ND-20-1222, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.vi.03 (Index Number 1911)

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Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.vi.03 (Index Number 1911)
ML20297A375
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 10/22/2020
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-1222
Download: ML20297A375 (6)
v • d • e


Text

Michael J. Yox 7825 River Road hk. Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tei OCT 2 2 2020 Docket No.: 52-026 ND-20-1222 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 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.vi.03 [Index Number 1911 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 15, 2020, Vogtle Electric Generating Plant(VEGP) Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.vi.03 [Index Number 191] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.03.08c.vi.03 [Index Number 191].

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 Vogtle 3&4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.2.03.08c.vi.03 [Index Number 191]

MJY/WLP/sfr

U.S. Nuclear Regulatory Commission ND-20-1222 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. Yox 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 Regulatory Commission M C. P. Patel M G. J. Khouri M N. D. Karlovich M A. Lerch M C. J. Even M B. J. Kemker Ms. N. C. Coovert M C. Welch M J. Gaslevic M V. Hall M G. Armstrong M M. Webb M T. Fredette M S. Smith M C. Santos M s. M. Bailey M S. Rose M B. Davis M J. Vasquez M J. Eargle M M. King M E. Davidson M T. Fanelli

U.S. Nuclear Regulatory Commission ND-20-1222 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 Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Orlani (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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-20-1222 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-1222 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.2.03.08c.vl.03[Index Number 191]

U.S. Nuclear Regulatory Commission ND-20-1222 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

Inspections/Tests/Analvses vi) Inspections of each of the following tanks will be conducted:

3.- IRWST Acceptance Criteria vi) The calculated volume of each of the following tanks is as follows:

3. IRWST > 73,100 ft^ between the tank outlet connection and the tank overflow ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. This ITAAC performs an inspection to verify the volume of the In-containment Refueling Water Storage Tank(IRWST) between the tank outlet connection and the tank overflow is greater than or equal to 73,100 ft^.

An inspection is performed of measurements made inside the IRWST. A laser scanner is used to determine the inside volume between the tank outlet connection and the tank overflow.

Various scanner locations are used within the tank to provide a complete scanned coverage of the internal surface of the IRWST. One complete data file consisting of the composite of the scans which represents the entire internal surface of the IRWST is analyzed. Significant permanent features that displace the useable tank volume such as the passive residual heat removal heat exchanger, the integrated head package stand, and the automatic depressurization system spargers, are represented in the scanned volume and mathematically removed from the IRWST useable volume. Smaller permanent features such as ladders are conservatively accounted for from the design calculation and also removed from the useable volume.

Measurements are taken using survey equipment in accordance with 26139-000-4MP-T81C-N3201,"Construction Survey"(Reference 1). The calculated volume of the IRWST represented by the 3-D model developed from the scanned data between the tank outlet connection and the tank overflow is determined to be XX,XXX ft^ which meets the minimum volume of 73,100 ft^

specified in the ITAAC Acceptance Criteria. The results of the inspection are documented in the Principal Closure Document SV4-PXS-FSK-800191 (Reference 2) and is available for NRC inspection as part of the Unit 4 ITAAC completion package (Reference 3).

U.S. Nuclear Regulatory Commission ND-20-1222 Enclosure Page 3 of 3 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 this ITAAC.

References favaiiabie for NRG inspection)

1. 26139-000-4MP-T81C-N3201 Rev. X, Construction Survey
2. SV4-PXS-FSK-800191 Rev. X, ITAAC Verification Volume of the IRWST
3. 2.2.03.08c.vi.03-U4-CP-Rev0, ITAAC Completion Package
4. NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52
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