ND-18-0929, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.09c (Index Number 44)
| ML18186A417 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/02/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.1.02.09c, ND-18-0929 | |
| Download: ML18186A417 (6) | |
Text
ik Southern Nuclear JUL 0 2 2018 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com Docket Nos.:
52-025 52-026 ND-18-0929 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 2.1.02.09c [Index Number 441 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 12, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.09c [Index Number44]
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 completed225-days prior to initial fuel load.
This notification is informed by the guidance described in NEI 08-01, Industry Guidelinefor 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 NRCto support the Commission finding that all acceptance criteria are met priorto 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 Unit4 Completion Plan for Uncompleted ITAAC 2.1.02.09c [Index Number 44]
MJY/PGL/amw
U.S. Nuclear Regulatory Commission ND-18-0929 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc; Nuclear Reauiatorv Commission Mr. W. Jones (w/o enclosures)
Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Qqiethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0929 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. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis 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. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0929 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0929 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.09c [Index Number 44]
U.S. Nuclear Regulatory Commission ND-18-0929 Enclosure Page 2 of 3 ITAAC Statement Desian Commitment:
9.0) The pressurizer heaters trip after a signal is generated by the RMS.
Inspection. Tests. Analyses:
Testing will be performed to confirm trip of the pressurizer heaters identified in Table 2.1.2-3.
Acceptance Criteria:
The pressurizer heaters identified in Table 2.1.2-3 trip after a signal Is generated by the RMS.
ITAAC Completion Description Testing is performed in accordance with Unit3 and Unit4 preoperational test procedures 3-RMS-ITRR-523 and 4-RMS-ITRR-523 (References 1 and 2, respectively) to confirm that the pressurizer heaters identified in Combined License (COL) Appendix C Table 2.1.2-3 trip after a signal is generated by the Protection and Safety Monitoring System (RMS).
The pressurizer heater breakers are placed in the closed position and an actuation signal is generated by inserting a simulated high-pressure condition for two of the containment pressure channels at the RMS cabinets. Each breaker identified in Table 2.1.2-3 (Attachment A) is verifiedto open using the Main Control Room (MCR) display as well as local inspection of the switchgear. Results ofthe preoperational testing are documented on data sheets included inthe Unit 3 and Unit4 preoperational test procedures (References 1 and 2, respectively), and confirm that each of the pressurizer heaters identified inTable 2.1.2-3 trips after a signal is generated by the RMS.
References 1 and 2 are available for NRC Inspection as part of the ITAAC 2.1.02.09c Completion Packages (Reference 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 ITAAC 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. 3-RMS-ITRR-523, "Containment Pressure High-2 Actuation Preoperational Test Procedure"
- 2. 4-PMS-ITPP-523, "Containment Pressure High-2 Actuation Preoperational Test Procedure" 3.
2.1.02.09c-U3-CP-Rev0, ITAAC Completion Package 4.
2.1.02.09c-U4-CP-Rev0, 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-18-0929 Enclosure Page 3 of 3 Attachment A Excerpt from Combined License Appendix C Table 2.1.2-3 Table 2.1.2-3 Equipment Tag No.
Display Control Function Pressurizer Heaters RCS-EH-03 Yes On/Off Pressurizer Heaters RCS-EH-04A Yes On/Off Pressurizer Heaters RCS-EH-04B Yes On/Off Pressurizer Heaters RCS-EH-04C Yes On/Off Pressurizer Heaters RCS-EH-04D Yes On/Off