ND-18-1541, Unit 4, Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.11c.i (Index Number 51)
| ML18355A673 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/19/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.1.02.11c.i, ND-18-1541 | |
| Download: ML18355A673 (8) | |
Text
Southern Nuclear DEC 1 9 2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 cell myox@souttiernco.com ND-18-1541 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit3 and Unit4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.11c.i [Index Number 511 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern NuclearOperating Company hereby notifies the NRC that as of December 17, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.1.02.1 Ic.i
[Index Number 51] has not been completed greaterthan 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.1.02.1 Ic.i [Index Number 51]. Southern Nuclear Operating Company will, at a laterdate, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.
Southern NuclearOperating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.1.02.1 Ic.i [Index Number 51] ND-17-1166
[ML17186A064] dated June 30, 2017.This resubmittal supersedes ND-17-1166 in itsentirety.
This notification is informed bythe guidance described in NEI-08-01, Industry Guideline forthe 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, oranalyses have not been performed or have been only partially completed.
All ITAAC will be fully completed and all Section 52.99(c)(3) 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.
U.S. Nuclear Regulatory Commission ND-18-1541 Page 2 of 4 Respectfully submitted, Micfiael J. Yox Regulatory Affairs Director Vogtle3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.11c.i [Index Number 51]
MJY/DLW/sfr
U.S. Nuclear Regulatory Commission ND-18-1541 Page 3 of 4 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (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. A. L. Pugh 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 Reoulatorv Commission Mr. W. Jones (w/o enclosures)
Mr. F. D. Brown Ms. J. M. Heisserer 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. I. Cozens Mr. J. Gaslevic Mr. V. Hall Oaiethoroe 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-18-1541 Page 4 of 4 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 Ms. J. Monahan 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. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-1541 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-1541 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.1 Ic.i [Index Number 51]
U.S. Nuclear Regulatory Commission ND-18-1541 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 11.c) The valves identified inTable 2.1.2-1 as having DAS control perform an active safety function after receiving a signal from DAS.
Insoections/Tests/Analvses i) Testing will be performed on the squib valves identified in Table 2.1.2-1 using real or simulated signals into the DAS without stroking the valve.
Acceptance Criteria i) The squibvalves receivea signalat the valve electrical leads that is capable of actuatingthe squib valve.
ITAAC Completion Description Multiple ITAAC are performed to verify thatthe valves identified in Combined License (COL)
Appendix CTable2.1.2-1 (Attachment A) as having Diverse Actuation System(DAS) control perform an active safetyfunction after receiving a signal from DAS. The subject ITAAC performs testing on the squib valves listed inAttachment A.
The preoperational test is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-DAS-ITPP-501 and 4-DAS-ITPP-501 (References 1 and 2) to verify thatthe valves identified inAttachment Aas having DAS control perform an active safety function after receiving a signal from DAS. Testing is performed on the squib valves using real signalsinto the DAS without stroking the valveand ensuring the squib valves receivea signalat the valve electrical leads that is capable of actuating the squib valve.
The squib valves are armed using the manual controls on the DAS paneland then actuatedwith the DAS actuation controls. During testing each squib valve identified inAttachmentAhas the squib valve igniters replaced with test resistor fixtures. Test resistance is correctedto the maximum resistance expected during accident conditions. A multimeter along with a Data Acquisition (DAQ) system is used to measure bothfiring currentand voltage.
Circuit resistance is measured and inside and outside containment temperatures are measured at multiple locations and are used to calculate the circuit resistance expected during accident conditions and at the minimum ambient temperature. The calculated circuit resistances are verified to meet the minimum and maximum allowable resistances.
The minimum signal necessary to actuate the squib valves is specified invalve design information as at least 3.7 amperes for 10 milliseconds. The information recorded during testing of voltage and firing current is utilized to confirm thata sufficient test signal is received at each of the squib valves.
Thecompleted test results (References 1 and 2), confirm that each squibvalve, identified in the AttachmentA, receives an electrical signal at the valve electrical leads that is capable of actuating the squib valve after a signal is inputto the DAS.
U.S. Nuclear Regulatory Commission ND-18-1541 Enclosure Page 3 of 4 References 1 and 2 are available for NRG inspection as part of tfie Unit3 and Unit4 ITAAC Completion Packages (Reference 3 and 4, respectively).
List of ITAAC Findings Inaccordance witfi plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performeda review of allfindings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings associated with this ITAAC.
References favaiiabie for NRG inspection)
- 1. 3-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure" 2.
4-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure" 3.
2.1.02.11 c.i-U3-CP-Rev 0, ITAAC Completion Package 4.
2.1.02.11 c.i-U4-CP-Rev 0, 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-18-1541 Enclosure Page 4 of 4 Attachment A' Equipment Name Tag No.
Control RMS/ DAS Fourth-stage ADS Squib Valve RCS-PL-V004A YesA'es Fourth-stage ADS Squib Valve RCS-PL-V004B Yes/Yes Fourth-stage ADS Squib Valve RCS-PL-V004C YesA'es Fourth-stage ADS Squib Valve RCS-PL-V004D YesA'es Excerpt from COL Appendix C Table 2.1.2-1