ND-18-0939, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.08d.ii (Index Number 33)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.08d.ii (Index Number 33)

ML18205A423
Person / Time
Site:	Vogtle
Issue date:	07/24/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0939
Download: ML18205A423 (7)

Text

_ , . . I MichaelJ. Yox 7825 River Road SOUtn0rn NUCl0dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tel 410-474-8587 cell JUL 2 4 2018 myox@soutfiernco.com Docket Nos.: 52-025 52-026 ND-18-0939 10CFR 52.99(c)(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 2.1.02.08d.ii [Index Number 331 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as ofJuly 17, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.08d.ii [Index Number 33] has not been completed greater 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 by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses 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 submittedto 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.

Michael J. Vox Regulatory Affaifs Director Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.08d.ii [Index Number 33]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0939 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. B. Klecha Mr. G. Chick Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Ms. A. C. Chamberlain Mr. T. G. Petrak 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. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Mr. P. B. Donnelly Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0939 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westlnqhouse 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. 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 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-18-0939 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0939 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.08d.ii [Index Number 33]

U.S. Nuclear Regulatory Commission ND-18-0939 Enclosure Page 2 of 4 ITAAC Statement Deslon Commitment:

B.d) The RCS provides automatic depressurization during design basis events.

Insoections. Tests. Analvses:

ii) Inspections and associated analysis of each fourth-stage ADS sub-loop (four valves and associated piping connected to each hot leg) will be conducted to verify the line routing is consistent with the line routing used for design flow resistance calculations.

Acceptance Criteria:

ii) The calculated flow resistance for each fourth-stage ADS sub-loopvalves and piping is:

Loop 1:

Sub-loop A: < 5.91x10'^ft/gpm^

Sub-loop C: < 6.21x10-^ ft/gpm^

Loop 2:

Sub-loop B: < 4.65x10"^ ft/gpm^

Sub-loop D: < 6.20x10"^ ft/gpm^

ITAAC Completion Description Multiple ITAAC are performed to demonstrate the Reactor Coolant System (RCS) provides automatic depressurization during design basis events. This ITAAC performs inspections and analysis of each fourth stage Automatic Depressusrization System (ADS) sub-loop (four valves and associated piping connected to each hot leg) to verify the line routing is consistent with the line routing used for design flow resistance calculations.

A flow resistance is caiculated with Darcy's formula for each of the fourth stage ADS sub-loops flow paths A, B, C, and D using line routing information (i.e., pipe length, pipe diameter, number and type of pipe fittings, entrance/exit losses, and valves) (Reference 1). Following installation, an inspection of each sub-loop's as-built construction records are performed to verify the line routing information from the hot leg of the RCS to the discharge of the fourth-stage squib valves remains consistent with the information in the flow resistance design caiculation. The results are used to calculate the as-built flow resistance for each sub-loop using the same methodology used in the flow resistance design calculation and compared to the ITAAC acceptance criteria (References 2 and 3).

The results are documented in the Unit 3 and Unit 4 Principal Closure Document (Reference 2 and 3, respectively) and shown in the Attachment which demonstrates the ITAAC acceptance criteria is met.

References 1 thru 3 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.1.02.08d.ii Completion Packages (Reference 4 and 5, respectively).

U.S. Nuclear Regulatory Commission ND-18-0939 Enclosure Page 3 of 4 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References favailable for NRG inspection)

1. APP-PXS-M3C-019, Revision 5, "IRWST / Contlnment Sump Injection Lines and ADS Line Resistances"

2. Principal Closure Document (Unit 3)

3. Principal Closure Document (Unit 4)

4. 2.1.02.08d.ll-U3-CP-Rev0, ITAAC Completion Package

5. 2.1.02.08d.ll-U4-CP-Rev0, ITAAC Completion Package

6. NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0939 Enclosure Page 4 of 4 Attachment Fourth Stage ADS Loop Flow Resistance Calculated ITAAC Fourth-stage As-bullt Flow Acceptance Loop Squib valve Resistance'*' Criteria Tag No.* (ft/gpm2)

(ft/gpm2)

Sub-loop A RCS-PL-V004A <5.91x10-^

Sub-loop B RCS-PL-V004B <4.65x10-^

Sub-loop C RCS-PL-V004C <6.21x10

Sub-loop D RCS-PL-V004D <6.20x10-^

• Excerpt from COL App C Table 2.1.2-1

+ Results are Unit specific