ND-20-1286, ITAAC Closure Notification on Completion of ITAAC 3.3.00.02h (Index Number 776)

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ITAAC Closure Notification on Completion of ITAAC 3.3.00.02h (Index Number 776)
ML20339A575
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 12/04/2020
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-1286
Download: ML20339A575 (6)


Text

^ ,1 >> I I MichaelJ. Yox 7825 River Road

^OUtilSm INUCl0dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle3&4 706-848-6459 tel DEC 0 h 2020 Docket No.: 52-025 ND-20-1286 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 3.3.00.02h [Index Number 7761 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant(VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria ITAAC item 3.3.00.02h [Index Number 776]. This ITAAC verified by inspection that the flood-up volume portion of the as-built containment is less than 71,960 ft^ to an elevation of 107.68'. The closure process for this ITAAC is based on 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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

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

Respectfully submitted, Hi Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 3.3.00.02h [Index Number 776]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-20-1286 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

Mr. M. D. Meier (w/o enclosures)

Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Vox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Requlatorv Commission Ms. M. Bailey (w/o enclosures)

M M. King M H. K. Nieh M C. P. Patel M G. J. Khouri M C. J. Even M B. J. Kemker Ms. N. C. Coovert M C. Welch M . J. Gaslevic M . O. Lopez-Santiago M . G. Armstrong M M. Webb M T. Fredette M . C. Santos M s. M. Bailey M B. Davis M J. Vasquez M J. Eargle M E. Davidson M T. Fanelli M S. Rose Ms. K. McCurry

U.S. Nuclear Regulatory Commission ND-20-1286 Page 3 of 3 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton 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 Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8.W. Kline, 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. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-20-1286 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-1286 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 3.3.00.02h [Index Number 776]

U.S. Nuclear Regulatory Commission ND-20-1286 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 loss-of-coolant accidents.

Inspections. Tests. 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-coolant accident in passive core cooling system valve/equipment room B (11207). The in-containment refueling water storage tank volume is excluded from this inspection.

Acceptance Criteria A report exists and concludes that the floodup volume of this portion of the containment is less than 71,960 ft^ to an elevation of 107.68".

ITAAC Determination Basis An inspection was 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 core cooling system (PXS)valve/equipment room B (11207). The In-containment Refueling Water Storage Tank(IRWST)volume is excluded from this inspection. The inspection report concluded that the floodup volume of this portion of the containment is less than 71,960 ft to an elevation of 107.68' which demonstrates the free volume in the containment allows for floodup to support long-term core cooling for postulated loss-of-coolant accidents.

The inspection consisted of measuring the areas in containment that flood with a LOCA in the PXS valve/equipment Room B(11207) using measurement equipment in accordance with site procedures. These measurements were used to confirm the calculation inputs (Reference 1) to calculate the free volume available is less than 71,960 ft to an elevation of 107.68".

The results of the inspection and a summary of the calculation for Unit 3 were documented in Principal Closure Document "Unit 3 Containment Floodup Volume Inspection; ITAAC 3.3.00.02h" (Reference 2). The report concludes that the floodup volume of the specified portions of the containment to an elevation of 107.68' was calculated to be 68,354 ft, which meets the ITAAC acceptance criteria of less than 71,960 ft to an elevation of 107.68". The results verified that the free volume in the containment allows for floodup to support long-term core cooling for postulated loss-of-coolant accidents.

References 1 and 2 are available for NRC inspection as part of the Unit 3 ITAAC 3.3.00.02h Completion Package (Reference 3).

U.S. Nuclear Regulatory Commission ND-20-1286 Enclosure Page 3 of 3 ITAAC Finding Review 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 this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.3.00.02h (Reference 3)and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.02h was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References(available for NRC inspection)

1. SV3-PXS-M3C-033, Rev. 0,"Containment Flood-Up Volume Calculation"
2. SV3-1100-ITR-800776, Rev. 0,"Unit 3 Containment Floodup Volume Inspection: ITAAC 3.3.00.02h"
3. 3.3.00.02h-U3-CP-Rev0, ITAAC Completion Package