ND-19-0898, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.07b (Index Number 233)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.07b (Index Number 233)

ML19210D530
Person / Time
Site:	Vogtle
Issue date:	07/26/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0898
Download: ML19210D530 (9)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Southern Nuclear Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel JUL 2 6 2019 Docket Nos.: 52-025 52-026 ND-19-0898 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.04.07b findex Number 2331 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 22, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.04.07b [Index Number 233] 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 Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.07b [Index Number 233]

MJY/RLB/sfr

U.S. Nuclear Regulatory Commission ND-19-0898 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. Karlovlch Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Convert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Oaiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0898 Page 3 of 3 MuniciDal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani(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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-0898 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-19-0898 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.07b [Index Number 233]

U.S. Nuclear Regulatory Commission ND-19-0898 Enclosure Page 2 of 6 ITAAC Statement Design Commitment 7.b) The Class 1E components identified in Table 2.2.4-1 are powered from their respective Class 1E division.

I nsoections/Tests/Analvses Testing will be performed 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 2.2.4-1 when the assigned Class 1E division is provided the test signal.

ITAAC Completion Description Testing is performed on the Class 1E components(equipment) identified in the VEGP Unit 3 and Unit 4 COL Appendix C Table 2.2.4-1 (Attachment A)to demonstrate they are powered from their respective Class 1E division. This ITAAC performs testing on the Steam Generator System (SGS)equipment identified in Table 2.2.4-1 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 ITAAC 2.5.02.05a component testing (Reference 1) and confirms the PMS cabinets are powered from their respective Class 1E division. Unit 3 and Unit 4 component test package work orders SNC922104 and SNCXXXXXX (References 2 and 3, respectively) document completion of power verification activities from the PMS cabinets and the Class 1E power distribution panels/motor control centers to the equipment identified in Attachment A. References 2 and 3 first verify that power supply cables/wiring are installed and terminated from the applicable PMS cabinet and Class 1E power distribution panel/motor control center to the respective component identified in Attachment A using approved construction drawings and cable/wiring termination documentation. References 2 and 3then 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 Class 1E division.

The Unit 3 and Unit 4 component test package work orders(References 2 and 3, respectively) confirm that a simulated test signal exists at the Class 1E equipment identified in Table 2.2.4-1 when the assigned Class 1E division is provided the test signal.

References 2 and 3 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC Completion Packages(References 4 and 5).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nucle/ar 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

U.S. Nuclear Regulatory Commission ND-19-0898 Enclosure Page 3 of 6 associated with this ITAAC.

References favailable for NRG inspection)

1. ITAAC 2.5.02.05a Closure Notification

2. SNC922104,"SGS Component Power Verification Test- ITAAC: SV3-2.2.04.07b"

3. SNCXXXXXX,"SGS Component Power Verification Test - ITAAC: SV4-2.2.04.07b"

4. 2.2.04.07b-U3-CP-Rev 0, ITAAC Completion Package

5. 2.2.04.07b-U4-CP-Rev 0, ITAAC Completion Package

6. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-0898 Enclosure Page 4 of 6 Attachment A COL Appendix C Table 2.2.4-1 Equipment Name* Tag No.*

Power-operated Relief Valve Block Motor-SGS-PL-V027A operated Valve Steam Generator 01 Power-operated Relief Valve Block Motor-SGS-PL-V027S operated Valve Steam Generator 02 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Steam Line Condensate Drain Isolation Valve SGS-PL-V036S Main Steam Line Isolation Valve SGS-PL-V040A Main Steam Line Isolation Valve SGS-PL-V040S Steam Line Condensate Drain Control Valve SGS-PL-V086A Steam Line Condensate Drain Control Valve SGS-PL-V086S Main Feedwater Isolation Valve SGS-PL-V057A Main Feedwater Isolation Valve SGS-PL-V057S Startup Feedwater Isolation SGS-PL-V067A Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067S Motor-operated Valve Steam Generator Slowdown Isolation Valve SGS-PL-V074A Steam Generator Slowdown Isolation Valve SGS-PL-V074S Steam Generator Slowdown Isolation Valve SGS-PL-V075A Steam Generator Slowdown Isolation Valve SGS-PL-V075S Power-operated Relief Valve SGS-PL-V233A Power-operated Relief Valve SGS-PL-V233S Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Main Steam Isolation Valve Bypass Isolation SGS-PL-V240S Main Feedwater Control Valve SGS-PL-V250A

U.S. Nuclear Regulatory Commission ND-19-0898 Enclosure Page 5 of 6 Main Feedwater Control Valve SGS-PL-V250B Startup Feedwater Control Valve SGS-PL-V255A Startup Feedwater Control Valve SGS-PL-V255B Steam Generator 1 Narrow Range Level Sensor SGS-001 Steam Generator 1 Narrow Range Level Sensor SGS-002 Steam Generator 1 Narrow Range Level Sensor SGS-003 Steam Generator 1 Narrow Range Level Sensor SGS-004 Steam Generator 2 Narrow Range Level Sensor SGS-005 Steam Generator 2 Narrow Range Level Sensor SGS-006 Steam Generator 2 Narrow Range Level Sensor SGS-007 Steam Generator 2 Narrow Range Level Sensor SGS-008 Steam Generator 1 Wide Range Level Sensor SGS-011 Steam Generator 1 Wide Range Level Sensor SGS-012 Steam Generator 2 Wide Range Level Sensor SGS-013 Steam Generator 2 Wide Range Level Sensor SGS-014 Steam Generator 1 Wide Range Level Sensor SGS-015 Steam Generator 1 Wide Range Level Sensor SGS-016 Steam Generator 2 Wide Range Level Sensor SGS-017 Steam Generator 2 Wide Range Level Sensor SGS-018 Main Steam Line Steam Generator 1 SGS-030 Pressure Sensor Main Steam Line Steam Generator 1 SGS-031 Pressure Sensor Main Steam Line Steam Generator 1 SGS-032 Pressure Sensor Main Steam Line Steam Generator 1 SGS-033 Pressure Sensor Main Steam Line Steam Generator 2 SGS-034 Pressure Sensor

U.S. Nuclear Regulatory Commission ND-19-0898 Enclosure Page 6 of 6 Main Steam Line Steam Generator 2 SGS-035 Pressure Sensor Main Steam Line Steam Generator 2 SGS-036 Pressure Sensor Main Steam Line Steam Generator 2 SGS-037 Pressure Sensor Steam Generator 1 Startup Feedwater SGS-55A Flow Sensor Steam Generator 1 Startup Feedwater SGS-55B Flow Sensor Steam Generator 2 Startup Feedwater SGS-56A Flow Sensor Steam Generator 2 Startup Feedwater SGS-56B Flow Sensor Excerpted from COL Appendix C Table 2.2.4-1