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ITAAC Closure Notification on Completion of ITAAC 2.2.01.11b (Index Number 118)
	ML23088A200
Person / Time
Site:	Vogtle
Issue date:	03/29/2023
From:	Coleman J; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	ND-23-0239, ITAAC 2.2.01.11b
	Download: ML23088A200 (1)
	v • d • e

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel March 29, 2023 Docket No.: 52-026 ND-23-0239 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 2.2.01.11b [Index Number 118]

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 2.2.01.11b [Index Number 118], for verifying each remotely operated valve in Table 2.2.1-1 assumes the indicated loss of motive power position. The closure process for this ITAAC is based on the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52, which is 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 2.2.01.11b [Index Number 118]

JMC/MKO/sfr

U.S. Nuclear Regulatory Commission ND-23-0239 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-23-0239 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-23-0239 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.01.11b [Index Number 118]

U.S. Nuclear Regulatory Commission ND-23-0239 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 11.b) After loss of motive power, the remotely operated valves identified in Table 2.2.1-1 assume the indicated loss of motive power position.

Inspections/Tests/Analyses Testing of the remotely operated valves will be performed under the conditions of loss of motive power.

Acceptance Criteria After loss of motive power, each remotely operated valve identified in Table 2.2.1-1 assumes the indicated loss of motive power position.

ITAAC Determination Basis Testing was performed under the conditions of loss of motive power to verify the remotely operated valves identified in Table 2.2.1-1 of the Combined License (COL) Appendix C, (Attachment A), assume the indicated loss of motive power position. The testing verified that the valves in Attachment A assume the indicated loss of motive power position.

The testing was performed as listed in References 1 through 6 for the Containment System (CNS) valves identified in Attachment A under the conditions of loss of motive power. The air-operated valves (AOVs) were placed into the open position, verified to be open locally then power was removed from the solenoid valve supplying air to the valve actuator which removed motive power to the valve. The valve position of each of the valves was verified to Close locally.

References 2 through 4 verified each Motor Operated Valve (MOV) locally to be in the Open position. Each MOV was stroked Closed by using the valve control circuit to deenergize the contactors, which removed motive power from the valve when the Closed position was reached.

This loss of power caused by valve control circuit demonstrated that each MOV failed "As-ls" (Closed) when motive power was removed. Actual valve position was verified locally. Each MOV was also stroked Open by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the Open position was reached. This loss of power caused by the valve control circuit demonstrated that each MOV failed "As-ls" (Open) when motive power was removed. Actual valve position was verified locally. The results of the testing were documented in ITAAC Technical Reports (References 1 through 6).

The completed Unit 4 test results (References 1-6) confirm that each remotely operated Containment isolation valve identified in Attachment A assumed the indicated loss of motive power position.

References 1 through 6 are available for NRC inspection as part of the Unit 4 ITAAC 2.2.01.11b Completion Package (Reference 7).

U.S. Nuclear Regulatory Commission ND-23-0239 Enclosure Page 3 of 5 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 2.2.01.11b (Reference 7) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.11b 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-CNS-ITR-800118 Rev. 0, Unit 4 Test Results for CAS Containment Isolation Valve -