ND-19-0793, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.v.01 (Index Number 187)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.v.01 (Index Number 187)

ML19177A268
Person / Time
Site:	Vogtle
Issue date:	06/26/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0793
Download: ML19177A268 (6)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel JUN 2 6 2019 Docket Nos.: 52-026 ND-19-0793 10 CFR 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 4 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.v.01 [Index Number 1871 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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.v.01 [Index Number 187]for verifying that the elevation of the bottom inside tank surface of the Core Makeup Tanks (CMTs) is higher than the direct vessel injection nozzle centerlines by greater than or equal to 7.5 ft.

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 sul^itted, Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.2.03.08c.v.01 [Index Number 187]

MJY/GDUsfr

U.S. Nuclear Regulatory Commission ND-19-0793 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. Yox 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 Reoulatorv Commission Mr. W. Jones(w/o enclosures)

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0793 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton 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. S. Roetger, 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-19-0793 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-0793 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 4 Completion of ITAAC 2.2.03.08c.v.01 [Index Number 187]

U.S. Nuclear Regulatory Commission ND-19-0793 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

I nspections/Tests/Analvses v) Inspections of the elevation of the following tanks will be conducted:

1.CMTS Acceptance Criteria v) The elevation of the bottom inside tank surface is higher than the direct vessel injection nozzle centerline by the following:

1. CMTs > 7.5 ft ITAAC Determination Basis 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 requires that inspections be conducted to verify that the elevation of the Core Makeup Tanks(CMTs) bottom inside tank surface is higher than the direct vessel injection nozzle centerline by ^ 7.5 ft.

The inspection of the bottom inside tank surface of both CMTs(SV4-PXS-MT-02A and -02B) and their associated direct vessel injection nozzle centerlines was performed using survey equipment in accordance with site survey and measurement procedures (Reference 1). The measured elevation of the bottom inside tank surface of each CMT was compared to the measured elevation of their associated direct vessel injection nozzle centerline using a common reference point.

The inspection results are documented in Reference 2. The results determined that the elevation of the bottom inside tank surface of CMT SV4-PXS-MT-02A and SV4-PXS-MT-02B is 107.12 feet and 107.09 feet, respectively and the elevation of their associated direct vessel injection nozzle centerlines is 99.58 feet and 99.58 feet, respectively. These inspection results verify that the elevation of the bottom inside tank surface of CMT SV4-PXS-MT-02A and -02B are both 7.5 ft higher than the elevation of their associated respective direct vessel injection nozzle centerlines, which meets the ITAAC acceptance criteria.

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 2.2.03.08c.iv.01 (Reference 3)and available for NRC review.

U.S. Nuclear Regulatory Commission ND-19-0793 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRG that ITAAC 2.2.03.08c.v.01 was performed for VEGP Unit 4 and that the prescribed acceptance criteria are 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 NRG inspection)

1. 4MP-T81C-N3201 Rev 5 "Construction Survey"

2. SV4-PXS-MTK-892047 Rev 0"CMT's Bottom Inside Tank Surface Comparison to DVI Nozzle Centerline Elevation"

3. 2.2.03.08c.v.01-U4-CP-Rev 0, ITAAC Completion Package