ND-19-0706, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.04.04.1 (Index Number 330)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.04.04.1 (Index Number 330)

ML19177A292
Person / Time
Site:	Vogtle
Issue date:	06/26/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0706
Download: ML19177A292 (7)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel JUN 2 6 2019 Docket Nos.: 52-025 52-026 ND-19-0706 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 2.3.04.04.1 [Index Number 3301 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 24, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.3.04.04.1[Index Number 330] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.3.04.04.1[Index Number 330]. 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 tfiat 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.

4or 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 2.3.04.04.1 [Index Number 330]

MJY/GJL/sfr

U.S. Nuclear Regulatory Commission ND-19-0706 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.LOG File AR.01.02.06 cc:

Nuclear Reaulatorv 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. P. O'Bryan Mr. T. Fredette Mr. C. Weber Qqiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0706 Page 3 of 3 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 Ms. L. G. Iller Ms. J. Monahan 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. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-19-0706 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0706 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC Item 2.3.04.04.1 [Index No.330]

U.S. Nuclear Regulatory Commission ND-19-0706 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment

4. The FPS provides for manual fire fighting capability in plant areas containing safety-related equipment.

6. The FPS provides nonsafety-related containment spray for severe accident management.

7. The FPS provides two fire water storage tanks, each capable of holding at least 100 percent of the water supply necessary for FPS use.

Insoections/Tests/Analvses i) Inspection of the passive containment cooling system (PCS)storage tank will be performed.

Inspection of the containment spray headers will be performed.

Inspection of each fire water storage tank will be performed.

Acceptance Criteria i) The volume of the PCS tank above the standpipe feeding the FPS and below the overflow is at least 18,000 gal.

The FPS has spray headers and nozzles as follows:

At least 44 nozzles at plant elevation of at least 260 feet, and 24 nozzles at plant elevation of at least 275 feet.

The volume of water dedicated to FPS use provided in each fire water storage tank is at least 396,000 gallons.

ITAAC Completion Description Multiple ITAACs are performed to demonstrate that the Fire Protection System (FPS) provides for manual fire fighting capability in plant areas containing safety-related equipment, the FPS provides nonsafety-related containment spray for severe accident management, and the FPS provides two fire water storage tanks, each capable of holding at least 100 percent of the water supply necessary for FPS use. This ITAAC requires inspections to be performed of the Passive Containment Cooling System (PCS)storage tank, the containment spray headers, and each fire water storage tank.

i) The volume of the PCS tank above the standoioe feedino the FPS and below the overflow is at least 18.000 oal.

Inspections of the Passive Containment Cooling Water Storage Tank(PCCWST)and line elevation measurements for the standpipe feeding the FPS and the PCCWST overflow standpipe are performed to demonstrate that the volume of the PCCWST above the standpipe feeding the FPS and below the overflow is at least 18,000 gallons. The PCCWST usable

U.S. Nuclear Regulatory Commission ND-19-0706 Enclosure Page 3 of 4 volume above the standpipe feeding the FPS and below the PCCWST overflow standpipe is calculated, using the PCCWST dimensions and line elevation measurements, and compared to the ITAAC acceptance criteria of at least 18,000 gallons.

The inspection results of the PCS storage tank volume above the standpipe feeding the FPS and below the PCCWST overflow and the calculated volume are documented in the Principal Closure Documents(Reference 1 & 2). The volume of the PCS storage tank (Tag No. PCS-MT-01)above the standpipe feeding the FPS and below the overflow standpipe is XX,XXX gallons.

This confirms that the volume of the PCS storage tank above the standpipe feeding the FPS and below the overflow is at least 18,000 gallons, in accordance with the ITAAC acceptance criteria.

The FPS has sorav headers and nozzles as follows:

At least 44 nozzles at plant elevation of at least 260 feet, and 24 nozzles at plant elevation of at least 275 feet.

Inspection of the containment spray headers in the Fire Protection System (FPS)are performed to demonstrate that the FPS provides nonsafety-related containment spray for severe accident management. The inspection is performed to determine the number and elevation of the containment spray nozzles. The number of containment spray nozzles is determined by counting the number of spray nozzles at each of the two (upper and lower) ring headers located above the containment polar crane.

The number and elevation of the FPS containment spray headers and nozzles are compared to the ITAAC acceptance criteria. The results of the comparison are documented in Principle Closure Documents(References 1 & 2). The results verify that the FPS has at least 44 containment spray nozzles at plant elevation of at least 260 feet, and 24 containment spray nozzles at plant elevation of at least 275 feet, in accordance with the ITAAC acceptance criteria.

The volume of water dedicated to FPS use orovided in each fire water storaoe tank is at least 396.000 Gallons.

Inspections are performed to verify that the Fire Protection System (FPS) provides two fire water storage tanks, each capable of holding at least 396,000 gallons of water, per the VEGP 3&4 Updated Final Safety Analysis Report, Table 9.5.1-2, Component Data - Fire Protection System (Nominal Values). The FPS tanks are identified as the Primary Fire Water Tank (FPS-MT-01 A) and the Secondary Fire Water Tank (FPS-MT-01B). Measurements and calculations for these fire water storage tanks are conducted to verify that the dedicated volume of each tank to the FPS is at least 396,000 gallons.

The volume of the Primary Fire Water Tank and the Secondary Fire Water Tank are determined by the following method.

The dimensions of each fire water storage tank are measured and recorded following tank fabrication. Each tank's as-built dedicated volume is calculated and compared to the minimum volume acceptance criteria of 396,000 gallons per fire water storage tank.

The results of the Primary Fire Water Tank and the Secondary Fire Water Tank volume determinations are documented in the Principal Closure Documents(Reference 1 & 2). The calculated dedicated volume of the Primary Fire Water Tank is XXX,XXX gallons and the

U.S. Nuclear Regulatory Commission ND-19-0706 Enclosure Page 4 of 4 Secondary Fire Water Tank is XXX,XXX gallons. This confirms that the dedicated volume of each fire water storage tank supplying the FPS is at least 396,000 gallons, in accordance with the ITAAC acceptance criteria.

Measurements taken to meet the ITAAC acceptance criterias are taken using survey equipment in accordance with the Bechtel Construction Survey procedure (Reference 3), as applicable.

The inspection results are available for NRC inspection as part of the ITAAC 2.3.04.04.1 Completion Package (Reference 4 & 5).

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 2.3.04.04.1 for Unit 3 and Unit 4(References 4 and 5)and are available for NRC review.

References(availabie for NRC inspection)

1. Unit 3 Principal Closure Document ITAAC 2.3.04.04.1 [Index No. 330](SV3-AA-BBB-###)

2. Unit 4 Principal Closure Document ITAAC 2.3.04.04.1 [Index No. 330](SV4-AA-BBB-###)

3. 26139-000-4MP-T81C-N3201, Rev. 5,"Bechtel Construction Survey"

4. 2.3.04.04.i-U3-CP-Rev0, ITAAC Completion Package

5. 2.3.04.04.i-U4-CP-Rev0, ITAAC Completion Package

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