ND-19-1556, Notification of Partial Completion of ITAAC 2.2.03.08c.x (Index Number 195)

Notification of Partial Completion of ITAAC 2.2.03.08c.x (Index Number 195)

ML19357A036
Person / Time
Site:	Vogtle
Issue date:	12/20/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1556
Download: ML19357A036 (6)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle3& 4 706-848-1959 tel DEC 2 0 2019 Docket Nos.: 52-025 ND-19-1556 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 3 Notification of Partial Completion of ITAAC 2.2.03.08c.x [Index Number 1951 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 partial completion of Vogtle Electric Generating Plant(VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.x [Index Number 195]for confirming the PXS provides RCS makeup, boration, and safety injection during design basis events. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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 partial ITAAC closure notification addresses an analysis showing that coatings applied on-site with a dry film density less than the ITAAC acceptance criteria will not transport in the post-accident containment flow. The remaining portions of the ITAAC regarding other coatings, tags and signs, ventilation filters, and fire barriers are not addressed. No other partial submittals have been submitted on this ITAAC.

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 Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Partial Completion of ITAAC 2.2.03.08c.x [Index Number 195]

MJY/PGL/sfr

U.S. Nuclear Regulatory Commission ND-19-1556 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. D. H. Jones(w/o enclosures)

Mr. G. Chick Mr. M. Page 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. J. L. Hughes 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 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. T. Fredette Mr. C. Weber Mr. S. Smith Mr. C. Santos Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1556 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. OrianI (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. CorlettI Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hosier, 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. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-1556 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-1556 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Partiai Compietion of ITAAC 2.2.03.08c.x [Index Number 195]

U.S. Nuclear Regulatory Commission ND-19-1556 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. Anaivses:

x) inspections will be conducted of the as-buiit nonsafety-reiated coatings or of plant records of the nonsafety-reiated coatings used inside containment on wails, floors, ceilings, and structural steel except in the CVS room, inspections will be conducted of the as-buiit nonsafety-reiated coatings or of plant records of the nonsafety-reiated coatings used on components below the maximum flood level of a design basis LOCA or located above the maximum flood level and not inside cabinets or enclosures.

Inspections will be conducted on caulking, tags, and signs used inside containment below the maximum flood level of a design basis LOCA or located above the maximum flood level and not inside cabinets or enclosures.

Inspections will be conducted of ventilation filters and fiber-producing fire barriers used inside containment within the ZOI or below the maximum flood level of a design basis LOCA.

Acceptance Criteria:

x) A report exists and concludes that the coatings used on these surfaces have a dry film density of s 100 Ib/ft^. If a coating is used that has a lower dry film density, a report must exist and conclude that the coating will not transport. A report exists and concludes that inorganic zinc coatings used on these surfaces are Safety- Service Level I or have been quantified and justified in a program for management of unqualified coatings to demonstrate the unqualified coatings are acceptable for use.

A report exists and concludes that tags and signs used in these locations are made of steel or another metal with a density s 100 lb/ft. In addition, a report exists and concludes that caulking used in these locations or coatings used on these signs or tags have a dry film density of s 100 lb/ft. If a material is used that has a lower density, a report must exist and conclude that there is insufficient water flow to transport lightweight caulking, signs, or tags.

A report exists and concludes that the ventilation filters and fire barriers in these locations have a density of ^ 100 Ib/ft^.

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 partial ITAAC Completion Notification (ICN) addresses only the portion of the acceptance criteria for coatings applied on-site regarding "If a coating is used that has a lower dry film density, a report must exist and conclude that the coating will not transport." The remaining portions of the ITAAC regarding other coatings, tags and signs, ventilation filters, and fire

U.S. Nuclear Regulatory Commission ND-19-1556 Enclosure Page 3 of 3 barriers will be addressed in the final ION. No other partial submittais have been submitted on this ITAAC.

One batch of coating applied in containment was identified as having a dry film density(DFD) value slightly less than the ITAAC acceptance criteria. Engineering & Design Coordination Report(E&DCR) APP-AX01-GEF-019(Reference 1) was performed to evaluate and address this batch of coating. This document performed an analysis to demonstrate that coatings with DFD values slightly less than the acceptance criteria are not transported to an API000 screen or into the core through a flooded break. The Unqualified Coating Log was updated to account for the lower density coating batch. See the details in Reference 1.

This evaluation provides evidence that the partial ICN portion of the ITAAC Acceptance Criteria requirements are met:

• If a coating is used that has a lower dry film density, a report must exist and conclude that the coating will not transport Reference 1 is available for NRC inspection.

References(available for NRG inspection)

1. Engineering & Design Coordination Report(E&DCR)APP-AX01-GEF-019 Rev. 0,"Dry Film Density Conversion Factor Correction"

2. NEI 08-01,"Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52"