ND-19-0974, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.12a.iii (Index Number 55)
| ML19221B697 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/09/2019 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-19-0974 | |
| Download: ML19221B697 (8) | |
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Southern Nuclear Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 708-848-6459 tei AU6 0 9 2013 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-19-0974 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 2.1.02.12a.iii [Index Number 551 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 Inspection, Test, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.12a.ill
[Index Number 55] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.1.02.12a.iii [Index Number 55]. 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
U.S. Nuclear Regulatory Commission ND-19-0974 Page 2 of 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.iii [Index Number 55]
MJY/GCW/sfr
U.S. Nuclear Regulatory Commission ND-19-0974 Page 3 of 4 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter 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 Reaulatorv 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. Karlovlch 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-19-0974 Page 4 of 4 Municipai 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. 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, Baich Bingham
U.S. Nuclear Regulatory Commission ND-19-0974 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0974 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.ili [Index Number 55]
U.S. Nuclear Regulatory Commission ND-19-0974 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 12.a) The automatic depressurization valves identified in Table 2.1.2-1 perform an active safety-related function to change position as indicated in the table.
Insoections/Tests/Analvses ill) Tests of the motor-operated valves will be performed under preoperational flow, differential pressure and temperature conditions.
Acceotance Criteria iii) Each motor-operated valve changes position as indicated in Table 2.1.2-1 under pre operational test conditions.
ITAAC Completion Description Multiple ITAAC are performed to verify that the automatic depressurization valves (ADS) identified in Table 2.1.2-1 perform an active safety-related function to change position as indicated in the table. This ITAAC verifies each motor-operated valve (MOV) changes position as indicated in Table 2.1.2-1 under preoperational test conditions.
Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-PXS-ITPP-505 and 4-PXS-ITPP-505 (References 1 and 2) to verify that each motor-operated valve changes position as indicated in Attachment A under preoperational test conditions.
Testing is performed sequentially on each ADS stage which has an A and B train and each MOV is operated using the Component Interface Module (CIM). The valves are tested one stage at a time and the tested valves are initially verified locally and in the Main Control Room (MCR) to be in the Closed position. Starting with the first train of the first stage of ADS, testing is performed on the MOVs with the pressurizer at 2235 psig +30 psig. Each ADS first stage isolation MOV is opened pressurizing the downstream line and verified to Open. Each ADS first stage MOV is then closed and the corresponding downstream ADS first stage MOV (control valve) is opened under pressure and verified to Open. This same test is repeated for each train of the second and third stage ADS MOVs with the pressurizer at 1200 psig +30 psig and 500 psig +30 psig, respectively. Note, the fourth-stage ADS MOVs are normally open and do not have an active function to transfer closed.
The completed Unit 3 and Unit 4 test results (References 1 and 2) verify that each motor-operated valve changes position as indicated in Table 2.1.2-1 under preoperational test conditions.
References 1 and 2 are available for NRC inspection as part of the ITAAC Completion Packages (References 3 and 4).
U.S. Nuclear Regulatory Commission ND-19-0974 Enclosure Page 3 of 4 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company 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 (avaiiabie for NRG inspection)
- 3. 2.1.02.12a.iiii-U3-CP-RevO, ITAAC Completion Package
- 4. 2.1.02.12a.iiii-U4-CP-RevO, 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-19-0974 Enclosure Page 4 of 4 Attachment A
- Excerpt from COL Appendix 0 Table 2.1.2-1 Equipment Name
- Tag No.
- Active Function
RCS-PL-V001A Transfer Open First-stage ADS MOV RCS-PL-V001B Transfer Open Second-stage ADS MOV RCS-PL-V002A Transfer Open Second-stage ADS MOV RCS-PL-V002B Transfer Open Third-stage ADS MOV RCS-PL-V003A Transfer Open Third-stage ADS MOV RCS-PL-V003B Transfer Open First-stage ADS Isolation MOV RCS-PL-V011A Transfer Open First-stage ADS Isolation MOV RCS-PL-V011B Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012A Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012B Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013A Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013B Transfer Open