ND-21-0267, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.viii (Index Number 193)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.viii (Index Number 193)

ML21274A739
Person / Time
Site:	Vogtle
Issue date:	10/01/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.2.03.08c.viii, ND-21-0267
Download: ML21274A739 (8)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel OCT 0 I 2021 Docket No.: 52-025 ND-21-0267 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 2.2.03.08c.viii [Index Number 1931 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 2.2.03.08c.viii [Index Number 193] for the inspection of the as-built components verification of the frontal face area, screen surface area, and screen mesh size of the In-containment Refueling Water Storage Tank (IRWST) and Containment Recirculation Screens in the containment building. 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. Yox Regulatory Affairs Director'Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.viii [Index Number 193]

MJY/JFV/sfr

U.S. Nuclear Regulatory Commission ND-21-0267 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKlnney 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 Regulatory 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 M J. Parent M B. Griman

U.S. Nuclear Regulatory Commission ND-21-0267 Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. OrlanI Mr. D. 0. Durham 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., CDS 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0267 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-20-0267 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.vlll [Index Number 193]

U.S. Nuclear Regulatory Commission ND-21-0267 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

inspections. Tests. Anaivses viii) inspections of the IRWST and containment recircuiation screens will be conducted. The inspections will include measurements of the pockets and the number of pockets used in each screen. The pocket frontal face area is based on a width times a height. The width is the distance between pocket centeriines for pockets located beside each other. The height is the distance between pocket centeriines for pockets located above each other. The pocket screen area is the total area of perforated plate inside each pocket; this area will be determined by inspection of the screen manufacturing drawings.

Acceptance Criteria viii) The screens utilize pockets with a frontal face area of > 6.2 in^ and a screen surface area s 140 in^ per pocket. IRWST Screens A and B each have a sufficient number of pockets to provide a frontal face area s 25 ft^, a screen surface area s 575 ft^, and a screen mesh size of s 0.0625 inch. IRWST Screen C has a sufficient number of pockets to provide a frontal face area s 50 ft^, a screen surface area 2:1150 ft^, and a screen mesh size 2 0.0625 inch. Each containment recircuiation screen has a sufficient number of pockets to provide a frontal face area >105 ft^, a screen surface area ^ 2500 ft^, and a screen mesh size s 0.0625 inch.

A debris curb exists in front of the containment recircuiation screens which is s 2 ft above the loop compartment floor.

The bottoms of the IRWST screens are located s 6 in above the bottom of the IRWST.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. The subject ITAAC requires an inspection of the In Containment Refueling Water Storage Tank(IRWST)screens and containment recircuiation screens to verify the frontal face area, screen surface area, and screen mesh size meet the acceptance criteria as shown in Attachment A. In addition, inspections were performed to verify the debris curb in front of the containment recircuiation screens is s 2 ft above the loop compartment floor, and the bottoms of the IRWST screens are located > 6 in above the bottom of the IRWST.

Following fabrication of the IRWST and containment recircuiation screens, the vendor determined the pocket screen area based upon the screen manufacturing drawings and verified by vendor field measurements. The screen mesh size, which is the hole diameters in the perforated plates, were measured during production of the plates. Vendor compliance with the design specifications, which included verification of the screen surface area per pocket and screen mesh size, was documented in Reference 1, and shown in Attachment A.

U.S. Nuclear Regulatory Commission ND-21-0267 Enclosure Page 3 of 5 Following receipt of the screens, inspections were performed in accordance with Reference 2 to determine the pocket frontal face area, and the results are shown in Attachment A. The inspection plan utilized guidance provided in Electric Power Research Institute (EPRI) Report TR-017218-R1 (Reference 7)to determine the number of pockets to measure. The pocket frontal face area is based on a width times a height. The width is the distance between pocket centerlines for pockets located beside each other. The height is the distance between pocket centerlines for pockets located above each other.

Following installation of the IRWST screens, containment recirculation screens, and debris curb, inspections were performed to determine the number of pockets in order to calculate the frontal face area of each screen (References 3 and 4). Inspections were performed to determine the distance from the bottom of the IRWST screens to the IRWST floor (Reference 3), the distance from the top of the containment recirculation screen debris curb to the loop compartment floor (Reference 4), and verification that the debris curb in front of the containment recirculation screens is installed in its proper location and final configuration in accordance with design specifications (Reference 4). Measurements were taken using survey equipment in accordance with site survey and measurement procedures (Reference 6).

The total screen surface area was calculated based on the number of pockets installed in each screen and the screen area inside each pocket. The screen area inside each pocket was determined based on the screen manufacturing drawings and verified by vendor field measurements (Reference 1). Conservatively, for calculating the total frontal face area of the screens, the acceptance criteria value of the pocket frontal face area and the number of pockets installed in each screen was used (References 3 and 4).

The results are documented in the Unit 3 Principal Closure Documents SV3-MY03-VDR-002, SVO-PXS-ITR-800193, SV3-PXS-M6K-801193, and SV3-PXS-M6K-802193(References 1 through 4)and are shown in Attachment A, which meets the ITAAC acceptance criteria.

References 1 through 4 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.03.08c.viii Completion Package (Reference 5).

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.viii (Reference 5) 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.viii 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.

U.S. Nuclear Regulatory Commission ND-21-0267 Enclosure Page 4 of 5 References(available for NRG inspection)

1. SV3-MY03-VDR-002, Rev. 0,"ITAAC 2.2.03.08c.vjli Verification Report".

2. SVO-PXS-ITR-800193, Rev. 0,"Units 3 & 4 Frontal Face Area Inspection: ITAAC 2.2.03.08c.vjjl NRC Index 193"

3. SV3-PXS-M6K-801193, Rev. 0,"PXS ITAAC 193 IRWST Recirc. Screens ITAAC Inspections/Field Measurements"

4. SV3-PXS-M6K-802193, Rev. 0,"PXS ITAAC 193 Containment Recirc. Screens & Weir Inspections/Field Measurements"

5. 2.2.03.08c.viii-U3-CP, Rev. 0, ITAAC Completion Package

6. Nuclear Construction and Startup Procedure(NCSP)3-24,"Field Surveying"

7. TR-017218-R1, Electric Power Research Institute (EPRI) Report

U.S. Nuclear Regulatory Commission ND-21-0267 Enclosure Page 5 of 5 Attachment A IRWST and Containment Recirculation Screen Areas and Measured Clearances r, . , Screen Pocket o ( Screen

^ . , Surface Frontal . Mesh size Total Component Tag Face Area Calculated K,-* Pocket Name* (AC< Frontal (ACS 6.2 (AC >140 0.0625 Face Area in') ^ i2x inch)

IRWST SV3- 6.5 in^ 143 in^ 0.0622 26 ft2 Screen A PXS- inch MY- (AC >25 Y01A J!)

IRWST SV3- 6.5 in^ 143 in^ 0.0622 26ft2 Screen 8B PXS- inch MY- (AC > 25 Y01B Jt!)

IRWST SV3- 6.5 in^ 143 in2 0.0622 52ft2 Screen C PXS- inch MY- (AC > 50 Y01C J!)

Containment SV3- 6.4 in^ 143 in^ 0.0622 109ft2 Recirculation PXS- inch Screen A MY- (ACS 105 Y02A J!)

Containment SV3- 6.4 in^ 143 in^ 0.0622 109ft2 Recirculation PXS- inch Screen B MY- (ACS 105 Y02B ft^)

Minimum measured distance from the top of the debris curb in front of the containment recirculation screens to the loop compartment floor is 2.018 ft.(AC s 2 ft)

Minimum measured distance from the bottoms of the IRWST screens to the floor of the IRWST(AC s 6 in).

IRWST Screen A bottom is 6.6 inch above the floor IRWST Screen B bottom is 6.1 inch above the floor IRWST Screen C bottom is 6.6 inch above the floor Excerpt from COL Appendix C, Table 2.2.3-1