ND-17-2043, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02h (Index Number 776)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.02h (Index Number 776)

ML18019A100
Person / Time
Site:	Vogtle
Issue date:	01/04/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-17-2043
Download: ML18019A100 (7)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox @southernco.com JAN 0 4 2018 Docket Nos.: 52-025 52-026 ND-17-2043 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Cbntrol 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 3.3.00.02h [Index Number 7761 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 02, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.3.00.02h

[Index Numbejr 776] 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 dat4, 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 Closu e 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 operatic n, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are ariy questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yo^

Regulatory Affairs Director Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-17-2043 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.3.00.02h [Index Number776]

MJY/LBP/am w

U.S. Nuclear Regulatory Commission ND-17-2043 Page 3 of 4 To:

Southern Nit clear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Ra J ckhorst (w/o enclosures)

Mr. M. D. Mei<er Mr. D. H. Jor es (w/o enclosures)

Mr. D. L. MoiCi nney Mr. M. J. Yo>

Mr. D. L. Fultpin Mr. J. D. Will ams Mr. F. H. Will is Ms. A. L. Fuji h Mr. A. 8. Par;(on Mr. W. A. Spa!rkman Mr. 0. E. Mornow Ms. K. M. St£i(cy Mr. M. K. WasIhington Mr. J. P. Redd Ms. A. C. Chaimberlain Mr. D. R. Cul yer Mr. R. L. Beil <e Mr. T. G. Pet! 3,k Document S4 rvicesRTYPE: VND.LI.L06 File AR.01.02 .06 cc; Nuclear Reobiatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisiserer Mr. 0. P Pate Mr. M. E. Ern stes Mr. G. J. Kho uri Mr. T. E. Ch^i ndler Ms. S. E pie Ms. P. Braxtc n Mr. T. 0. Briiinhfield Mr. A. J. Lerc h Mr. C. J.

Mr. F. D. Brolyvn Mr. B. J. Ken) ker Ms. A. E. Riveira-Varona Oaiethorpe i*ower Corooration Mr. R. B. Brirkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-17-2043 Page 4 of 4 Dalton UtilitI]§§ Mr. T. Bundros Westinahou se Electric Company. LLC Dr. L. Oriani w/o enclosures)

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

Mr. M. M. Co rietti Ms. L. G. met Mr. D. Hawkiii:s Ms. 8. DiTomimaso Mr. J. L. Cow ard Ms. N. E. Deangelis Other Mr. J. E. Hes er, Bechtel Power Corporation Ms. L. Matis, 'etra Tech NUS, Inc.

Dr. W. R. Jac;bbs, Jr., Ph.D., GDSAssociates, inc.

Mr. 8. Roetgeir, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-17-2043 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-17-2043 Enclosure Vogtle Electric Generating Riant (VEGP) Unit 3 and Unit 4 Corlipletion Plan for Uncompleted ITAAC 3.3.00.02h [Index Number 776]

U.S. Nuclear Regulatory Commission ND-17-2043 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 2.h) The free volume in the containment allows for floodup to support long-term core cooling for postulated losis-of-coolant accidents.

Insoections/T ests/Analvses An inspection will be performed of the as-built containment structures and equipment. The portions of the containment included in this inspection are the volumes that flood with a loss-of-coolatl)t accident in passive core cooling system valve/equipment room B (11207). The in-containmeiht refueling water storage tank volume is excluded from this inspection.

Acceotance Criteria A report exist 3and concludes that the floodup volume of this portion of the containment is less than 73,500 fi^ to an elevation of 108'.

ITAAC Comc letion Description An inspection is performed of the as-built containment structures and equipment. The volumes included in the inspection and calculation are the volumes that flood with a loss-of-coolant accident (LOCA) in passive corecooling system (PXS) valve/equipment room B(11207). The In-containmerrt Refueling Water Storagetank (IRWST) volume is excluded from this inspection.

The inspectio i report concludes thatthe floodup volume ofthis portion of the containment is less than 73,500 ft to an elevation of 108' which demonstrates the free volume in the containment ^Hows for floodup to support long-term core cooling for postulated loss-of-coolant accidents.

The inspectiop consists of measuring the areas in containment that flood with a LOCA in the PXS valve/eq jipment Room B(11207) using measurement equipment in accordance with site procedures. 1 hese measurements are used to confirm the calculation inputs (References 1 and 2), or used to calculate the free volume available is less than 73,500 ft to an elevation of 108'.

The results of the inspection and a summary of the calculations for Unit 3 and Unit 4 are documented in Principle Closure Document XXX (Unit 3) and Principle Closure Document YYY (Unit 4) (References 3 and 4). The reports conclude that the floodup volume of the specified portions of the containment to an elevation of 108' is calculated to beXX,XXX ft (for Unit 3),

and YY,YYY ft (for Unit 4), which meets the ITAAC acceptance criteria of less than 73,500 ft to an elevation of 108' for each unit. The results verify that the free volume in the containment allows for floodup to support long-term core cooling for postulated loss-of-coolant accidents.

The Unit 3 anifi Unit 4 Principal Closure Documents XXX and YYY are available for NRC inspection as Dart of the Unit 3 and Unit 4 ITAAC 3.3.00.02h Completion Packages (References 5 and 6).

U.S. Nuclear Regulatory Commission ND-17-2043 Enclosure Page 3 of 3 List of iTAA( ^ FIndlnas 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 wnh this ITAAC.

References favallable for NRG inspection)

1. APP-PXS^M3C-033, "Containment Flood-Up Volume Calculation"

2. APP-PXSJ-M3C-034, "Containment Flood-Up Level"

3. Principal (Closure Document XXX (Unit 3)

4. Principal Closure Document YYY (Unit 4)

5. XXX, "Completion Package for Unit 3 ITAAC 3.3.00.02h [Index Number 776]"

6. YYY, "Completion Package for Unit 4 ITAAC 3.3.00.02h [Index Number 776]"

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