, inc.
Mr. 8. Roetger, Georgia PubiicService Commission Ms. 8. W. Kemizan, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-17-1533 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-17-1533 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.04.08b.ii [Index Number 238]
U.S. Nuclear Regulatory Commission ND-17-1533 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment:
8.b)
During design basis events, the SGS limits steamgenerator blowdown and feedwater flow to the steam generator.
Inspections. Tests. Analvses:
ii)
Inspection will be performed for the existence of a report confirming thatthe area of the flow limiting orifice within the SG main steam outlet nozzle will limit releases to the containment.
Acceptance Criteria:
ii)
Areport exists to indicate the installed flow limiting orifice within theSG main steamline discharge nozzle does not exceed 1.4 sq. ft.
ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that during design basis events, the Steam Generator System (SGS) limits SteamGenerator (SG) blowdown and feedwater flow tothe SG.
This ITAAC requires an inspection to verify the existence of a report confirming thatthe area of the flow limiting orifice within the SG main steam outletnozzle will limit releases to the containment. Inspections ofeach ofthe Vogtle Unit 3 SGs were conductedto verify that a report exists to indicate that the installed flow limiting orifice within the SG main steam line discharge nozzle does not exceed 1.4 square feet (sq. ft.).
Post installation dimensional inspectionswere performed to determinethe diameters for both the Vogtle 3A SG and Vogtle 3B SG installed flow limiting orifices within the SG main steam outlet nozzle. Calculationswere then performed usingthe measurements obtained during inspection to determine the total area ofthe flow limiting orifice foreach SG. The measurements and calculations showed that the total area of the Vogtle 3A SG flow limiting orifice is 1.392 sq. ft. and the total area ofthe Vogtle 3BSG flow limiting orifice is 1.392 sq. ft.
The results were documented in the "Vogtle Unit 3 Steam Generator Flow Limiting Orifice Inspection Summary Report" (Reference 1). Theresults demonstrated that the installed flow limiting orifice for each Vogtle Unit 3 SGwithin the SG main steam line discharge nozzle does not exceed 1.4 sq. ft. and meets ITAAC 2.2.04.08b.ii acceptance criteria.
ITAAC Finding Review Inaccordance with plant procedures for ITAAC completion. Southern NuclearOperating Company (SNC) performed a review ofall ITAAC findings pertaining to thesubject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review document number is included inthe Vogtle Unit 3 ITAAC Completion Package for ITAAC 2.2.04.08b.ii (Reference 2)and available for NRC Inspection.
U.S. Nuclear Regulatory Commission ND-17-1533 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRG that ITAAC 2.2.04.08b.ii was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.
Systems, structures, and components 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 favailable for NRG Inspection)
- 1. SV3-MB01-VFR-001, Rev. 0, Vogtle Unit 3 Steam Generator Flow Limiting Orifice Inspection Summary Report
- 2. SVP_SV0_005013, Attachment 1, Submittal of Inspections, Test, Analyses and Acceptance Criteria (ITAAC) Completion Package for Unit 3 ITAAC 2.2.04.08b.ii [Index Number 238]
(SGS Main Steam Line Flow Limiting Orifice Area)