ND-23-0565, ITAAC Closure Notification on Completion of ITAAC Item 2.1.02.11c.ii (Index Number 52)

ITAAC Closure Notification on Completion of ITAAC Item 2.1.02.11c.ii (Index Number 52)

ML23181A182
Person / Time
Site:	Vogtle
Issue date:	06/30/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0565
Download: ML23181A182 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel June 30, 2023 Docket No.:

52-026 ND-23-0565 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 2.1.02.11c.ii [Index Number 52]

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 2.1.02.11c.ii [Index Number 52]. This ITAAC confirms that the other remotely operated valves identified in Table 2.1.2-1 as having DAS control perform the active function identified in the table after receiving a signal from DAS. 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) request 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 2.1.02.11c.ii [Index Number 52]

JMC/TJC/sfr

U.S. Nuclear Regulatory Commission ND-23-0565 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-23-0565 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-ND-23-0565 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.11c.ii [Index Number 52]

U.S. Nuclear Regulatory Commission ND-23-0565 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 11.c) The valves identified in Table 2.1.2-1 as having DAS control perform an active safety function after receiving a signal from DAS.

Inspections, Tests, Analyses ii) Testing will be performed on the other remotely operated valves identified in Table 2.1.2-1 using real or simulated signals into the DAS.

Acceptance Criteria ii) The other remotely operated valves identified in Table 2.1.2-1 as having DAS control perform the active function identified in the table after receiving a signal from DAS.

ITAAC Determination Basis Multiple ITAAC were performed to verify that the valves identified in Combined License (COL)

Appendix C Table 2.1.2-1 as having Diverse Actuation System (DAS) control perform an active safety function after receiving a signal from DAS. The subject ITAAC performed testing on each Automatic Depressurization System (ADS) stage 1, 2, and 3 motor operated valve (MOV) and ADS motor operated isolation valve.

The preoperational test was performed in accordance with Unit 4 preoperational test procedure listed in Reference 1 to confirm that the other remotely operated valves identified in Table 2.1.2-1 (Attachment A) as having DAS control perform an active safety function after receiving a signal from DAS. Testing was performed on the other remotely operated valves identified in Attachment A using simulated signals into the DAS to verify they perform the active function identified in the table after receiving a signal from DAS.

The preoperational test procedure listed in Reference 1 demonstrated that each ADS stage 1, 2, and 3 valve and ADS isolation valve received a signal from DAS and performed the active function required. The valves were tested one stage at a time and the tested valves were initially verified closed. The ADS control switches on the DAS control panel in the Main Control Room (MCR) were placed to OPEN and the valves were verified to OPEN. The valves were verified locally and in the MCR to be in the OPEN position.

The report documenting the Unit 4 preoperational test results (Reference 1), confirmed the other remotely operated valves identified in Table 2.1.2-1 as having DAS control perform the active function identified in the table after receiving a signal from DAS.

Reference 1 is available for NRC inspection as part of the ITAAC 2.1.02.11c.ii Completion Package (Reference 2).

U.S. Nuclear Regulatory Commission ND-23-0565 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 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 2.1.02.11c.ii (Reference 2) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.11c.ii 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.

SV4-RCS-ITR-800052, Rev. 0, Unit 4 Recorded Results of RCS Remotely Operated Valves Other Than Squib Control From DAS: ITAAC 2.1.02.11c.ii NRC Index Number: 52

2.

2.1.02.11c.ii-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0565 Enclosure Page 4 of 4 Attachment A

• Excerpt from COL Appendix C Table 2.1.2-1

• Tag No.

• Equipment Name

• Active Function

• Control PMS/DAS RCS-PL-V001A First-stage ADS Motor-operated Valve (MOV)

Transfer Open Yes/Yes RCS-PL-V001B First-stage ADS MOV Transfer Open Yes/Yes RCS-PL-V011A First-stage ADS Isolation MOV Transfer Open Yes/Yes RCS-PL-V011B First-stage ADS Isolation MOV Transfer Open Yes/Yes RCS-PL-V002A Second-stage ADS MOV Transfer Open Yes/Yes RCS-PL-V002B Second-stage ADS MOV Transfer Open Yes/Yes RCS-PL-V012A Second-stage ADS Isolation MOV Transfer Open Yes/Yes RCS-PL-V012B Second-stage ADS Isolation MOV Transfer Open Yes/Yes RCS-PL-V003A Third-stage ADS MOV Transfer Open Yes/Yes RCS-PL-V003B Third-stage ADS MOV Transfer Open Yes/Yes RCS-PL-V013A Third-stage ADS Isolation MOV Transfer Open Yes/Yes RCS-PL-V013B Third-stage ADS Isolation MOV Transfer Open Yes/Yes