ND-18-1253, Unit 4 - Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.04.02.11 (Index Number 328)

Unit 4 - Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.04.02.11 (Index Number 328)

ML18275A052
Person / Time
Site:	Vogtle
Issue date:	09/28/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-1253
Download: ML18275A052 (6)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynestwro, GA 30830 Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@southemco.com SEP 2 8 2018 Docket Nos.: 52-025 52-026 ND-18-1253 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 2.3.04.02.11 (Index Number 3281 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of September 28, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.04.02.ii

[Index Number 328] has not been completed greater than 225-days priorto 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.

Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.3.04.02.11 [Index Number 328] ND-18-0725

[ML18197A086] dated July 13, 2018. This resubmittal supersedes ND-18-0725 in its entirety.

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 priorto plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

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

Respectfully submitted.

Michael J. Yox Regulatory Affairs Dijj^ctor Vogtle 3&4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 & Unit 4 Completion Plan for Uncompleted ITAAC 2.3.04.02.ii [Index Number 328]

MJY/GCW/amw

U.S. Nuclear Regulatory Commission ND-18-1253 Page 2 of 3 To:

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

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

Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Ms. A. L. Pugh Mr. A. 8. Paiion Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Ms. A. C. Chamberlain 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 Mr. P. B. Donnelly Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Eiectric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-1253 Page 3 of 3 Westlnahouse 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. Hesler, 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-18-1253 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-1253 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 & Unit 4 Completion Plan for Uncompleted ITAAC 2.3.04.02.11 [Index Number 328]

U.S. Nuclear Regulatory Commission ND-18-1253 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment

2. The FPS piping shown on Figure 2.3.4-2 remains functional following a safe shutdown earthquake.

Insoections/Tests/Analvses ii) A reconciliation analysis using the as-designed and as-built piping information will be performed, or an analysis of the as-built piping will be performed.

Acceotance Criteria ii) The as-built piping stress report exists and concludes that the piping remainsfunctional following a safe shutdown earthquake.

ITAAC Completion Description Multiple ITAAC are performed to demonstrate the Fire Protection System (FPS) piping shown on Combined License (COL) Appendix C, Figure 2.3.4-2 ("the figure") remainsfunctional following a safe shutdown earthquake (SSE). Thesubject ITAAC requires a reconciliation analysis using theas-designed and as-built piping information be performed, oran analysis of the as-built piping be performed and documented in the as-built piping stress report that concludes the piping remains functional following a SSE.

The portion ofthe FPS piping shown in the figure that is designated as "JCB" (i.e., equipment class B) is classified as Seismic Category Iand designed in accordance with American Society of Mechanical Engineers (ASME), Boiler &Pressure Vessel CodeSection III, 1998 Edition, 2000 Addenda (Reference 1). The portions of the FPS piping shown in the figure that are designated as "RCF" (i.e., equipment class F) are classified as Seismic Category II and designed in accordance with ASME B31.1,1989 Edition, 1989 Addenda (Reference 2) and are seismically analyzed consistent with ASME Section III Class 3 systems. The JCB and RCF piping is designed to remain functional following a SSE. UFSAR Table 3.9-11 provides that Service Level D conditions be applied using ASME Equation 9 and a stress limit which is less than orequal tothe smaller of3.0 allowable stress (Sh) or2.0 yield strength (Sy) (Reference 3).

This stress limit will be used in the stress analysis forthe piping represented in COL Appendix C Figure 2.3.4-2 todemonstrate the piping classified as JCB and RCF remains functional following a SSE. Additional information on the classification designations and applicable code requirements are described in Subsection 3.2.1 and Table 3.2-3 ofthe Updated Final Safety Analysis Report (UFSAR) (Reference 3).

The Unit 3 and Unit 4 ASME Section III as-built piping design reports (References 4 and 5, respectively) for the FPS piping (including valves) identified as equipment class Bin thefigure are completed and conclude that the as-built FPS piping (including valves) remains functional following a SSE.

The Unit 3 and Unit 4 ASME B31.1 as-built piping stress reports (References 8 and 9, respectively) identified as equipment classF in thefigure are completed and conclude that the as-built piping (including valves) remain functional following a SSE.

U.S. Nuclear Regulatory Commission ND-18-1253 Enclosure Page 3 of 3 The as-built piping system identified as equipment class B and class F in the figure is subjected to a reconciliation process (References 6 and 7), which verifies that the as-built piping system has been analyzed for normal operating loads, seismic loads and for compliance with the design specification. Design reconciliation of the as-built system designated as equipmentclass B and class F in the figure validates that construction completion, including field changes and any nonconforming condition dispositions, is consistent with and bounded by the approved design.

The results of the physical inspection of the piping and reconciliation are incorporated into the as-built piping stress reports.

The Unit 3 and Unit 4 as-built piping stress reports (References 8 and 9, respectively) along with the Unit 3 and Unit4 as-built FPS ASME Design Reports (References 4 and 5, respectively) exist and conclude that the FPS piping shown on COL Appendix C, Figure 2.3.4-2 remains functional following a safe shutdown earthquake.

References 4, 5,6, 7, 8 and 9, are available for NRG inspection as part of the Unit 3 and Unit4 ITAAC Completion Packages (Reference 10 and 11, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of allfindings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References favaiiabie for NRG inspection)

1. ASME Boiler and Pressure Vessel Code,Section III, "Rules for Construction of Nuclear Facility Components", 1998 Edition, 2000 Addenda

2. ASME B31.1, "Power Piping", 1989 Edition, 1989 Addenda (formally ANSI)

3. VEGP 3&4 Updated Final Safety Analysis Report,

a. Subsection 3.2.1, Seismic Classification

b. Table 3.2-3, API 000 Classification of Mechanical and Fluid Systems, Components, Equipment

c. Table 3.9-11, Piping Functional Capability Class 1, 2 and 3

4. FPS ASME As-Built Design Report (Unit 3)

5. FPS ASME As-Built Design Report (Unit 4)

6. APP-GW-GAP-139, "Westinghouse/WECTEC ASME N-5 Interface Procedure"

7. XXX As-Built Reconciliation process for Class F B31.1 Piping

8. FPS As-built piping stress report(s) (Unit 3)

9. FPS As-built piping stress report(s) (Unit 4)

10. 2.3.04.02.ii-U3-CP-Rev 0, ITAAC Completion Package 11.2.3.04.02.ii-U4-CP-Rev 0, ITAAC Completion Package

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