ND-19-0945, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.06b (Index Number 103)
| ML19224B575 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/12/2019 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-19-0945 | |
| Download: ML19224B575 (8) | |
Text
Southern Nuclear Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Roarj Waynesboro, GA 30830 706-848-6459 tei AU6 1 2 2019 Docket Nos.;52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-19-0945 10CFR 52.99(c)(3)
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 2.2.01.06b [Index Number 1031 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 31, 2019, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.06b [Index Number 103] 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:
MJY/RLB/sfr Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.06b [Index Number 103]
U.S. Nuclear Regulatory Commission ND-19-0945 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. P. P. Sena III (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. G. Chick Mr. M. J. Vox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak 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 Regulatory Commission Mr. W. Jones (w/o enclosures)
Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khourl 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 Oalethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-19-0945 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. C. Durham (w/o enclosures)
Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hesler, 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 Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham
U.S. Nuclear Regulatory Commission ND-19-0945 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-19-0945 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.06b [Index Number 103]
U.S. Nuclear Regulatory Commission ND-19-0945 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment 6.b) The Class 1E components identified in Table 2.2.1-1 are powered from their respective Class 1E division.
I nsoections/Tests/Anaivses Testing will be performed by providing a simulated test signal in each Class IE division.
Acceotance Criteria A simulated test signal exists at the Class 1E equipment identified in Table 2.2.1-1 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 2.2.1-1 (Attachment A) to demonstrate they are powered from their respective Class 1E division. This ITAAC performs testing on the Containment System (CNS) equipment identified in Table 2.2.1-1 by providing a simulated test signal in each Class 1E division. The Class 1E electrical penetrations identified in Attachment A are also tested by this iTAAC.
The electrical penetrations identified in Attachment A provide electrical continuity from Class 1E power supplies Outside Reactor Containment (ORC) to Class IE equipment Inside Reactor Containment (IRC), and are not themselves powered components. Multiple Class 1E component and equipment ITAAC perform Class 1E power verifications that include power verifications through the electrical penetrations identified in Attachment A. Thus, for the purposes of this ITAAC's design commitment scope. Unit 3 and Unit 4 component test package work orders SNC920985 and SNCXXXXXX (References 1 and 2, respectively) document completion of Class 1E power verification testing on the containment Electrical Penetration Assembly (EPA) electrical conductors from the ORC EPA field cable conductor termination point to the IRC EPA field cable conductor termination point for the Class 1E power electrical penetrations identified in Attachment A. References 1 and 2 first verify that the Class 1E power EPA feedthrough conductors are installed in the containment electrical penetrations identified in Attachment A using approved construction drawings and EPA installation documentation.
References 1 and 2 then confirm, via EPA inspection documentation, that continuity testing is performed on each of the installed Class 1E power EPA feedthrough conductors to confirm current flow within the installed conductor. The combination of Class 1E power EPA feedthrough conductor installation verification, with the installed EPA feedthrough conductor continuity testing confirms that the EPA electrical conductors from the ORC EPA field cable conductor termination point to the IRC EPA field cable conductor termination point for the Class 1E electrical penetrations identified in Attachment A are powered from their respective Class 1E division.
For the remaining equipment identified in Attachment A, Unit 3 and Unit 4 component test package work orders SNC920985 and SNCXXXXXX (References 1 and 2, 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.
Class 1E power verification testing of the Protection and Safety Monitoring System (PMS)
U.S. Nuclear Regulatory Commission ND-19-0945 Enclosure Page 3 of 5 cabinets, associated with the equipment identified in Attachment A, is verified through ITAAC 2.5.02.05a component testing (Reference 3) and confirms the RMS cabinets are powered from their respective Class 1E division. References 1 and 2 first verify that power supply cables/wiring are installed and terminated from the applicable RMS 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 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 Class 1E division.
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 Class 1E equipment identified in Table 2.2.1-1 when the assigned Class 1E division is provided the test signal.
References 1 and 2 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC Completion Rackages (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.
References (available for NRC inspection)
- 1. SNC920985, "CNS Component Rower Verification Test -
ITAAC: SV3-2.2.01.06b"
- 2. SNCXXXXXX, "CNS Component Rower Verification Test -
ITAAC: SV4-2.2.01.06b"
- 3. ITAAC 2.5.02.05a Closure Notification
- 4. 2.2.01.06b-U3-CR-Rev0, ITAAC Completion Rackage
- 5. 2.2.01.06b-U4-CR-Rev0, ITAAC Completion Rackage
U.S. Nuclear Regulatory Commission ND-19-0945 Enclosure Page 4 of 5 Attachment A COL Appendix C Table 2.2.1-1 Equipment Name*
Tag No.*
Instrument Air Supply Outside Containment Isolation Valve CAS-PL-V014 Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve (MOV) -
Inlet Line Outside Reactor Containment (ORC)
CCS-PL-V200 CCS Containment Isolation MOV -
Outlet Line IRC CCS-PL-V207 CCS Containment Isolation MOV -
Outlet Line ORC CCS-PL-V208 SFS Discharge Line Containment Isolation MOV -
ORC SFS-PL-V038 SFS Suction Line Containment Isolation MOV -
IRC SFS-PL-V034 SFS Suction Line Containment Isolation MOV -
ORC SFS-PL-V035 Containment Purge Inlet Containment Isolation Valve -
ORC VFS-PL-V003 Containment Purge Inlet Containment Isolation Valve -
IRC VFS-PL-V004 Containment Purge Discharge Containment Isolation Valve -
IRC VFS-PL-V009 Containment Purge Discharge Containment Isolation Valve -
ORC VFS-PL-V010 Vacuum Relief Containment Isolation A MOV -
ORC VFS-PL-V800A Vacuum Relief Containment Isolation B MOV -
ORC VFS-PL-V800B Fan Coolers Return Containment Isolation Valve -
IRC VWS-PL-V082 Fan Coolers Return Containment Isolation Valve -
ORC VWS-PL-V086 Fan Coolers Supply Containment Isolation Valve -
ORC VWS-PL-V058 Reactor Coolant Drain Tank (RCDT)
Gas Outlet Containment Isolation Valve -
IRC WLS-PL-V067 RCDT Gas Outlet Containment Isolation Valve -
ORC WLS-PL-V068 Sump Discharge Containment Isolation Valve -
IRC WLS-PL-V055 Sump Discharge Containment Isolation Valve -
ORC WLS-PL-V057
U.S. Nuclear Regulatory Commission ND-19-0945 Enclosure Page 5 of 5 Electrical Penetration P11 IDSA-EY-P11Z Electrical Penetration PI 2 IDSA-EY-P12Y Electrical Penetration PI 3 IDSA-EY-P13Y Electrical Penetration PI4 IDSD-EY-P14Z Electrical Penetration PI 5 IDSD-EY-P15Y Electrical Penetration PI 6 IDSD-EY-P16Y Electrical Penetration P27 IDSC-EY-P27Z Electrical Penetration P28 IDSC-EY-P28Y Electrical Penetration P29 IDSC-EY-P29Y Electrical Penetration P30 IDSB-EY-P30Z Electrical Penetration P31 IDSB-EY-P31Y Electrical Penetration P32 IDSB-EY-P32Y Excerpted from COL Appendix C Table 2.2.1-1