ND-19-0508, Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.3.09.02b (Index Number 422)

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Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.3.09.02b (Index Number 422)
ML19200A261
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/19/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-19-0508
Download: ML19200A261 (10)


Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tel JUL 1 9 2019 Docket Nos.: 52-025 52-026 ND-19-0508 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.09.02b (Index Number 4221 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 17, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.09.02b [Index Number 422] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.

All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.09.02b [Index Number 422]

MJY/RLB/sfr

U.S. Nuclear Regulatory Commission ND-19-0508 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. R.G. West(w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

Mr. M. D. Meier(w/o enclosures)

Mr. D. H. Jones(w/o enclosures)

Mr. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reaulatorv Commission Mr. W.Jones(w/o enclosures)

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Qqiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0508 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric ComDanv. LLC Dr. L. OrlanI (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hosier, 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 Ms. 8. W. Kemlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-19-0508 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-19-0508 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.09.02b [Index Number 422]

U.S. Nuclear Regulatory Commission ND-19-0508 Enclosure Page 2 of 7 ITAAC Statement Design Commitment 2.b) The components identified in Table 2.3.9-2 are powered from their respective non-Class 1E power group.

I nsoections/Tests/Analvses Testing will be performed by providing a simulated test signal in each non-Class 1E power group.

Acceotance Criteria A simulated test signal exists at the equipment identified in Table 2.3.9-2 when the assigned non-Class 1E power group is provided the test signal.

ITAAC Completlon Description Testing is performed on the components(equipment) identified in the VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.9-2(Attachment A)to demonstrate they are powered from their respective non-Class 1E power group. This ITAAC performs testing on the equipment identified in Attachment A by providing a simulated test signal in each non-Class 1E power group.

Unit 3 and Unit 4 component test package work orders SNC922137 and SNCXXXXXX (References 1 and 2, respectively) document completion of power verification activities for the equipment identified in Attachment A. References 1 and 2 first verify that power supply cables/wiring are installed and terminated from the applicable non-Class 1E power group distribution panels to the equipment identified in Attachment A using approved construction drawings and cable/wiring termination documentation. References 1 and 2 then confirm, via cable/wiring termination inspection documentation, that continuity testing is 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, confirms that the equipment identified in Appendix A is powered from its respective non-Class 1E power group.

The Unit 3 and Unit 4 component test package work orders(References 1 and 2, respectively) confirm that a simulated test signal exists at the equipment identified in Table 2.3.9-2 when the assigned non-Class 1E power group is provided the test signal.

References 1 and 2 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC Completion Packages(References 3 and 4).

List of ITAAC Findings 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.

U.S. Nuclear Regulatory Commission ND-19-0508 Enclosure Page 3 of 7 References favailable for NRG inspection)

1. SNC922137,"VLB Component Power Verification Test- ITAAC: SV3-2.3.09.02a and 2.3.09.2b"
2. SNCXXXXXX,"VLB Component Power Verification Test- ITAAC: BV4-2.3.09.02a and 2.3.09.2b"
3. 2.3.09.02b-U3-CP-Rev 0, ITAAC Completion Package
4. 2.3.09.02b-U4-CP-Rev 0, ITAAC Completion Package
5. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-0508 Enclosure Page 4 of 7 Attachment A COL Appendix C Table 2.3.9-2 Equipment Name* Tag Number* Power Group Number*

Hydrogen Igniter 01 VLS-EH-01 1 Hydrogen Igniter 02 VLS-EH-02 2 Hydrogen Igniter 03 VLS-EH-03 1 Hydrogen Igniter 04 VLS-EH-04 2 Hydrogen Igniter 05 VLS-EH-05 1 Hydrogen Igniter 06 VLS-EH-06 2 Hydrogen Igniter 07 VLS-EH-07 2 Hydrogen Igniter 08 VLS-EH-08 1 Hydrogen Igniter 09 VLS-EH-09 1 Hydrogen Igniter 10 VLS-EH-10 2 Hydrogen Igniter 11 VLS-EH-11 2 Hydrogen Igniter 12 VLS-EH-12 1 Hydrogen Igniter 13 VLS-EH-13 1 Hydrogen Igniter 14 VLS-EH-14 2 Hydrogen Igniter 15 VLS-EH-15 2 Hydrogen Igniter 16 VLS-EH-16 1 Hydrogen Igniter 17 VLS-EH-17 2 Hydrogen Igniter 18 VLS-EH-18 1

U.S. Nuclear Regulatory Commission ND-19-0508 Enclosure Page 5 of 7 Hydrogen Igniter 19 VLS-EH-19 2 Hydrogen Igniter 20 VLS-EH-20 2 Hydrogen Igniter 21 VLS-EH-21 1 Hydrogen Igniter 22 VLS-EH-22 1 Hydrogen Igniter 23 VLS-EH-23 2 Hydrogen Igniter 24 VLS-EH-24 2 Hydrogen Igniter 25 VLS-EH-25 2 Hydrogen Igniter 26 VLS-EH-26 2 Hydrogen Igniter 27 VLS-EH-27 1 Hydrogen Igniter 28 VLS-EH-28 1 Hydrogen Igniter 29 VLS-EH-29 1 Hydrogen Igniter 30 VLS-EH-30 2 Hydrogen Igniter 31 VLS-EH-31 1 Hydrogen Igniter 32 VLS-EH-32 1 Hydrogen Igniter 33 VLS-EH-33 2 Hydrogen Igniter 34 VLS-EH-34 1 Hydrogen Igniter 35 VLS-EH-35 1 Hydrogen Igniter 36 VLS-EH-36 2 Hydrogen Igniter 37 VLS-EH-37 1 Hydrogen Igniter 38 VLS-EH-38 2 Hydrogen Igniter 39 VLS-EH-39 1

U.S. Nuclear Regulatory Commission ND-19-0508 Enclosure Page 6 of 7 Hydrogen Igniter 40 VLS-EH-40 2 Hydrogen Igniter 41 VLS-EH-41 2 Hydrogen Igniter 42 VLS-EH-42 1 Hydrogen Igniter 43 VLS-EH-43 1 Hydrogen Igniter 44 VLS-EH-44 1 Hydrogen Igniter 45 VLS-EH-45 2 Hydrogen Igniter 46 VLS-EH-46 2 Hydrogen Igniter 47 VLS-EH-47 1 Hydrogen Igniter 48 VLS-EH-48 2 Hydrogen Igniter 49 VLS-EH-49 1 Hydrogen Igniter 50 VLS-EH-50 2 Hydrogen Igniter 51 VLS-EH-51 1 Hydrogen Igniter 52 VLS-EH-52 2 Hydrogen Igniter 53 VLS-EH-53 2 Hydrogen Igniter 54 VLS-EH-54 1 Hydrogen Igniter 55 VLS-EH-55 1 Hydrogen Igniter 56 VLS-EH-56 2 Hydrogen Igniter 57 VLS-EH-57 2 Hydrogen Igniter 58 VLS-EH-58 1 Hydrogen Igniter 59 VLS-EH-59 2 Hydrogen Igniter 60 VLS-EH-60 1

U.S. Nuclear Regulatory Commission ND-19-0508 Enclosure Page 7 of 7 Hydrogen Igniter 61 VLS-EH-61 1 Hydrogen Igniter 62 VLS-EH-62 2 Hydrogen Igniter 63 VLS-EH-63 1 Hydrogen Igniter 64 VLS-EH-64 2 Hydrogen Igniter 65 VLS-EH-65 1 Hydrogen Igniter 66 VLS-EH-66 2 Excerpted from COL Appendix C Table 2.3.9-2