ND-22-0651, ITAAC Closure Notification on Completion of ITAAC Item 2.1.02.15 (Index Number 67)

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ITAAC Closure Notification on Completion of ITAAC Item 2.1.02.15 (Index Number 67)
ML23079A165
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 03/20/2023
From: Coleman J
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0651, ITAAC 2.1.02.15
Download: ML23079A165 (1)
v • d • e


Text

~ Southern Nuclear March 20, 2023 Docket No.:

52-026 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 &4 7825 River Road Waynesboro. GA 30830 706-848-6926 lei ND-22-0651 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 Item 2.1.02.15 [Index Number 67]

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 (1TAAC) Item 2.1.02.15 [Index Number 67]. This ITAAC confirms reactor coolant system displays can be retrieved in the main control room. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "Industry Guideline for the IT AAC 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,

~(0fi~

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP} Unit 4 Completion of IT AAC 2.1.02.15 [Index Number 67]

JMC/CWM/sfr

U.S. Nuclear Regulatory Commission ND-22-0651 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-22-0651 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0651 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC Item 2.1.02.15 [Index Number 67]

U.S. Nuclear Regulatory Commission ND-22-0651 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

15. Displays of the parameters identified in Table 2.1.2-3 can be retrieved in the MCR.

Inspections, Tests, Analyses Inspection will be performed for retrievability of the RCS parameters in the MCR.

Acceptance Criteria The displays identified in Table 2.1.2-3 can be retrieved in the MCR.

ITAAC Determination Basis An inspection was performed to verify the retrievability of the Vogtle Electric Generating Plant (VEGP) Unit 4 plant parameters in the Main Control Room (MCR). The inspection for retrievability confirmed that the displays of the parameters identified in Combined License (COL) Appendix C Table 2.1.2-3 (Attachment A) can be retrieved in the MCR.

The inspection was performed in accordance with Unit 4 ITAAC Technical Report (Reference 1) for Reactor Coolant System (RCS) component indication verifications, and visually confirmed that when each of the displays of parameters identified in Attachment A was summoned at an MCR workstation, the summoned plant parameter appeared on a display monitor at that MCR workstation.

The Unit 4 inspection results (Reference 1) confirmed that the VEGP Unit 4 plant parameter displays listed in Attachment A can be retrieved in the MCR.

Reference 1 is available for NRC inspection as part of the Unit 4 ITAAC 2.1.02.15 Completion Package (Reference 2).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.1.02.15 Unit 4 (Reference 2) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.15 was performed for VEGP Unit 4 and that the prescribed acceptance criteria are 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-22-0651 Enclosure Page 3 of 4 References (available for NRC inspection)

1. SV4-RCS-ITR-800067, Rev. 0, " Unit 4 Reactor Coolant System Parameter Indication Verification: ITAAC 2.1.02.15 Item 15 NRC Index Number: 67
2. 2.1.02.15-U4-CP-Rev0, Completion Package for Unit 4 ITAAC 2.1.02.15 [Index Number 67]

U.S. Nuclear Regulatory Commission ND-22-0651 Enclosure Page 4 of 4 Attachment A Displays of RCS Parameters in the MCR Equipment

  • Tag No.*

Display

  • RCP 1A Breaker (Status)

ECS-ES-31 Yes RCP 1A Breaker (Status)

ECS-ES-32 Yes RCP 1B Breaker (Status)

ECS-ES-41 Yes RCP 1B Breaker (Status)

ECS-ES-42 Yes RCP 2A Breaker (Status)

ECS-ES-51 Yes RCP 2A Breaker (Status)

ECS-ES-52 Yes RCP 2B Breaker (Status)

ECS-ES-61 Yes RCP 2B Breaker (Status)

ECS-ES-62 Yes Pressurizer Heaters RCS-EH-03 Yes Pressurizer Heaters RCS-EH-04A Yes Pressurizer Heaters RCS-EH-04B Yes Pressurizer Heaters RCS-EH-04C Yes Pressurizer Heaters RCS-EH-04D Yes Fourth-stage ADS Squib Valve (Position Indication)

RCS-PL-V004A Yes Fourth-stage ADS Squib Valve (Position Indication)

RCS-PL-V004B Yes Fourth-stage ADS Squib Valve (Position Indication)

RCS-PL-V004C Yes Fourth-stage ADS Squib Valve (Position Indication)

RCS-PL-V004D Yes Pressurizer Safety Valve (Position Indication)

RCS-PL-V005A Yes Pressurizer Safety Valve (Position Indication)

RCS-PL-V005B Yes Pressurizer Safety Valve (Position Indication)

RCS-PL-V110A Yes Pressurizer Safety Valve (Position Indication)

RCS-PL-V110B Yes Reactor Vessel Head Vent Valve (Position Indication)

RCS-PL-V150A Yes Reactor Vessel Head Vent Valve (Position Indication)

RCS-PL-V150B Yes Reactor Vessel Head Vent Valve (Position Indication)

RCS-PL-V150C Yes Reactor Vessel Head Vent Valve (Position Indication)

RCS-PL-V150D Yes

  • Excerpt from COL Appendix C Table 2.1.2-3
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