ND-19-0394, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.10.ii (Index Number 816)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.10.ii (Index Number 816)

ML19154A458
Person / Time
Site:	Vogtle
Issue date:	06/03/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0394
Download: ML19154A458 (7)

Text

A _ , .. , MichaelJ. Yox 7825 River Road 50Utn©rn NUCl03r Regulatory Atfalrs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel JUN 0 3 2019 Docket Nos.: 52-025 52-026 NO-19-0394 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 3.3.00.10.ii [Index Number 8161 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of May 29, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.10.11 [Index Number 816] 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 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.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.10.ii [Index Number 816]

MJY/PGL/sfr

U.S. Nuclear Regulatory Commission ND-19-0394 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. R.G. West(w/o enclosures)

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

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

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

Mr. J. B. Klecha Mr. G. Chick Mr. M. J. Vox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown Ms. J. M. Heisserer 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. I. Cozens Mr. J. Gaslevic Mr. V. Hall Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-19-0394 Page 3 of 3 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 Ms. J. Monahan Mr. J. L. Coward 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, Batch BIngham

U.S. Nuclear Regulatory Commission ND-19-0394 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0394 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion Plan for Uncompleted ITAAC 3.3.00.10.11 [Index Number 816]

U.S. Nuclear Regulatory Commission ND-19-0394 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

10. The shield building roof and PCS storage tank support and retain the PCS water sources. The PCS storage tank has a stainless steel liner which provides a barrier on the inside surfaces of the tank. Leak chase channels are provided on the tank boundary liner welds.

I nsoections/Tests/Analvses

11) An inspection of the PCS storage tank exterior tank boundary and shield building tension ring will be performed before and after filling of the PCS storage tank to the overflow level. The vertical elevation of the shield building roof will be measured at a location at the outer radius of the roof (tension ring) and at a location on the same azimuth at the outer radius of the PCS storage tank before and after filling the PCS storage tank.

iii) An inspection of the PCS storage tank exterior tank boundary and shield building tension ring will be performed before and after filling of the PCS storage tank to the overflow level. The boundaries of the PCS storage tank and the shield building roof above the tension ring will be inspected visually for excessive concrete cracking.

Acceptance Criteria ii) A report exists and concludes that inspection and measurement of the PCS storage tank and the tension ring structure, before and after filling of the tank, shows structural behavior under normal loads to be acceptable.

iii) A report exists and concludes that there is no visible water leakage from the PCS storage tank through the concrete and that there is no visible excessive cracking in the boundaries of the PCS storage tank and the shield building roof above the tension ring.

ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the shield building (SB) roof and Passive Containment Cooling System (PCS)storage tank support and retain the PCS water sources.

The PCS storage tank has a stainless steel liner which provides a barrier on the inside surfaces of the tank. Leak chase channels are provided on the tank boundary liner welds.

The subject ITAAC requires that an inspection of the PCS storage tank exterior tank boundary and SB tension ring be performed before and after filling of the PCS storage tank to the overflow level to demonstrate structural behavior under normal loads is acceptable. The vertical elevation of the SB roof is measured at a location at the outer radius of the roof (tension ring) and at a location on the same azimuth at the outer radius of the PCS storage tank before and after filling the PCS storage tank. The subject ITAAC also requires visual inspections before and after filling of the PCS storage tank to the overflow level to confirm there is no visible water leakage from the PCS storage tank through the concrete, and that there is no visible excessive cracking in the boundaries of the PCS storage tank and the SB roof above the tension ring.

Inspections before and after tank filling are coordinated by Unit 3 and Unit 4 preoperational test procedures 3-PCS-ITPP-502 and 4-PCS-ITPP-502 (References 1 and 2).

U.S. Nuclear Regulatory Commission ND-19-0394 Enclosure Page 3 of 4 For the inspection and measurement portion of the ITAAC, the vertical elevation and the horizontal position of the SB roof and the PCS storage tank are measured at several locations.

The measurements are performed before and after the first filling of the PCS storage tank to the overflow level. The values at each of the selected measurement locations and for each condition are obtained using survey equipment in accordance with site survey and measurement procedures (Reference 3).

The difference in the measured values at each of the selected locations corresponds to the vertical deflection and horizontal displacement at that location due to the filling of the tank. This difference is compared to the maximum acceptable deflections as documented in APP-XX-YYY-ZZZ(Reference 4). The maximum acceptable deflections are based on the greatest dimensional and material property tolerances of the roof structure consistent with a largest displacement at the measured points. The measured values are verified to be less than or equal to the maximum acceptable vertical deflection and horizontal displacement for each of the selected measurement locations. The results of the measurements and comparisons are documented in the Unit 3 and Unit 4 principal closure documents(References 5 and 6).

For the visual inspection and crack evaluation portion of the ITAAC, prior to the first filling of the PCS storage tank, a crack map is developed of the boundaries of the PCS storage tank and the SB roof above the tension ring. The crack mapping includes the exposed concrete surface of the PCS storage tank at several locations. A visual inspection is performed to obtain surface crack information. Crack evaluation and crack significance is assessed using Section 2.2 of American Concrete Institute (ACI) 224.1 R-07(Reference 7).

Crack mapping is repeated after the first filling of the PCS storage tank to the overflow level.

The second crack mapping reviews the exposed concrete surface at the same locations that were used for the crack mapping performed before the PCS storage tank was first filled. Visual inspections are again performed to obtain surface crack information. The crack map for the filled condition is compared to the crack map for the unfilled condition and evaluated to determine whether any significant concrete cracking exists. Significant concrete cracking is documented and evaluated in accordance with Chapter 5 of ACI 349.3R-96 (Reference 8).

Visual inspection of the PCS storage tank is also performed once the tank is first filled to the overflow level to verify that there is no visible water leakage from the tank through the concrete.

The results of the inspections, measurements, crack mapping, and crack evaluations are documented in the Unit 3 and Unit 4 principal closure documents (References 9 and 10) and conclude that inspection and measurement of the PCS storage tank and the tension ring structure, before and after filling the PCS storage tank to the overflow level, shows structural behavior under normal loads to be acceptable, and that there is no visible water leakage from the PCS storage tank through the concrete, and that there is no visible excessive cracking in the boundaries of the PCS storage tank and the SB roof above the tension ring.

References 1 thru 10 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 3.3.00.10.11 Completion Packages(Reference 11 and 12, respectively).

U.S. Nuclear Regulatory Commission ND-19-0394 Enclosure Page 4 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 favaiiable for NRG inspection)

1. 3-PCS-ITPP-502,"Passive Containment Cooling System PCCWST Preoperational Test Procedure"

2. 4-PCS-ITPP-502,"Passive Containment Cooling System PCCWST Preoperational Test Procedure"

3. 26139-000-4MP-T81C-N3201, Revision 4,"Construction Survey"

4. APP-XX-YYY-ZZZ, Calculation of Expected Vertical Deflections and Expected Horizontal Displacements for Selected Measurement Locations

5. SV3-1278-ITR-816001,"PCS Storage Tank Loading Deflection Principal Closure Document (Unit 3)"

6. SV4-1278-ITR-816001,"PCS Storage Tank Loading Deflection Principal Closure Document (Unit 4)"

7. ACI 224.1 R-07 Causes, Evaluation and Repair of Cracks in Concrete Structures

8. ACI 349.3R-96, Evaluation of Existing Nuclear Safety-Related Concrete Structures.

9. SV3-1278-ITR-816002,"PCS Storage Tank Crack Evaluation Principal Closure Document (Unit 3)"

10. SV4-1278-ITR-816002,"PCS Storage Tank Crack Evaluation Principal Closure Document (Unit 4)"

11.3.3.00.10.ii-U3-CP-Rev0, ITAAC Completion Package 12.3.3.00.10.ii-U4-CP-Rev0, ITAAC Completion Package

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