Letter Sequence Request |
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EPID:L-2023-LLA-0123, ITAAC Closure Verification Evaluation Form (Vef) for ITAAC Number 2.1.02.08e (Index No. 40) for Vogtle Unit 4 Combined License (VOG4) (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, ... further results|Request]]
- Acceptance
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ND-22-0711, ITAAC Closure Notification on Completion of ITAAC 3.3.00.01 (Index Number 759)2022-11-23023 November 2022
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ND-22-0964, Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.07d.ii.a (Index Number 800)2022-12-22022 December 2022
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Project stage: Request
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Project stage: Request
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Project stage: Request
ND-22-0869, ITAAC Closure Notification on Completion of Item 2.3.13.05.i (Index Number 462)2023-01-12012 January 2023
ITAAC Closure Notification on Completion of Item 2.3.13.05.i (Index Number 462)
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ND-23-0026, ITAAC Closure Notification on Completion of ITAAC 2.2.03.12a.iv (Index Number 216)2023-01-13013 January 2023
ITAAC Closure Notification on Completion of ITAAC 2.2.03.12a.iv (Index Number 216)
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ITAAC Closure Notification on Completion of ITAAC 3.3.00.02a.i.c (Index Number 762)
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ITAAC Closure Notification on Completion of ITAAC 2.1.02.12a.iv (Index Number 56)
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ITAAC Closure Notification on Completion of ITAAC 2.1.02.01 (Index Number 12)
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ITAAC Closure Notification on Completion of Item 2.2.04.12a.i (Index Number 248)
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ITAAC Closure Notification on Completion of ITAAC 2.3.02.02a (Index Number 285)
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ITAAC Closure Notification on Completion of 2.4.06.02 (Index Number 504)
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ITAAC Closure Notification on Completion of ITAAC 2.3.05.03c.ii (Index Number 350)
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ITAAC Closure Notification on Completion of ITAAC 2.3.07.07c (Index Number 408)
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ITAAC Closure Notification on Completion of ITAAC 2.3.05.03d.ii (Index Number 352)
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ITAAC Closure Notification on Completion of ITAAC Item 2.3.10.12 (Index Number 879)
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ITAAC Closure Notification on Completion of ITAAC 2.3.09.02a (Index Number 421)
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ITAAC Closure Notification on Completion of Item 2.2.05.05a.i (Index Number 259)
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ITAAC Closure Notification on Completion of ITAAC 2.3.07.05.i (Index Number 396)
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ITAAC Closure Notification on Completion of ITAAC 3.3.00.07d.i (Index Number 799)
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ITAAC Closure Notification on Completion of ITAAC 2.6.03.05d.i (Index Number 613)
Project stage: Request
2023-01-12
[Table View] |
Text
Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel January 10, 2023 Docket No.: 52-026 ND-22-0848 10 CFR 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 4 ITAAC Closure Notification on Completion of ITAAC 2.3.02.14 [Index Number 317]
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 4 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, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.02.14 [Index Number 317]
JMC/JTK/sfr
U.S. Nuclear Regulatory Commission ND-22-0848 Page 2 of 2 cc:
Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)
Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4
U.S. Nuclear Regulatory Commission ND-22-0848 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0848 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.02.14 [Index Number 317]
U.S. Nuclear Regulatory Commission ND-22-0848 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 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-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 is documented in the VEGP Unit 4 CVS Seismic Analysis Report.
Information associated with the VEGP Unit 4 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 was summarized in the Vogtle Unit 4 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-related 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 4 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-related 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 4 Chemical Volume Control System (CVS) ITAAC Requirement As-built Assessment (CVS Seismic Analysis Report) (Reference 3) exists for the CVS piping lines identified in Attachment A and is available for NRC inspection as part of the ITAAC Completion Package (Reference 4).
U.S. Nuclear Regulatory Commission ND-22-0848 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 4 (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 4 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, Rev 11.1, Section 5.2.1.1, Compliance with 10 CFR 50.55a
- 2. VEGP 3&4 Updated Final Safety Analysis Report, Rev 11.1, Section 5.2.1.3, Alternate Classification
- 3. SV4-CVS-Z0R-001, Rev. 0, Vogtle Unit 4 Chemical and Volume Control System (CVS)
ITAAC Requirement As-built Assessment (CVS Seismic Analysis Report)
- 4. 2.3.02.14-U4-CP-Rev0, ITAAC Completion Package
U.S. Nuclear Regulatory Commission ND-22-0848 Enclosure Page 4 of 4 Attachment A: *Excerpts from COL Appendix C Table 2.3.2-2 Line Name*
Line Number*
CVS Seismic Analysis Report CVS Supply Line to Regenerative Heat Exchanger L002 SV4-CVS-Z0R-001 CVS Return Line from Regenerative Heat Exchanger L018 SV4-CVS-Z0R-001 CVS Line from Regenerative Heat Exchanger to Letdown Heat Exchanger L003 SV4-CVS-Z0R-001 CVS Lines from Letdown Heat Exchanger to Demin. Tanks L004 L005 L072 SV4-CVS-Z0R-001 CVS Lines from Demin Tanks to RC Filters and Connected Lines L006(1)
L007(1)
L010(1)
L011(1)
L012 L015(1)
L016(1)
L020 L021 L022 L023(1)
L024(1)
L029 L037 SV4-CVS-Z0R-001 CVS Lines from RC Filters to Regenerative Heat Exchanger L030 L031 L034 L050 L073 SV4-CVS-Z0R-001 CVS Resin Fill Lines to Demin. Tanks L008(1)
L013(1)
L025(1)
SV4-CVS-Z0R-001 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.
