ND-18-0498, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.xii (Index Number 197)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.xii (Index Number 197)

ML18106A790
Person / Time
Site:	Vogtle
Issue date:	04/13/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.03.08c.xii, ND-18-0498
Download: ML18106A790 (7)

Text

k. I I Michael J. Yox 7825 River Road

^ 5OUtn0rn NLICl03r Regulatory Affairs Director Waynesboro, GA 30830 Vogtle3&4 706-848-6459 tel 410-474-8587 cell APR t 3 2018 myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0498 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.xll [Index Number 1971 Ladles and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 6, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.xll [Index Number 197] 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 DIrebtor Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.xll [Index Number 197]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0498 Page 2 of 3 To:

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

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

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

Mr. D. L. McKinney Mr. M. J. Vox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. 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.L06 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 Oalethorpe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0498 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton 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-18-0498 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0498 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.xll [Index Number 197]

U.S. Nuclear Regulatory Commission ND-18-0498 Enclosure Page 2 of 4 ITAAC Statement Design Commitment:

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

Inspections. Tests. Analvses:

xii) Inspections will be conducted of the CMT level sensors (PXS-11A/B/D/C, - 12A/B/C/D, -

13A/B/C/D, - 14A/B/C/D) upper level tap lines.

Acceptance Criteria:

xii) Each upper level tap line has a downward slope of ^ 2.4 degrees from the centerline of the connection to the CMT to the centerline of the connection to the standpipe.

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 ITAAC requires inspections to be performed of each Core Makeup Tank (CMT) level sensors (PXS-11A/B/D/C, - 12A/B/C/D, - 13A/B/C/D, - 14A/B/C/D) upper level tap lines to verify that each upper level tap line has a downward slope of ^ 2.4 degrees from the centerline of the connection to the CMT to the centerline of the connection to the standpipe.

An inspection of the installed CMT level sensors upper level tap lines is performed using survey equipment in accordance with site survey and measurement procedures. The inspection is performed using specified survey locations and common reference points to measure the elevation and distance of each upper level tap line from the centerline of the connection to the CMT to the centerline of the connection to the standpipe. The survey measurements are recorded and used to calculate the as-built slope of each upper level tap line to ensure it meets the acceptance criteria.

The inspection results are shown in Attachment A and documented in the Unit 3 and Unit 4 Principal Closure Documents (References 1 and 2, respectively) which confirm that each upper level tap line has a downward slope of ^ 2.4 degrees from the centerline ofthe connection to the CMT to the centerline of the connection to the standpipe and meets the ITAAC acceptance criteria.

References 1 and 2 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.03.08c.xii Completion Packages (References 3 and 4, 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 pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-18-0498 Enclosure Page 3 of 4 References (available for NRG inspection)

1. Principal Closure Document XXX (Unit 3)

2. Principal Closure Document YYY (Unit 4)

3. 2.2.03.08c.xii-U3-CP-Rev X, "Completion Package for the Unit 3 ITAAC 2.2.03.08c.xii [Index Number 197]"

4. 2.2.03.08c.xii-U4-CP-Rev X, "Completion Package for the Unit 4 ITAAC 2.2.03.08c.xii [Index Number 197]"

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

U.S. Nuclear Regulatory Commission ND-18-0498 Enclosure Page 4 of 4 Attachment A GMT level sensors upper level tap line slope (Acceptance criteria s 2.4 degrees)

Units Unit 4 GMT Level GMT Level Upper Level Galculated Galculated Sensor GMT* Sensor* Tap Line++ as-built slope as-built slope Standplpe+ (degrees) (degrees)

PXS-11A/C PXS-MY-Y11A PXS-PL-L082A x.x v.v PXS-MT- PXS-11B/D PXS-MY-Y12A PXS-PL-L086A x.x v.v 02A PXS-13A/C PXS-MY-Y13A PXS-PL-L092A X.X v.v PXS-13B/D PXS-MY-Y14A PX8-PL-L096A x.x v.v PXS-12A/C PXS-MY-Y12B PXS-PL-L082B x.x v.v PXS-MT- PXS-12B/D PXS-MY-Y11B PXS-PL-L086B x.x v.v 02B PXS-14A/C PXS-MY-Y14B PXS-PL-L092B x.x v.v PXS-14B/D PXS-MY-Y13B PXS-PL-L096B x.x v.v

• Excerpt from COL Appendic C Table 2.2.3-1

+Excerpt from UFSAR Table 3.2-3

++ Reference Piping & Instrumentation Drawing APP-PXS-M6-001