ND-20-0096, ITAAC Closure Notification on Completion of ITAAC 2.1.02.08d.ii (Index Number 33)

ITAAC Closure Notification on Completion of ITAAC 2.1.02.08d.ii (Index Number 33)

ML20034E985
Person / Time
Site:	Vogtle
Issue date:	01/31/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0096
Download: ML20034E985 (7)

Text

,i > I I MichaelJ. Yox 7825 River Road

^OUtn0rn INUCl3dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle3&4 706-848-6459 tel JAN 3 1 2020 Docket No.: 52-025 ND-20-0096 10CFR 52.99(c)(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 2.1.02.08d.ii (Index Number 331 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 2.1.02.08d.ii [Index Number 33] for verifying the line routing is consistent with the line routing used for design flow resistance calculations and is less than or equal to the calculated flow resistance of each Automatic Depressurization System (ADS) fourth-stage sub-loops. 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 letter contains 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. Yox" Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.1.02.08d.ii [Index Number 33]

MJY/GCW/sfr

U.S. Nuclear Regulatory Commission ND-20-0096 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKlnney (w/o enclosures)

Mr. M. D. Meier(w/o enclosures)

Mr. D. H. Jones(w/o enclosures)

Mr. G. Chick Mr. M. Page Mr. P. Martino Mr. M. J. Vox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Mr. W. Jones(w/o enclosures)

Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Mr. C. Santos Mrs. M. Bailey Mr. S. Rose Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Carrington Mr. P. Heher

U.S. Nuclear Regulatory Commission ND-20-0096 Page 3 of 3 Mr. M. King Mr. E. Davidson Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani(w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hesler, 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. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-20-0096 Enclosure Page 1 of4 Southern Nuclear Operating Company ND-20-0096 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Compietion of ITAAC 2.1.02.08d.ii pndex Number 33]

U.S. Nuclear Regulatory Commission ND-20-0096 Enclosure Page 2 of4 ITAAC Statement Design Commitment:

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

Inspections. 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-loop valves 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 Determination Basis 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 Depressurization 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 was calculated 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, inspections of each sub-loop's as-built construction records were performed to verify the line routing information from the hot leg of the RCS to the discharge of the fourth-stage squib valves remained consistent with the information in the flow resistance design calculation.

The results were 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 (Reference 2).

The results documented in Reference 2 and shown in Attachment A demonstrate the ITAAC acceptance criteria is met.

References 1 and 2 are available for NRC inspection as part of the Unit 3 ITAAC 2.1.02.08d.ii Completion Package(Reference 3).

U.S. Nuclear Regulatory Commission ND-20-0096 Enclosure Page 3 of4 ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company(SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.1.02.08d.ii (Reference 3)and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.08d.ii was performed for VEGP Unit 3 and that the prescribed acceptance criteria were 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(available for NRC inspection)

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

2. SV3-PXS-ITR-800033, Rev. 0,"Unit 3 Inspections and Associated Analysis of each fourth-stage ADS Sub-loop: ITAAC 2.1.02.08d.ii"

3. 2.1.02.08d.ii-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-20-0096 Enclosure Page 4 of4 Attachment A Fourth-Stage ADS Loop Flow Resistance Calculated ITAAC Fourth-stage As-bullt Flow Acceptance Loop Squib valve Resistance^ Criteria*

Tag No *

(ft/gpm^) (ft/gpm^)

Sub-loop A RCS-PL-V004A 2.60x10-7 ^5.91x10-7 Sub-loop B RCS-PL-V004B 2.68x10-7 ^4.65x10-7 Sub-loop C RCS-PL-V004C 2.46x10-7 ^6.21x10-7 Sub-loop D RCS-PL-V004D 2.34x10-7 ^6.20x10-7

• Excerpt from COL App C Table 2.1.2-1

+ Results are Unit specific