ND-21-0389, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.vii (Index Number 192)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.vii (Index Number 192)

ML21266A417
Person / Time
Site:	Vogtle
Issue date:	09/23/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0389
Download: ML21266A417 (6)

Text

^ ,1 I I MichaelJ. Vox 7825 River Road

^OUtnGrn INUClSdr Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tel SEP 2 3 2021 Docket No.: 52-025 ND-21-0389 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.vii [Index Number 1921 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 Vogtie Electric Generating Plant(VEGP) Unit 3 inspections.

Tests, Analyses, and Acceptance Criteria ITAAC item 2.2.03.08c.vii [Index Number 192]. This ITAAC performed an inspection of the as-built plate located above the containment recirculation screens and verified that the plate size and location satisfy the ITAAC acceptance criteria. 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 Kelli A. Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.vii [Index Number 192]

MJY/JFV/sfr

U.S. Nuclear Regulatory Commission ND-21-0389 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. H. Nieh Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher 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 Mr. M. King Mr. G. Bowman Ms. A. Veil 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 . B. Davis M . J. Vasquez M . J. Eargle M . E. Davidson M T. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman

U.S. Nuclear Regulatory Commission ND-21-0389 Page 3 of 3 Oalethorpe 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. Oriani Mr. D. 0. Durham Mr. M. M. Gorletti 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, Batch BIngham

U.S. Nuclear Regulatory Commission ND-21-0389 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-21-0389 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.vii [Index Number 192]

U.S. Nuclear Regulatory Commission ND-21-0389 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.c) The PXS provides PCS makeup, boration, and safety injection during design basis events.

Inspections. Tests. Analvses vii) Inspection of the as-built components will be conducted for the plate located above the containment recirculation screens.

Acceptance Criteria vii) The plate located above the containment recirculation screens is no more than 1 ft, 3 in above the top of the face of the screens and extends at least 8 ft, 3 in perpendicular to the front and at least 7ft to the side of the face of the screens.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate the Passive Core Cooling System (PXS) provides Reactor Coolant System (PCS) makeup, boration, and safety injection during design basis events.

For this ITAAC, an inspection of the as-built components is conducted for the plate located above the containment recirculation screens(PXS-MY-Y02A and PXS-MY-Y02B)to confirm the plate is located no more than 1 ft, 3 in above the top of the face of the screens and extends at least 8 ft, 3 in perpendicular to the front and least 7ft to the side of the face of the screens.

Inspections were performed of the as-built components by taking as-built measurements using survey equipment in accordance with Nuclear Construction and Startup Procedure(NCSP)3-24, "Field Surveying"(Reference 1). NCSP 3-24 is used to establish layout and control points for determining the distance between the plate surfaces to the top and side face of the containment recirculation screens. The protective plate maximum height dimension is the distance between the top of the screens and the underside of the protective plate module top plate at the exposed edges of the protective plate, which extend into the containment recirculation water flow (east toward steam generator 2, and north toward the corridor), as described in the Updated Final Safety Analysis Report (UFSAR)Subsection 6.3.2.2.7(Reference 2). Measurements are taken using survey equipment in accordance with site survey and measurement procedures to derive the distance between the as built components.

The results of the inspection are documented in the Unit 3 inspection report(Reference 3) confirming the plate is no more than 1 ft, 3 in above the top of the face of the screens(maximum as-built distance is 1 ft, 1 in), extends out at least 8 ft, 3 in perpendicular to the front of the screens(minimum as-built distance 8 ft, 7.6 in), extends at least 7 ft to the side of the face of the screens (minimum as-built distance is 7 ft, 0.3 in), which meets the ITAAC Acceptance Criteria.

Reference 3 is available for NRC inspection as part of the Unit 3 ITAAC 2.2.03.08c.vii Completion Package (Reference 4).

U.S. Nuclear Regulatory Commission ND-21-0389 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 2.2.03.08c.vii (Reference 4) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.vii 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. Nuclear Construction and Startup Procedure(NCSP)3-24,"Field Surveying"

2. VEGP 3&4 Updated Final Safety Analysis Report(UFSAR), Revision 10.0, Subsection 6.3.2.2.7 "IRWST and Containment Recirculation Screens"

3. SV3-PXS-M6K-800192, Rev. 0,"PXS ITAAC 192 Cont. Recirc. Screens ITAAC Inspections/Field Measurements"

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