ND-22-0146, ITAAC Closure Notification on Completion of ITAAC 2.3.13.06b (Index Number 467)

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ITAAC Closure Notification on Completion of ITAAC 2.3.13.06b (Index Number 467)
ML22059A960
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-22-0146
Download: ML22059A960 (7)


Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tei FEB 2 8 2022 Docket No.: 52-025 ND-22-0146 10CFR 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 2.3.13.06b [Index Number 4671 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 2.3.13.06b [Index 467]. This ITAAC confirms that the Containment Air Sample and Containment Liquid Sample Containment Isolation Valves are powered from their respective Class 1E 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. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.13.06b [Index Number 467]

MJY/GCS/sfr

U.S. Nuclear Regulatory Commission ND-22-0146 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney 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. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Reoulatorv 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-22-0146 Page 3 of 3 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utiiities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani Mr. D. C. 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., GDS 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-22-0146 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0146 Enclosure Vogtle Electric Generating Piant(VEGP) Unit 3 Completion of ITAAC 2.3.13.06b [Index Number 467]

U.S. Nuclear Regulatory Commission ND-22-0146 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 6.b) The Class 1E components identified in Table 2.3.13-1 are powered from their respective Class IE division.

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

Acceptance Criteria A simulated test signal exists at the Class 1E equipment identified in Table 2.3.13-1 when the assigned Class 1 Edivision is provided the test signal.

ITAAC Determination Basis Testing was performed on the Class IE components identified in the VEGP Unit 3 COL Appendix C Table 2.3.13-1 (Attachment A)to demonstrate that the components were powered from their respective Class 1E division. This ITAAC performed testing on the Primary Sampling System (PSS)components identified in Table 2.3.13-1 by providing a simulated test signal in each Class 1E division.

Class 1E power verification testing of the Protection and Safety Monitoring System (PMS) cabinets, associated with the equipment identified in Attachment A, is verified through the applicable portions of ITAAC 2.5.02.05a testing (Reference 1) and confirms the PMS cabinets are powered from their respective Class IE division. SV3-PSS-ITR-800467(Reference 2) documents completion of power verification activities from the respective PMS cabinets to the components identified in Attachment A. Reference 2 first verified that power supply cables/wiring was installed and terminated from the applicable PMS cabinet to the respective components 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 components identified in Appendix A are powered from their respective Class IE division.

The results of the testing are documented in SV3-PSS-ITR-800467(Reference 2)and confirmed that a simulated test signal exists at the Class 1E components identified in Table 2.3.13-1 when the assigned Class IE division provided the test signal.

References 1 and 2 are available for NRC inspection as part of the Unit 3 ITAAC 2.3.13.06b Completion Package (Reference 3).

U.S. Nuclear Regulatory Commission ND-22-0146 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 2.3.13.06b (Reference 3) and Is available for NRC Inspection.

ITAAC Completion Statement Based on the above Information, SNC hereby notifies the NRC that ITAAC 2.3.13.06b 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 IE Division: ITAAC 2.5.02.05a"
2. SV3-PSS-ITR-800467 rev 0 "Unit 3 Primary Sampling System (PSS) Class IE Equipment Signaled: ITAAC 2.3.13.06b"
3. 2.3.13.06b-U3-CP-Rev 0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0146 Enclosure Page 4 of 4 Attachment A COL Appendix C Table 2.3.13-1 Equipment Name* Tag No.*

Containment Air Sample Containment Isolation PSS-PL-V008 Valve Inside Reactor Containment(IRC)

Liquid Sampie Line Containment Isolation PSS-PL-V010A Valve IRC Liquid Sample Line Containment Isolation PSS-PL-V010B Valve IRC Liquid Sample Line Containment Isolation PSS-PL-V011A Valve Outside Reactor Containment(ORC)

Liquid Sample Line Containment Isolation PSS-PL-V011B Valve ORC Sample Return Line Containment Isolation PSS-PL-V023 Valve ORC Sample Return Containment Isolation PSS-PL-V024 Valve IRC Air Sample Line Containment Isolation PSS-PL-V046 Valve ORC Excerpted from COL Appendix C Table 2.3.13-1