ND-18-0725, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.04.02.ii (Index Number 328)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.04.02.ii (Index Number 328)

ML18197A086
Person / Time
Site:	Vogtle
Issue date:	07/13/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0725
Download: ML18197A086 (6)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director WaynestJoro, GA 30830

^ Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@southernco.com JUL 1 3 2018 Docket Nos.: 52-025 52-026 ND-18-0725 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.ii [Index Number 3281 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as ofJuly 11, 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 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 Director 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/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0725 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (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 Ms. A. L. Pugh Mr. A. 8. Parton 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 Oolethoroe Power Corporation Mr. R. B. Brinkman Municioal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-0725 Page 3 of 3 Westinahouse 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. Deangells Other Mr. J. E. Hesler, 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0725 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0725 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-18-0725 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.

Inspectlons/Tests/Analvses II) A reconciliation analysis using the as-designed and as-bullt piping Information will be performed, or an analysis of the as-bullt piping will be performed.

Acceptance Criteria II) The as-bullt pipingstress report exists and concludes that the piping remains functional 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") remains functional following a safe shutdown earthquake (SSE). The subject ITAAC requires a reconciliation analysis using the as-designed and as-bullt piping Information be performed, or an analysis of the as-bullt piping be performed and documented In the as-bullt piping stress report that concludes the piping remains functional following a SSE.

The portion of the FPS piping shown In the figure that Is designated as "JCB" (I.e., equipment class B) Is classified as Seismic Category I and designed In accordance with American Society of Mechanical Engineers (ASME), Boiler &Pressure Vessel Code Section 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 (Reference2) and are selsmlcally analyzed consistent with ASME Section III Class 3 systems. Additional Information on the classification designations and applicable code requirements are described In Subsection 3.2.1 and Table 3.2-3 of the Updated Final Safety Analysis Report (UFSAR) (Reference 3).

The Unit 3 and Unit4 ASME Section III as-bullt piping design reports (References 4 and 5, respectively) for the FPS piping (Including valves) Identified as equipment class B In the figure are completed and conclude that the as-bullt FPS piping (Including valves) remains functional following a SSE.

The Unit 3 and Unit 4 ASME B31.1 as-bullt piping stress reports (References 8 and 9, respectively) Identified as equipmentclass F In the figure are completed and conclude that the as-bullt piping (Including valves) remain functional following a SSE. Specificfunctional requirements for FPS piping Identified as equipmentclass F In the figure are defined In Subsection 3.7.3.13.4.2 of the UFSAR (Reference 3).

The as-bullt 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-bullt piping system has been analyzed for normal operating loads, seismic loads and for compliance with the design

U.S. Nuclear Regulatory Commission ND-18-0725 Enclosure Page 3 of 3 specification. Design reconciliation of tfie as-built system designated as equipmentclass B and class F in tfie 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 intothe 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 Unit 4 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 NRC inspection as part of the Unit 3 and Unit 4 ITAAC Completion Packages (Reference 10 and 11, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southem NuclearOperating Company (SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings associated with this ITAAC.

References favailable for NRC 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. Subsection 3.7.3.13.4.2, Seismic Category II Piping

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

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

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

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

8. FPS As-built piping stress report(s) (Unit3)

9. FPS As-built piping stress report(s) (Unit 4) 10.2.3.04.02.ii-U3-CP-Rev0, ITAAC Completion Package 11.2.3.04.02.ii-U4-CP-Rev0, ITAAC Completion Package

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