ND-19-1309, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.02.07a.iii (Index Number 137)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.02.07a.iii (Index Number 137)

ML19304B738
Person / Time
Site:	Vogtle
Issue date:	10/31/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1309
Download: ML19304B738 (8)

Text

Michael J. Vox 7825 River Road Sk.Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 and Unit 4 706-848-6459 tel DCT 3 I 2019 Docket Nos.: 52-025 52-026 ND-19-1309 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 2.2.02.07a.ill (Index Number 1371 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 28, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.2.02.07a.iii

[Index Number 137] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.02.07a.iii [Index Number 137]. 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. Vox Regulatory Affairs Director Vogtle 3and4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.02.07a.ill [Index Number 137]

MJY/GJL/sfr

U.S. Nuclear Regulatory Commission ND-19-1309 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. M. J. Yox 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. F. D. Brown 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1309 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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. Z. 8. Harper 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-1309 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-19-1309 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC Item 2.2.02.07a.lll [Index No. 137]

U.S. Nuclear Regulatory Commission ND-19-1309 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 7.a) The PCS delivers water from the PCCWST to the outside, top of the containment vessel.

7.f) The PCS provides a flow path for long-term water makeup from the PCCWST to the spent fuel pool.

8.a) The PCCAWST contains an inventory of cooling water sufficient for PCS containment cooling from hour 72 through day 7.

Inspections/Tests/Analvses iii) Inspection will be performed to determine the PCCWST standpipes elevations.

ii) Inspection of the PCCWST will be performed.

Inspection of the PCCAWST will be performed.

Acceptance Criteria iii) The elevations of the standpipes above the tank floor are:

- 16.8 ft+/- 0.2 ft

- 20.3 ft +/- 0.2 ft

- 24.1 ft +/-0.2 ft ii) The volume of the PCCWST is greater than 756,700 gallons.

The volume of the PCCAWST is greater than 780,000 gallons.

ITAAC Compietion Description Multiple ITAAC are performed to demonstrate that the Passive Containment Cooling System (PCS); delivers water from the Passive Containment Cooling Water Storage Tank(PCCWST)to the outside, top of the containment vessel; provides a flow path for long-term water makeup from the PCCWST to the spent fuel pool; and the Passive Containment Cooling Ancillary Water Storage Tank(PCCAWST)contains an inventory of cooling water sufficient for PCS containment cooling from hour 72 through day 7. The subject ITAAC requires that an inspection be performed to determine the PCCWST standpipes elevations; an inspection be performed of the PCCWST to verify that the volume of the PCCWST is greater than 756,700 gallons; and an inspection be performed of the PCCAWST to verify that the volume of the PCCAWST is greater than 780,000 gallons.

iii) The elevations of the standoioes above the tank floor are:

- 16.8 ft +/-0.2 ft

- 20.3 ft +/- 0.2 ft

- 24.1 ft +/-0.2 ft

U.S. Nuclear Regulatory Commission ND-19-1309 Enclosure Page 3 of 5 The inspection to determine the POCWST standpipes elevations is performed in the PCOWST module after its installation at the top of the shield building. The PCOWST standpipes are identified in the VEGP 3&4 Updated Final Safety Analysis Report(UFSAR), Table 6.2.2-2, Component Data Passive Containment Cooling System (Nominal)(Reference 1) as the Third Standpipe, Second Standpipe, and Top Standpipe. The PCCWST standpipes elevations are measured using survey equipment in accordance with site survey and measurement procedure (Reference 2). The elevations of the standpipes above the PCCWST tank floor are determined by measuring the distance between the PCCWST floor and the opening at the high point of the inlet at each standpipe.

The inspection results are documented in the Unit 3 and Unit 4 Principal Closure Documents XXX (References 3 and 4), and determined that the elevations of the standpipes above the tank floor are:

Unit 3 xx.x ft (Third Standpipe) yy.y ft(Second Standpipe) zz.z ft(Top Standpipe)

Unit 4

- xx.x ft (Third Standpipe)

- yy.y ft(Second Standpipe)

- zz.z ft(Top Standpipe)

The inspection results verify that the elevations of the standpipes above the tank floor are:

16.8 ft+/- 0.2 ft (Third Standpipe)

- 20.3 ft+/- 0.2 ft(Second Standpipe)

- 24.1 ft +/- 0.2 ft (Top Standpipe)

Unit 3 and Unit 4 Principal Closure Documents XXX are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.02.07a.iii Completion Packages.

ii) The volume of the PCCWST is Greater than 756.700 Gallons.

VEGP 3&4 UFSAR, Table 14.3-2, Design Basis Accident Analysis,(Reference 1) references the PCCWST capacity for the spent fuel pool long-term water makeup volume to VEGP 3&4 UFSAR, Table 6.2.2-1, Passive Containment Cooling System Performance Parameters, (Reference 1). UFSAR Tables 14.3-2 and 6.2.2-1 identify that the PCCWST volume for the spent fuel pool long-term water makeup is a minimum of 756,700 gallons. The volume of the PCCWST providing a flow path for long-term water makeup is determined by the following method:

The dimensions of the PCCWST, below the PCCWST standpipe elevation which begins feeding the Fire Protection System (FPS), are measured and recorded following tank installation by both the tank vendor and site. Site measurements are performed using survey equipment in accordance with site survey and measurement procedure (Reference 2). The PCCWST usable volume for the spent fuel pool long-term water makeup is calculated, using the survey measurements, and compared to the ITAAC acceptance criteria of greater than 756,700 gallons.

U.S. Nuclear Regulatory Commission ND-19-1309 Enclosure Page 4 of 5 The inspection results of the PCCWST volume determination are documented in the Unit 3 and Unit 4 Principal Closure Documents YYY (References 5 and 6), and determined that the volume of the PCCWST(Tag No. PCS-MT-01) is XXX,XXX gallons for Unit 3, and XXX,XXX for Unit 4.

This confirms that the volume of the PCCWST is greater than 756,700 gallons.

The Unit 3 and Unit 4 Principal Closure Documents YYY are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.02.07a.iii Completion Packages.

The volume of the PCCAWST is greater than 780.000 gallons.

VEGP 3 and 4 Updated Final Safety Analysis Report, Table 6.2.2-2, Component Data Passive Containment Cooling System (Nominal)(Reference 1) identifies that the nominal volume of the PCCAWST Is 885,000 gallons. The nominal volume of the PCCAWST is determined by the following method:

As-built measurements of the PCCAWST are taken by the tank vendor. These measurements are recorded and used to calculate the nominal volume of the PCCWST minus unavailable volume due to tank internals, and compared to the volume acceptance criteria of greater than 780,000 gallons.

The inspection results of the PCCAWST volume determination are documented in the Unit 3 and Unit 4 Principal Closure Documents ZZZ(References 7 and 8), and the calculated nominal volume of the PCCAWST (Tag No. PCS-MT-05) is XXX,XXX gallons for Unit 3, and XXX,XXX for Unit 4. This confirms that the volume of the PCCAWST is greater than 780,000 gallons.

Unit 3 and Unit 4 Principal Closure Documents ZZZ is available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.02.07a.iii Completion Packages.

List of ITAAC Findings 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 these ITAAC. The ITAAC completion review is documented in the ITAAC Completion Packages for ITAAC 2.2.02.07a.iii for Unit 3 and Unit 4(References X and X)and are available for NRC review.

References favaiiabie for NRC inspection)

1. VEGP 3&4 UFSAR, Revision 8.1

2. 26139-000-4MP-T81C-N3201, Rev. 5,"Bechtel Construction Survey"

3. Unit 3 Principal Closure Document XXX

4. Unit 4 Principal Closure Document XXX

5. Unit 3 Principal Closure Document YYY

6. Unit 4 Principal Closure Document YYY

7. Unit 3 Principal Closure Document ZZZ

8. Unit 4 Principal Closure Document ZZZ

9. 2.2.02.07a.iii-U3-CP-Rev0, ITAAC Completion Package

10. 2.2.02.07a.iii-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-19-1309 Enclosure Page 5 of 5

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