ND-18-0691, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.viii (Index Number 193)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.viii (Index Number 193)

ML18149A395
Person / Time
Site:	Vogtle
Issue date:	05/25/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0691
Download: ML18149A395 (7)

Text

C* iU M I MichaelJ. Yox 7825 River Road jOUtn0rn iNUCl03r Regulatory Affairs Director Waynesboro, GA 30830 Vogtle3 &4 706-848-6459 tel 410-474-8587 cell myox@southernco.com MAY 2 5 2018 Docket Nos.: 52-025 52-026 ND-18-0691 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.viii [Index Number 1931 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of May 10, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.viii [Index Number 193] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox Regulatory Affairs l^rector Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.viii [Index Number 193]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0691 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company M D. A. Bost (w/o enclosures)

M M. D. Rauckhorst (w/o enclosures)

M M. D. Meier M . D. H. Jones (w/o enclosures)

M D. L. McKinney M M. J. Vox M D. L. Fulton M J. B. Klecha M G. Chick M F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.LOG File AR.01.02.06 cc:

Nuclear Reaulatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oolethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0691 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. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, 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 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-18-0691 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0691 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.viii [Index Number 193]

U.S. Nuclear Regulatory Commission ND-18-0691 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment:

B.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

Insoections/Tests/Analvses:

viii) Inspections of the IRWST and containment recirculation 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 centerlines for pockets located beside each other. The height is the distance between pocket centerlines 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 s 6.2 in^ and a screen surface area ^

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 ^ 575 ft^, and a screen mesh size of 2 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 s 1150 ft^, and a screen mesh size ^ 0.0625 inch. Each containment recirculation screen has a sufficient number of pockets to provide a frontal face area s 105 ft^, a screen surface area ^ 2500 ft^, and a screen mesh size ^ 0.0625 inch.

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

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

ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Passive Core Cooling System (PXS) provides ReactorCoolant 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 recirculation 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 are performed to verify the debris curb in front of the containment recirculation 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 recirculation screens, the vendor determined the pocket screen area based upon the screen manufacturing drawings. The screen mesh size, which is the hole diameters in the perforated plates, are measured during production of the plates. The results are documented in the quality data package for the screens (References 2 and 3) and shown in Attachment A.

U.S. Nuclear Regulatory Commission ND-18-0691 Enclosure Page 3 of 4 Following installation of the IRWSTscreens, containment recirculation screens, and debris curb, inspections are performed in accordance with inspection procedure XYZ (Reference 1) to determine the pocket frontal face area and number of pockets in order to calculate the frontal face area of each screen. The inspection procedure utilizes guidance provided in Electric Power Research Institute (EPRI) Report TR-017218-R1 (Reference 4) to determine the number of pockets to measure. The inspection procedure also specifies required inspections and measurement locations to determine the distance from the bottom of the IRWST screens to the IRWST floor, the distance from the top of the containment recirculation screen debris curb to the loop compartmentfloor, 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. Measurements are taken using survey equipment in accordance with site survey and measurement procedures (Reference 7).

The total frontal face area of each screen and total screen surface area is calculated based on the width and height centerline measurements between pockets, the number of pockets installed in each screen, and the screen area inside each pocket. The width and height measurement is the distance between pocket centerlines for pockets located beside each other and above each other, respectively. The screen area inside each pocket is determined based on the screen manufacturing drawings.

The results are documented in the Unit 3 and Unit 4 Principal Closure Documents XXX and YYY (References 5 and 6, respectively) and shown in Attachment A, which meets the ITAAC acceptance criteria.

References 1, 2, 3, 5 and 6 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.03.08c.viii Completion Packages (References 8 and 9, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.

This reviewfound there are no relevant ITAAC findings associated with this ITAAC.

References ^available for NRG inspection)

1. Inspection Procedure XYZ

2. SV3-MY03-VQQ-001, Rev. X, "Quality Release and Data Package Vogtle 3 IRWST &

Containment Recirculation Screeens"

3. SV4-MY03-VQQ-001, Rev. X, "Quality Release and Data Package Vogtle 4 IRWST &

Containment Recirculation Screeens"

4. EPRI Report TR-017218-R1, "Guideline for Sampling in the Commercial-Grade Item Acceptance Process," January 1999

5. XXX Principal Closure Document (Unit 3)

6. YYY Principal Closure Document (Unit 4)

7. 26139-000-4MP-T81C-N3201, "Construction Surveying"

8. 2.2.03.08c.viii-U3-CP-Rev 0, ITAAC Completion Package

9. 2.2.03.08c.viii-U4-CP-Rev 0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-18-0691 Enclosure Page 4 of 4 Attachment A IRWST and Containment Recirculation Screen Areas and Measured Clearances +

Screen Surface Total Total Pocket Frontal Screen Mesh size Area per Calculated Calculated Component Name* Tag No.* Face Area (AC < 0.0625 Pocket Frontal Face Screen Surface (AC > 6.2 in^) inch)

(AC > 140 in^) Area Area PXS-MY- X.Xft2 x.xft^

IRWST Screen A X.X in^ X.X in^ X.X inch Y01A (AC>25ft2) (AC>575ft2)

PXS-MY- X.Xft2 x.xft2 IRWST Screen B X.X in^ X.X in^ X.X inch Y01B (ACs25ft2) (AC>575ft2)

PXS-MY- x.xft^ x.xft^

IRWST Screen C X.X in^ X.X in^ X.X inch Y01C (AC>50ft2) (ACSllSOft^)

Containment PXS-MY- x.xft^ x.xft^

X.X in^ X.X in^ X.X inch (ACS 2500 ft2)

Recriculation Screen A Y02A (AC> 105ft2)

Containment PXS-MY- x.xft^ x.xft^

X.X in^ X.X in^ X.X inch Recricuiation Screen B Y02B (ACS lOSft^) (ACS 2500 ft2)

Minimum measured distance from the top of the debris curb in front of the containment recirculation screens to the loop compartment floor is X.X 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 X.X inch above the fioor iRWST Screen B bottom is X.X inch above the floor IRWST Screen C bottom is X.X inch above the floor

• Excerpt from COL Appendix C, Table 2.2.3-1

+ Results are Unit specific