ND-23-0358, ITAAC Closure Notification on Completion of ITAAC 3.1.00.03 (Index Number 735)

ITAAC Closure Notification on Completion of ITAAC 3.1.00.03 (Index Number 735)

ML23164A213
Person / Time
Site:	Vogtle
Issue date:	06/13/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0358
Download: ML23164A213 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel June 13, 2023 Docket No.: 52-026 ND-23-0358 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 3.1.00.03 [Index Number 735]

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 3.1.00.03 [Index Number 735].

This ITAAC confirms that selected plant parameters listed in COL Appendix C, Table 2.5.4-1, can be retrieved in the Technical Support Center. The closure process for this ITAAC is 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 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 3.1.00.03 [Index Number 735]

JMC/SRV/sfr

U.S. Nuclear Regulatory Commission ND-23-0358 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-23-0358 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-23-0358 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 3.1.00.03 [Index Number 735]

U.S. Nuclear Regulatory Commission ND-23-0358 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

3. The plant parameters listed in Table 2.5.4-1, minimum inventory table, in subsection 2.5.4, DDS, with a "Yes" in the "Display" column, can be retrieved in the TSC.

Inspections/Tests/Analyses An inspection will be performed for retrievability of the plant parameters in the TSC.

Acceptance Criteria The plant parameters listed in Table 2.5.4-1, minimum inventory table, in subsection 2.5.4, DDS, with a "Yes" in the "Display" column, can be retrieved in the TSC.

ITAAC Determination Basis An inspection was performed to verify the retrievability of the VEGP Unit 4 plant parameters in the Technical Support Center (TSC). The inspection for retrievability confirmed that the plant parameters listed in COL Appendix C Table 2.5.4-1, Minimum Inventory of Controls, Displays, and Alerts at the RSW, with a "Yes" in the "Display" column (Attachment A) can be retrieved in the TSC.

The inspection was performed as described in ITAAC Technical Report SV4-ERO-ITR-800735 (Reference 1), and visually confirmed that when each of the plant parameters identified in Attachment A was summoned at a workstation connected to the TSC Local Area Network (Enterprise Data System) the summoned plant parameter appeared on a display monitor at that TSC workstation.

The inspection results are documented in Reference 1 and confirmed that the VEGP Unit 4 plant parameters listed in Attachment A can be retrieved in the TSC.

Reference 1 is available for NRC Inspection as part of the Unit 4 ITAAC 3.1.00.03 Completion Package (Reference 2).

ITAAC Finding Review 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 were no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.1.00.03 (Reference 2) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.1.00.03 was performed for VEGP Unit 4 and that the prescribed acceptance criteria was 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.

U.S. Nuclear Regulatory Commission ND-23-0358 Enclosure Page 3 of 4 References (available for NRC inspection)

1. SV4-ERO-ITR-800735, Unit 4 ITAAC 735 Displays: ITAAC 3.1.00.03, Rev 0

2. 3.1.00.03-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0358 Enclosure Page 4 of 4 Attachment A Minimum Inventory of Controls, Displays, and Alerts at the RSW*

Description

• Display

• Neutron Flux Yes Startup Rate Yes Reactor Coolant System (RCS) Pressure Yes Wide-range Hot Leg Temperature Yes Wide-range Cold Leg Temperature Yes RCS Cooldown Rate Compared to the Limit Based on RCS Pressure Yes Wide-range Cold Leg Temperature Compared to the Limit Based on Yes RCS Pressure Containment Water Level Yes Containment Pressure Yes Pressurizer Water Level Yes Pressurizer Water Level Trend Yes Pressurizer Reference Leg Temperature Yes Reactor Vessel-Hot Leg Water Level Yes Pressurizer Pressure Yes Core Exit Temperature Yes RCS Subcooling Yes RCS Cold Overpressure Limit Yes In-containment Refueling Water Storage Tank (IRWST) Water Level Yes Passive Residual Heat Removal (PRHR) Flow Yes PRHR HX Outlet Temperature Yes PRHR HX Inlet Isolation and Control Valve Status Yes Passive Containment Cooling System (PCS) Storage Tank Water Yes Level PCS Cooling Flow Yes IRWST to Normal Residual Heat Removal System (RNS) Suction Yes Valve Status Remotely Operated Containment Isolation Valve Status Yes Containment Area High-range Radiation Level Yes Containment Pressure (Extended Range) Yes Core Makeup Tank (CMT) Level Yes

• Excerpt from COL Table 2.5.4-1