ND-21-0227, ITAAC Closure Notification on Completion of ITAAC 2.3.02.14 (Index Number 3171)

ITAAC Closure Notification on Completion of ITAAC 2.3.02.14 (Index Number 3171)

ML21148A200
Person / Time
Site:	Vogtle
Issue date:	05/28/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.3.02.14, ND-21-0227
Download: ML21148A200 (7)

Text

Michael d. Vox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel MAY 2 8 2021 Docket No.: 52-025 ND-21-0227 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.02.14 [Index Number 3171 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant(VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.02.14 [Index Number 317].

This ITAAC verifies that the Chemical and Volume Control System (CVS) 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. The closure process for this ITAAC was based on the guidance described in Nuclear Energy Institute (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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli A. Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Vox y Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

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

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-21-0227 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil M C. P. Patel M G. J. Khouri M C. J. Even M B. J. Kemker Ms. N. C. Coovert M C. Welch M J. Gaslevic M . O. Lopez-Santiago M G. Armstrong M M. Webb M T. Fredette M C. Santos M B. Davis M . J. Vasquez M J. Eargle M E. Davidson M . T. Fanelli Ms. K. McCurry M J. Parent M B. Griman

U.S. Nuclear Regulatory Commission ND-21-0227 Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Orlani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, 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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-0227 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-21-0227 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.02.14[Index Number 317]

U.S. Nuclear Regulatory Commission ND-21-0227 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

14. The nonsafety-reiated 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. Anaivses 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 non-safety related piping located inside containment and designated as reactor coolant pressure boundary as identified in Table 2.3.2-2.

ITAAC Determination Basis An inspection was conducted to verify that the nonsafety-reiated 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 is documented in the VEGP Unit 3 CVS Seismic Analysis Report.

Information associated with the VEGP Unit 3 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-reiated (American Society of Mechanical Engineers(ASME) B31.1 Piping Class D)CVS piping identified in Attachment A was summarized in the Vogtle Unit 3 Chemical Volume Control System (CVS)ITAAC Requirement As-built Assessment(CVS Seismic Analysis Report)(Reference 3). Inspections were performed following installation of the piping identified in Attachment A to confirm that the as-built piping was installed per design report specifications. Inspection non-conformances are documented and dispositioned to ensure the nonsafety-reiated as-built CVS piping identified in Attachment A was designed and constructed to withstand a seismic design basis event and maintain structural integrity. Vogtle Unit 3 Chemical Volume Control System (CVS)ITAAC Requirement As-built Assessment(CVS Seismic Analysis Report)(Reference 3) documents the seismic analysis for the as-built piping in Attachment A using the criteria in Reference 1 and confirms that the nonsafety-reiated as-built CVS piping located inside containment and designated as reactor coolant pressure boundary was designed to withstand a seismic design basis event and maintain structural integrity.

The Vogtle Unit 3 Chemical Volume Control System (CVS)ITAAC Requirement As-built Assessment(CVS Seismic Analysis Report)(Reference 3)for the CVS piping lines identified in Attachment A for Unit 3 are available for NRC inspection as part of the ITAAC Completion Package (Reference 4).

U.S. Nuclear Regulatory Commission ND-21-0227 Enclosure Page 3 of 4 ITAAC Finding Review 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 no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.02.14 for Unit 3(Reference 4)and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.02.14 was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

Systems,structures, and components verified as part of this ITAAC are being maintained in their as designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References(available 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. SV3-CVS-Z0R-001, Rev. 1,"Vogtle Unit 3 Chemical and Volume Control System (CVS)

ITAAC Requirement As-built Assessment(CVS Seismic Analysis Report)"

4. 2.3.02.14-U3-CP-RevO, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-21-0227 Enclosure Page 4 of 4 Line CVS Seismic Anaiysis Line Name* Number* Report CVS Supply Line to Regenerative Heat L002 SV3-CVS-Z0R-001 Exchanger CVS Return Line from Regenerative L018 SV3-CVS-Z0R-001 Heat Exchanger CVS Line from Regenerative Heat L003 SV3-CVS-Z0R-001 Exchanger to Letdown Heat Exchanger CVS Lines from Letdown Heat L004 SV3-CVS-Z0R-001 Exchanger to Demin. Tanks LOOS L072 CVS Lines from Demin Tanks to RC L006'i> SV3-CVS-Z0R-001 Filters and Connected Lines L007<1)

L010<1' L011<1)

L012 L015(i)

L016(i>

L020 L021 L022 L023(i)

L024<1>

L029 L037 CVS Lines from RC Filters to L030 SV3-CVS-Z0R-001 Regenerative Heat Exchanger L031 L034 L050 L073 CVS Resin Fill Lines to Demin. Tanks LOOS'i) SV3-CVS-Z0R-001 L013(^)

L025(^'

Note:

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.