ND-19-0979, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.07b (Index Number 26)
| ML19225C361 | |
| 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-19-0979 | |
| Download: ML19225C361 (11) | |
Text
Jtk. Southern Nuclear AUG 1 2 2019 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-19-0979 10CFR 52.99(c)(3)
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 2.1.02.07b [Index Number 261 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of August 7, 2019, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.07b
[Index Number 26] 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:
MJY/RLB/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.07b [Index Number 26]
U.S. Nuclear Regulatory Commission ND-19-0979 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 Reoulatorv 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 Oqiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-19-0979 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse 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., 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, Baich Bingham
U.S. Nuclear Regulatory Commission ND-19-0979 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-19-0979 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.07b [Index Number 26]
U.S. Nuclear Regulatory Commission ND-19-0979 Enclosure Page 2 of 8 ITAAC Statement Desion Commitment 7.b) The Class 1E components identifiecl in Table 2.1.2-1 are powered from their respective Class 1E division.
I nsoections/Tests/Anaivses Testing will be performed on the RCS 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 2.1.2-1 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 2.1.2-1 (Attachment A) to demonstrate they are powered from their respective Class IE division. This ITAAC performs testing on the Reactor Coolant System (RCS) equipment identified in Table 2.1.2-1 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 SNC921640 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 3 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 IE 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 2.1.2-1 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
U.S. Nuclear Regulatory Commission ND-19-0979 Enclosure Page 3 of 8 associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.
References (available for NRG inspection)
- 1. ITAAC 2.5.02.05a Closure Notification
- 2. SNC921640, "RCS Component Power Verification Test -
ITAAC: SV3-2.1.02.07b"
- 3. SNCXXXXXX, "RCS Component Power Verification Test -
ITAAC: SV4-2.1.02.07b"
- 4. 2.1.02.07b-U3-CP-Rev0, ITAAC Completion Package
- 5. 2.1.02.07b-U4-CP-Rev0, 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-19-0979 Enclosure Page 4 of 8 Attachment A COL Appendix C Table 2.1.2-1 Equipment Name*
Tag No.*
First-stage ADS Motor-operated Valve (MOV)
RCS-PL-V001A First-stage ADS MOV RCS-PL-V001B Second-stage ADS MOV RCS-PL-V002A Second-stage ADS MOV RCS-PL-V002B Third-stage ADS MOV RCS-PL-V003A Third-stage ADS MOV RCS-PL-V003B Fourth-stage ADS Squib Valve RCS-PL-V004A Fourth-stage ADS Squib Valve RCS-PL-V004B Fourth-stage ADS Squib Valve RCS-PL-V004C Fourth-stage ADS Squib Valve RCS-PL-V004D First-stage ADS Isolation MOV RCS-PL-V011A First-stage ADS Isolation MOV RCS-PL-V011B Second-stage ADS Isolation MOV RCS-PL-V012A Second-stage ADS Isolation MOV RCS-PL-V012B Third-stage ADS Isolation MOV RCS-PL-V013A Third-stage ADS Isolation MOV RCS-PL-V013B Fourth-stage ADS MOV RCS-PL-V014A Fourth-stage ADS MOV RCS-PL-V014B Fourth-stage ADS MOV RCS-PL-V014C Fourth-stage ADS MOV RCS-PL-V014D Reactor Vessel Head Vent Valve RCS-PL-V150A
U.S. Nuclear Regulatory Commission ND-19-0979 Enclosure Page 5 of 8 Reactor Vessel Head Vent Valve RGS-PL-V150B Reactor Vessel Head Vent Valve RGS-PL-V150G Reactor Vessel Head Vent Valve RGS-PL-V150D RGB Hot Leg 1 Flow Sensor RGS-101A RGB Hot Leg 1 Flow Sensor RGS-101B RGB Hot Leg 1 Flow Sensor RGS-101G RGB Hot Leg 1 Flow Sensor RGS-101D RGB Hot Leg 2 Flow Sensor RGS-102A RGB Hot Leg 2 Flow Sensor RGS-102B RGB Hot Leg 2 Flow Sensor RGS-102G RGB Hot Leg 2 Flow Sensor RGS-102D RGB Gold Leg 1A Narrow Range Temperature Sensor RGS-121A RGB Gold Leg 1B Narrow Range Temperature Sensor RGS-121B RGB Gold Leg 1B Narrow Range Temperature Sensor RGS-121G RGB Gold Leg 1A Narrow Range Temperature Sensor RGS-121D RGB Gold Leg 2B Narrow Range Temperature Sensor RGS-122A RGB Gold Leg 2A Narrow Range Temperature Sensor RGS-122B RGB Gold Leg 2A Narrow Range Temperature Sensor RGS-122G RGB Gold Leg 2B Narrow Range Temperature Sensor RGS-122D RGB Gold Leg 1A Dual Range Temperature Sensor RGS-125A RGB Gold Leg 2A Dual Range Temperature Sensor RGS-125B RGB Gold Leg 1B Dual Range Temperature Sensor RGS-125G RGB Gold Leg 2B Dual Range Temperature Sensor RGS-125D RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-131A
U.S. Nuclear Regulatory Commission ND-19-0979 Enclosure Page 6 of 8 RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-131B RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-131G RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-131D RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-132A RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-132B RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-132G RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-132D RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-133A RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-133B RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-133G RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-133D RGB Hot Leg 1 Wide Range Temperature Sensor RGS-135A RGB Hot Leg 2 Wide Range Temperature Sensor RGS-135B RGB Wide Range Pressure Sensor RGS-140A RGB Wide Range Pressure Sensor RGB-MOB RGB Wide Range Pressure Sensor RGS-140G RGB Wide Range Pressure Sensor RGS-140D RGB Hot Leg 1 Level Sensor RGS-160A RGB Hot Leg 2 Level Sensor RGS-160B Passive Residual Heat Removal (PRHR)
Return Line Temperature Sensor RGS-161 Pressurizer Pressure Sensor RGS-191A Pressurizer Pressure Sensor RGS-191B Pressurizer Pressure Sensor RGS-191G Pressurizer Pressure Sensor RGS-191D
U.S. Nuclear Regulatory Commission ND-19-0979 Enclosure Page 7 of 8 Pressurizer Level Reference Leg Temperature Sensor RCS-193A Pressurizer Level Reference Leg Temperature Sensor RCS-193B Pressurizer Level Reference Leg Temperature Sensor RCS-193C Pressurizer Level Reference Leg Temperature Sensor RCS-193D Pressurizer Level Sensor RCS-195A Pressurizer Level Sensor RCS-195B Pressurizer Level Sensor RCS-195C Pressurizer Level Sensor RCS-195D RCP 1A Bearing Water Temperature Sensor RCS-211A RCP 1A Bearing Water Temperature Sensor RCS-211B RCP 1A Bearing Water Temperature Sensor RCS-211C RCP 1A Bearing Water Temperature Sensor RCS-211D RCP 1B Bearing Water Temperature Sensor RCS-212A RCP 1B Bearing Water Temperature Sensor RCS-212B RCP 1B Bearing Water Temperature Sensor RCS-212C RCP 1B Bearing Water Temperature Sensor RCS-212D RCP 2A Bearing Water Temperature Sensor RCS-213A RCP 2A Bearing Water Temperature Sensor RCS-213B RCP 2A Bearing Water Temperature Sensor RCS-213C RCP 2A Bearing Water Temperature Sensor RCS-213D RCP 2B Bearing Water Temperature Sensor RCS-214A RCP 2B Bearing Water Temperature Sensor RCS-214B RCP 2B Bearing Water Temperature Sensor RCS-214C RCP 2B Bearing Water Temperature Sensor RCS-214D
U.S. Nuclear Regulatory Commission ND-19-0979 Enclosure Page 8 of 8 RCP 1A Pump Speed Sensor RCS-281 RCP 1B Pump Speed Sensor RCS-282 RCP 2A Pump Speed Sensor RCS-283 RCP 28 Pump Speed Sensor RCS-284 Excerpted from COL Appendix C Table 2.1.2-1