ND-19-0864, Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.2.02.06b (Index Number 133)

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Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.2.02.06b (Index Number 133)
ML19200A257
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-19-0864
Download: ML19200A257 (7)


Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei JUL 1 9 2019 Docket Nos.: 52-025 52-026 ND-19-0864 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 2.2.02.06b flndex Number 1331 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 16, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.02.06b [Index Number 133] 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 2.2.02.06b [Index Number 133]

MJY/RLB/sfr

U.S. Nuclear Regulatory Commission ND-19-0864 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. Vox 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0864 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. 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., GDS Associates, inc.

Mr. 8. Roetger, Georgia Pubiic Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0864 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0864 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.02.06b [Index Number 133]

U.S. Nuclear Regulatory Commission ND-19-0864 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 6.b) The Class 1E components identified in Table 2.2.2-1 are powered from their respective Class 1E division.

i nspections/Tests/Anaivses 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 components identified in Table 2.2.2-1 when the assigned Class 1E division is provided the test signal.

ITAAC Compietion Description Testing is performed on the Class 1E components identified in the VEGP Unit 3 and Unit 4 COL Appendix C Table 2.2.2-1 (Attachment A)to demonstrate they are powered from their respective Class 1E division. This ITAAC performs testing on the components identified in Table 2.2.2-1 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 SNC921237 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 components 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 components identified in Appendix A are powered from their 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 components identified in Table 2.2.2-1 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 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-19-0864 Enclosure Page 3 of 4 References(available for NRC inspection)

1. ITAAC 2.5.02.05a Closure Notification
2. SNC921237,"PCS Component Power Verification Test- ITAAC: SV3-2.2.02.06b"
3. SNCXXXXXX,"PCS Component Power Verification Test- ITAAC: SV4-2.2.02.06b"
4. 2.2.02.06b-U3-CP-Rev 0, ITAAC Completion Package
5. 2.2.02.06b-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-19-0864 Enclosure Page 4 of 4 Attachment A COL Appendix C Table 2.2.2-1 Component Name* Tag No.*

PCCWST Isolation Valve PCS-PL-V001A PCCWST Isolation Valve PCS-PL-V001B PCCWST Isolation Valve MOV PCS-PL-V001C PCCWST Isolation Block MOV PCS-PL-V002A PCCWST Isolation Block MOV PCS-PL-V002B PCCWST Isolation Block MOV PCS-PL-V002C PCS Water Delivery Flow Sensor PCS-001 PCS Water Delivery Flow Sensor PCS-002 PCS Water Delivery Flow Sensor PCS-003 PCS Water Delivery Flow Sensor PCS-004 Containment Pressure Sensor PCS-005 Containment Pressure Sensor PCS-006 Containment Pressure Sensor PCS-007 Containment Pressure Sensor PCS-008 PCCWST Water Level Sensor PCS-010 PCCWST Water Level Sensor PCS-011 High-range Containment Pressure Sensor PCS-012 High-range Containment Pressure Sensor PCS-013 High-range Containment Pressure Sensor PCS-014 Excerpted from COL Appendix C Table 2.2.2-1