Text

ITAAC Closure Notification on Completion of ITAAC 2.2.01 .11 B (Index Number 118)
	ML21225A311
Person / Time
Site:	Vogtle
Issue date:	08/13/2021
From:	Yox M; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ND-21-0745
	Download: ML21225A311 (8)
	v • d • e

Southern Nuclear All 132811 Docket No.:

52-025 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 7825 River Road Waynesboro, GA 30830 706-848-6459 tel ND-21-0745 10 CFR 52.99(c)(1)

ITAAC Closure Notification on Completion of ITAAC 2.2.01.11 b [Index Number 118]

Ladies and Gentlemen:

In accordance with 1 O 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 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.11 b [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 1 O CFR 52.99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted, Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

MJY/DLW/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.01.11 b [Index Number 118]

U.S. Nuclear Regulatory Commission ND-21-0745 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. E. Davidson Mr. T. Fanelli Ms. K. Mccurry Mr. J. Parent Mr. B. Griman

U.S. Nuclear Regulatory Commission ND-21-0745 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Mr. J. L. Coward Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GOS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0745 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-21-0745 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.01.11 b [Index Number 118]

U.S. Nuclear Regulatory Commission ND-21-0745 Enclosure Page 2 of 5 IT AAC 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.

IT AAC 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 and in the MCR, 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 and in the Main Control Room (MCR). References 2 through 4 verified each Motor Operated Valve (MOV) locally and in the MCR 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 and in the MCR. 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 and in the MCR. The results of the testing were documented in ITAAC Technical Reports (References 1 through 6).

References 1 through 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 well as the Unit 3 ITAAC 2.2.01.11 b Completion Package (Reference 7).

U.S. Nuclear Regulatory Commission ND-21-0745 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.

IT AAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.11 b was performed for VEGP Unit 3 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. SV3-CNS-ITR-800118, Rev. 0, "Unit 3 Test Results for CAS Containment Isolation Valve -