ND-17-2043, 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
Southern Nuclear JAN 0 4 2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Cbntrol Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 &4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-17-2043 10 CFR 52.99(c)(3)
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 priorto initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, ata 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 Guide 1.215.
e Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory 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 partiallycompleted. All ITAAC will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operatic fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be 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 ND-17-2043 Page 2 of 4
Enclosure:
Regulatory Commission Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit4 Completion Plan for Uncompleted ITAAC 3.3.00.02h [Index Number776]
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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 Number776]
U.S. Nuclear ND-17-2043 Page 2 of 3 Regulatory Commission Enclosure ITAAC Statement Design Commitment 2.h) The free postulated volume in the containment allows for floodup to support long-term core cooling for is-of-coolant accidents.
los Insoections/Tests/Analvses An inspection portions of the loss-of-coolatl) in-containme will be performed of the as-built containment structures and equipment. The containment included in this inspection are the volumes that flood with a t accident in passive core coolingsystem valve/equipment room B (11207). The iht refueling waterstorage tank volume is excluded from this inspection.
Acceotance Criteria 3and concludes that the floodup volume of this portion of the containment is less A report exist 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. Thevolumes included in the inspection and calculation are the volumes thatflood 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 isexcluded from thisinspection.
Theinspectio i report concludes thatthe floodup volume ofthis portion of thecontainment 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 PXS valve/eq procedures. 1 2), or used to consists of measuring the areas in containment that flood with a LOCA in the jipment Room B(11207) using measurement equipment in accordance with site hese measurements are used to confirm the calculation inputs (References 1 and calculate the free volume available is less than 73,500 ft to an elevation of 108'.
The results ofthe inspection and a summary ofthe 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 inthe containment allows for floodup to support long-term corecooling for postulated loss-of-coolant accidents.
The Unit 3 anifi inspection as 5 and 6).
Unit 4 Principal Closure Documents XXX and YYY are available for NRC Dart of the Unit 3 and Unit4 ITAAC 3.3.00.02h Completion Packages (References
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 allfindings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings 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 (Unit3) 4.
Principal Closure Document YYY (Unit4) 5.
XXX, "Completion Package for Unit 3 ITAAC 3.3.00.02h [Index Number776]"
6.
YYY, "Completion Package for Unit 4 ITAAC 3.3.00.02h [Index Number 776]"
7.
NEI 08-01 "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"