ND-19-0707, Unit 4 - Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.3.00.06a (Index Number 787)

Unit 4 - Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.3.00.06a (Index Number 787)

ML19168A120
Person / Time
Site:	Vogtle
Issue date:	06/17/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0707
Download: ML19168A120 (6)

Text

Michael J. Yox 7825 River Road itL Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei JUN 1 7 2019 Docket Nos.: 52-025 52-026 ND-19-0707 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.3.00.06a [Index Number 7871 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 14, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 3.3.00.06a

[Index Number 787] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 3.3.00.06a[Index Number 787]. 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 Vogtie 3&4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.06a [Index Number 787]

MJY/GJL/sfr

U.S. Nuclear Regulatory Commission ND-19-0707 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 Reaulatorv Commission Mr. W.Jones(w/o enclosures)

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khourl Ms. S. E. Temple Mr. N. D. Karlovlch 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 Qqlethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0707 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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-19-0707 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-0707 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC Item 3.3.00.06a [Index No.787]

U.S. Nuclear Regulatory Commission ND-19-0707 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment 6.a) The available room volumes of the radiologically controlled area of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).

Insoections/Tests/Analvses An inspection will be performed of the as-built radiologically controlled area of the auxiliary building between floor elevations 66'-6" and 82'-6" to define volume.

Acceptance Criteria A report exists and concludes that the as-built available room volumes of the radiologically controlled area of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11)

ITAAC Completion Description This ITAAC is performed to demonstrate that the available room volumes of the radiologically controlled area(RCA)of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11). This ITAAC requires that an inspection be performed of the as-built RCA of the auxiliary building between floor elevations 66'-6" and 82'-6" to ensure available room volume exceeds the volume of the liquid radwaste storage tanks.

The as-built tank volumes of the liquid radwaste storage tanks are documented in the as-built information contained in the Quality Assurance Data Package(QADP) provided for each tank.

Inspections of the RCA portion of the auxiliary building rooms between elevations 66'-6" and 82'-6" are performed to the extent necessary to demonstrate and document that available room volume is more than the as-built tank volumes. Available room volume for this purpose is defined as the total room volume minus the volume of components or commodities within the room. Only those RCA auxiliary building rooms needed to provide the available room volume needed to meet the ITAAC acceptance criteria are inspected. Examples of such rooms are defined personnel and/or equipment access corridors, and reserved equipment removal spaces.

Measurements taken to calculate available room volume are taken using survey equipment in accordance with the site survey and measurement procedure (Reference 1), as applicable.

The as-built tank volumes of the liquid radwaste storage tanks are XXX ft and the available room volume of the RCA in the auxiliary building is XXX ft. The inspection plan, results of the visual inspections, available room volume calculation, and as-built tank volumes are documented in Principal Closure Documents (Reference 2 and 3)that demonstrate that the as-built available room volumes for the RCA portion of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the as-built volume of the liquid radwaste storage tanks.

U.S. Nuclear Regulatory Commission ND-19-0707 Enclosure Page 3 of 3 The inspection results and calculations conclude that the as-built available room volumes of the RCA of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).

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 3.3.00.06a Unit 3 and Unit 4(Reference 4 and 5)and are available for NRC review.

References(available for NRG inspection)

1. 26139-000-4MP-T81C-N3201, Rev. 5,"Bechtel Construction Survey"

2. Unit 3 Principal Closure Document ITAAC 3.3.00.06a [Index No. 787](SV3-AA-BBB-###)

3. Unit 4 Principal Closure Document ITAAC 3.3.00.06a [Index No. 787](SV4-AA-BBB-###)

4. 3.3 00.06a-U3-CP-Rev0, ITAAC Completion Package

5. 3.3 00.06a-U4-CP-Rev0, ITAAC Completion Package

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