ND-18-0589, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08d (Index Number 200)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08d (Index Number 200)

ML18292A733
Person / Time
Site:	Vogtle
Issue date:	10/18/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.03.08d, ND-18-0589
Download: ML18292A733 (7)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell CCT 1 8 2018 myox southernco.com Docket Nos.: 52-025 ND-18-0589 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 2.2.03.08d [Index Number 2001 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 2.2.03.08d [Index Number 200]

for verifying the existence, volume and elevation ofthe pFI adjustment baskets in the Passive Core Cooling System. 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.

Michael J. Yox Regulatory Affairs Dfrefctor Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08d [Index Number 200]

MJY/GDL/amw

U.S. Nuclear Regulatory Commission ND-18-0589 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (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. Vox Mr. A. 8. Parton Ms. A. L. Pugh 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 Regulatory Commission Mr. W. Jones (w/o enclosures)

Mr. F. D. Brown Ms. J. M. Heisserer Ms. A. E. Rivera-Varona Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-0589 Page 3 of 3 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. 8. Roetger, Georgia Pubiic Service Commission Ms. 8. W. Kernizan, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-18-0589 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0589 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08d [Index Number 200]

U.S. Nuclear Regulatory Commission ND-18-0589 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment:

8.d) The PXS provides pH adjustment of water flooding the containment following design basis accidents.

Inspections.Tests. Analysis:

Inspection of the pH adjustment baskets will be conducted.

Acceptance Criteria:

pH adjustment baskets exist, with a total calculated volume ^ 560 ft^. The pH baskets are located below plant elevation 107 ft. 2 in.

ITAAC Determination Basis Inspections were performed on the Passive Core Cooling System (PXS) pH adjustment baskets (Attachment A) to ensure that the pH baskets exist, have a total calculated volume

> 560 ft3, and are located below plant elevation 107 ft. 2 in.

The pH adjustment baskets are seismic category 1 equipment. The baskets are made of stainless steel and have a mesh front to facilitate water contact with buffering material Tri-sodium Phosphate (TSP). The baskets are physically located inside the containment building in the corridor between the loop compartments, which is in the circulation flowpath during severe accident conditions, as described in Subsection 6.3.2.2.4 of the UFSAR.

Following fabrication of the pH adjustment baskets, the vendor performed inspections to measure the internal dimensions of each basket to calculate the internal volume. The total volume was calculated by summing the internal volumes of each of the four pH baskets and comparing to the minimum required volume in the design specifications. Vendor compliance with the design specificationswas documented in the quality data package for the baskets (Reference 1).

Following placement of the pH adjustment baskets in their final locations, the inspection of each basket elevation was performed by site personnel using survey equipment in accordance with the site survey and measurement procedure (Reference 2). The elevation of the feet/beam supports of each basket was measured in relation to a common reference point. Additionally, walkdowns of each basket confirmed their existence and calculations, based upon as-built manufacturer's data, combined with the field measurements, were used to determine the elevation of the top plate of each basket, and the results compared to plant elevation 107ft. 2in.

The results are documented in an inspection report (Reference 3) and shown in Attachment A, which meet the ITAAC acceptance criteria.

U.S. Nuclear Regulatory Commission ND-18-0589 Enclosure Page 3 of 4 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 2.2.03.08d (Reference 4) and available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08d was performed for VEGP Unit 3 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 favailable for NRC inspection)

1. SV3-MY07-VQQ-001, Rev. 1, "Quality Release and Certificate of Conformance"- Vogtle Unit 3 (SV3) pH Adjustment Baskets"

2. 4MP-T81C-N3201 Rev 1, "Construction Survey"

3. SV3-PXS-ITR-800200, Rev 0 "Unit 3 Inspection PXS pH Adjustment Baskets: ITAAC 2.2.03.08d"

4. 2.2.03.08d-U3-CP-Rev 0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-18-0589 Enclosure Page 4 of 4 Attacfiment A PXS pH Adjustment Basket Elevation and Volume Plant Elevation of Top Plate (Reference 3) As-Built Internal Component Name* Tag No.* Volume (Acceptance criteria (Reference 1) below plant elevation 107 ft. 2 in.)

pH Adjustment SV3-PXS-MY-03A 96 ft. 4 in. 114ft3 Basket 3A pH Adjustment SV3-PXS-MY-03B 96 ft. 4 in. 113 ft Basket 3B pH Adjustment SV3-PXS-MY-04A 98 ft. 5 in. 197 ft Basket 4A pH Adjustment SV3-PXS-MY-04B 98 ft. 4 in. 198 ft Basket 4B Total Volume of all four pH Adjustment Baskets 622 ft (Acceptance criteria > 560 ft^)

'Excerpt from COL Appendix C Table 2.2.3-1