ND-22-0149, ITAAC Closure Notification on Completion of ITAAC 2.7.01.06a (Index Number 687)

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ITAAC Closure Notification on Completion of ITAAC 2.7.01.06a (Index Number 687)
ML22059A763
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 02/28/2022
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-22-0149
Download: ML22059A763 (7)


Text

Michael J. Vox 7825 River Road Southern Nuclear Regulatory Affairs Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel FEB 2 8 2022 Docket No.: 52-025 ND-22-0149 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 3 ITAAC Closure Notification on Completion of ITAAC 2.7.01.06a [Index Number 6871 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 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.7.01.06a [Index Number 687], for verifying that the Class 1E components Identified in the Combined License (COL), Appendix C Table 2.7.1-1 are powered from their respective Class IE division. 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 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.

Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.7.01.06a [Index Number 687]

MJY/CMK/sfr

U.S. Nuclear Regulatory Commission ND-22-0149 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKlnney Mr. H. NIeh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Hasweli Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Requlatorv 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. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-22-0149 Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. OrianI Mr. D. 0. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-22-0149 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0149 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.7.01.06a [Index Number 687]

U.S. Nuclear Regulatory Commission ND-22-0149 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 6.a) The Class 1E components identified in Table 2.7.1-1 are powered from their respective Class IE division.

Inspections. Tests. Analvses Testing will be performed on the VBS by providing a simulated test signal in each Class 1E division.

Acceptance Criteria A simulated test signal exists at the Class IE equipment identified in Table 2.7.1-1 when the assigned Class 1E division is provided the test signal.

ITAAC Determination Basis Testing was performed on the Class IE components(equipment) identified in the VEGP Unit 3 COL Appendix C Table 2.7.1-1 (Attachment A)to demonstrate that they are powered from their respective Class 1E division. This ITAAC performed testing on the Nuclear Island Nonradioactive Ventilation System (VBS)and Sanitary Drainage System (SDS) equipment identified in Table 2.7.1-1 by providing a simulated test signal in each Class IE division.

Class 1E power verification testing of the Protection and Safety Monitoring System (PMS) cabinets, associated with the equipment identified in Attachment A, was verified through the applicable portion of ITAAC 2.5.02.05a testing (Reference 1) and confirms the PMS cabinets are powered from their respective Class IE division. SV3-VBS-ITR 800687(Reference 2) documents completion of power verification activities from the PMS cabinets and the Class 1E motor control centers to the equipment identified in Attachment A. Reference 2 first verified that power supply cables/wiring were installed and terminated from the applicable PMS cabinet and Class 1E motor control center to the respective equipment identified in Attachment A using approved construction drawings and cable/wiring termination documentation. Reference 2 then confirmed, via cable/wiring termination inspection documentation, that continuity testing was performed on each of the installed cables/wiring to confirm current flow within the installed cable/wiring. The combination of cable/wiring installation and termination verification, with the installed cable/wiring continuity testing, confirmed that the equipment identified in Appendix A are powered from their respective Class 1E division.

The results of the testing are documented in SV3-VBS-ITR 800687(Reference 2)and confirmed that a simulated test signal exists at the Class 1E components identified in Table 2.7.1-1 when the assigned Class 1E division provided the test signal.

References 1 and 2 are available for NRC inspection as part of the Unit 3 ITAAC 2.7.01.06a Completion Package (Reference 3).

U.S. Nuclear Regulatory Commission ND-22-0149 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 all 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 Vogtle Unit 3 ITAAC Completion Package for ITAAC 2.7.01.06a (Reference 3)and is available for NRC inspection.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.7.01.06a 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-PMS-ITR-800527-1 Rev. 0,"Unit 3 Protection & Safety Monitoring (PMS)System Equipment by Assigned Class 1E Division"
2. SV3-VBS-ITR-800687 Rev. 0,"Unit 3 Nuclear Island Nonradioactive Ventilation System (VBS) Class 1E Equipment Signaled From Assigned Division"
3. 2.7.01.06a-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0149 Enclosure Page 4 of 4 Attachment A COL Appendix C Table 2.7.1-1 Equipment Name* Tag No.*

MCR Supply Air Isolation Valve VBS-PL-V186 MCR Supply Air Isolation Valve VBS-PL-V187 MCR Return Air Isolation Valve VBS-PL-V188 MCR Return Air Isolation Valve VBS-PL-V189 MCR Exhaust Air Isolation Valve VBS-PL-V190 MCR Exhaust Air Isolation Valve VBS-PL-V191 MCR SDS (Vent) Isolation Valve SDS-PL-V001 MCR SDS (Vent) Isolation Valve SDS-PL-V002 Excerpted from COL Appendix C Table 2.7.1-1