ND-19-1353, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.14 (Index Number 317)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.14 (Index Number 317)

ML19310F953
Person / Time
Site:	Vogtle
Issue date:	11/06/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1353
Download: ML19310F953 (7)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel NOV 0 6 2019 Docket No.: 52-025 52-026 ND-19-1353 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 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.02.14 [Index Number 3171 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of November 4, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.2.14 [Index Number 317] 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.

Southern Nuclear Operating Company(SNC) previously submitted Notices of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.3.02.14 [Index Number 317], ND-16-1851,

[ML16272A309], dated September 28, 2016 and ND-19-1242,[ML19291A369], dated October 17, 2019. This resubmittal supersedes both letter numbers ND-16-1851 and ND-19-1242 in their 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)(3) ITAAC Closure Notifications will be submitted to the NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

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

Respectfully submitted.

Michael J. Yox Regulatory Affairs rector Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.14 [Index Number 317]

MJY/GCW/sfr

U.S. Nuclear Regulatory Commission ND-19-1353 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKlnney (w/o enclosures)

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

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

Mr. G. Chick Mr. M. Page Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1353 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. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward 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. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-1353 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-1353 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.14[Index Number 317]

U.S. Nuclear Regulatory Commission ND-19-1353 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

14. The nonsafety-related piping located inside containment and designated as reactor coolant pressure boundary, as identified in Table 2.3.2-2, has been designed to withstand a seismic design basis event and maintain structural integrity.

Inspections. Tests. Analyses Inspection will be conducted of the as-built piping as documented in the CVS Seismic Analysis Report.

Acceptance Criteria The CVS Seismic Analysis Reports exist for the nonsafety related piping located inside containment and designated as reactor coolant pressure boundary as identified in Table 2.3.2-2.

ITAAC Completion Description An inspection is conducted to verify that the nonsafety-related Chemical and Volume Control System (CVS) piping located inside containment and designated as reactor coolant pressure boundary, as identified in VEGP Combined License (COL)Appendix C Table 2.3.2-2 (Attachment A), has been designed to withstand a seismic design basis event and maintain structural integrity. The inspection confirms that a seismic analysis for the as-built piping identified in Attachment A are documented in the VEGP Unit 3 and Unit 4 CVS Seismic Analysis Reports. Information associated with the VEGP CVS Seismic Analysis Report is discussed in VEGP 3&4 Updated Final Safety Analysis Report(UFSAR) Section 5.2.1.1,"Compliance with 10 CFR 50.55a",(Reference 1) and supplemented by UFSAR Section 5.2.1.3, "Alternate Classification",(Reference 2).

The design of the nonsafety-related (American Society of Mechanical Engineers(ASME) B31.1 Piping Class D)CVS piping identified in Attachment A is summarized in the CVS Structural Integrity Piping Design Report(s) XXX (References 3 and 4). Inspections are performed following installation of the piping identified in Attachment A to confirm that the as-built piping is installed per design report specifications. Inspection non-conformances are documented and dispositioned to ensure the nonsafety-related as-built CVS piping identified in Attachment A is designed and constructed to withstand a seismic design basis event and maintain structural integrity. CVS Seismic Analysis Report(s)(References 5 and 6) documents the seismic analysis for the as-built piping in Attachment A using the criteria in Reference 1 and confirms that the nonsafety-related as-built CVS piping located inside containment and designated as reactor coolant pressure boundary is designed to withstand a seismic design basis event and maintain structural integrity.

The CVS Seismic Analysis Reports for the CVS piping lines identified in Attachment A for Unit 3 and Unit 4 are available for NRC inspection as part of the ITAAC Completion Packages (References 7 and 8).

U.S. Nuclear Regulatory Commission ND-19-1353 Enclosure Page 3 of 4 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company(SNC) performed a review of all findings 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 NRC inspection)

1. VEGP 3&4 Updated Final Safety Analysis Report, Section 5.2.1.1, Compliance with 10 CFR 50.55a

2. VEGP 3&4 Updated Final Safety Analysis Report, Section 5.2.1.3, Alternate Classification

3. Unit 3 CVS Structural Integrity Piping Design Report XXX

4. Unit 4 CVS Structural Integrity Piping Design Report XXX

5. Unit 3 CVS Seismic Analysis Reports identified in Attachment A

6. Unit 4 CVS Seismic Analysis Reports identified in Attachment A

7. ITAAC 2.3.02.14-U3-CP-RevO "ITAAC Completion Package"

8. ITAAC 2.3.02.14-U4-CP-RevO "ITAAC Completion Package"

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

U.S. Nuclear Regulatory Commission ND-19-1353 Enclosure Page 4 of 4 Attachment A: Excerpt from COL Appendix 0 Table 2.3.2-2 CVS Seismic Line Name Line Number Analysis Report CVS Supply Line to Regenerative Heat L002 ZZZ Exchanger L018 CVS Return Line from Regenerative Heat ZZZ Exchanger CVS Line from Regenerative Heat L003 ZZZ Exchanger to Letdown Heat Exchanger CVS Lines from Letdown Heat Exchanger L004 ZZZ to Demin. Tanks LOOS L072 CVS Lines from Demin Tanks to RC Filters L006(1) ZZZ and Connected Lines L007<^)

LOIO'^'

LOII(^)

L012 LOIS'^)

L016(^'

L020 L021 L022 L023(i' L024(^)

L029 L037 CVS Lines from RC Filters to Regenerative L030 777 Heat Exchanger L031 L034 L050 L073 CVS Resin Fill Lines to Demin. Tanks L008<1> 7ZL L013<1>

L025(1)

Note:

1. Special seismic requirements include only the portion of piping normally exposed to RCS pressure. Piping beyond the first normally closed isolation valve is evaluated as seismic Category II piping extending to either an interface anchor, a rigid support following a six-way anchor, or the last seismic support of a rigidly supported region of the piping system as necessary to satisfy analysis requirements for piping connected to seismic Category I piping systems.