ND-18-1542, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.11c.i (Index Number 212)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.11c.i (Index Number 212)

ML18353B211
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 2.2.03.11c.i, ND-18-1542
Download: ML18353B211 (8)

Text

^ Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@southernco.conn DEC 1 9 2018 Docket Nos.: 52-025 52-026 ND-18-1542 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 2.2.03.11c.i [Index Number 2121 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 17, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspection, Test, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.Ilc.i

[Index Number 212] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.03.1 Ic.i[Index Number 212]. 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.

Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.2.03.1 Ic.i [Index Number 212] ND-17-1127

[ML17186A038] dated June 30, 2017. This resubmittal supersedes ND-17-1127 in its entirety.

This notification is informed bythe 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, oranalyses have not been performed orhave 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.

Respectfullysubmitted Michael J.

Regulatory Affairs Director Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-18-1542 Page 2 of 4

Enclosure:

Vogtle ElectricGenerating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.11c.i [Index Number 212]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-18-1542 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. Yox 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 Reaulatorv 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-1542 Page 4 of 4 Daiton Utilities Mr. T. Bundros WECTEC Mr. 0. A. Castell Westinqhouse Electric Company. LLC Dr. L. OrlanI (w/o enclosures)

Mr. D. C. 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., CDS 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-18-1542 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-1542 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.1Ic.l [Index Number 212]

U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 11 .c) The valves identified in Table 2.2.3-1 as having DAS control perform their active function after receiving a signal from the DAS.

Insoections/Tests/Analvses i) Testing will be performed on the squib valves identified inTable 2.2.3-1 using real or simulated signals into the DAS without stroking the valve.

Acceotance Criteria i) Squib valves receive an electrical signal at the valve electrical leadsthat is capable of actuating the valve after a signal is input to the DAS.

ITAAC ComDietion Description Multiple ITAAC are performed toverify that the valves identified in Combined License (COL)

Appendix C Table 2.2.3-1 (Attachment A) as having Diverse Actuation System (DAS) control perform an active function after receiving a signal from DAS. The subject ITAAC performs testing on the squib valves listed in Attachment A.

Testing 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 that the valves identified in Attachment Aas having DAS control perform an active function after receiving a signal from DAS. Testing is performed on the squib valves using real signals into the DAS without stroking the valve and ensuring the squib valves receive an electrical signal at the valve electrical leads that is capable of actuating the valve.

The squib valves are armed using the manual controls on the DAS panel and then actuated with the DAS actuation controls. During testing each squib valve identified in Attachment Ahas the squib valve igniters replaced with test resistor fixtures. Test resistance is corrected to the maximum resistance expected during accident conditions. A multimeter along with a Data Acquisition (DAQ) system is used to measure both firing current and voltage.

Circuit resistance is measured and inside and outside containment temperatures are measured at multiple locations andare 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 in valve 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 that a sufficient test signal is received at each of the squib valves.

The completed test results (References 1 and 2), confirm that each squib valve, identified in the Attachment A, receives an electrical signal at the valve electrical leads that is capable of actuating the squib valve after a signal is input to the DAS.

U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 3 of 4 References 1 and 2 are available for NRG inspection as part of the Unit 3 and Unit 4ITAAC Completion Packages (Reference 3 and 4, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all findings pertainingto the subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings associated with this ITAAC.

References favailable 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. 2.2.03.11 c.i-U3-CP-Rev 0, ITAAC Completion Package

4. 2.2.03.11 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-18-1542 Enclosure Page 4 of 4 Attachment A Excerpt from COL Appendix 0 Table 2.2.3-1 Equipment Name Tag No. Control RMS/ DAS Containment Recirculation A PXS-PL-V118A YesA'es Squib Valve Containment Recirculation B PXS-PL-V118B YesA'es Squib Valve Containment Recirculation A PXS-PL-V120A YesA'es Squib Valve Containment Recirculation B PXS-PL-V120B YesA'es Squib Valve IRWST Injection A Squib PXS-PL-V123A Yes/Yes Valve IRWST Injection B Squib PXS-PL-V123B YesA^es Valve IRWST Injection A Squib PXS-PL-V125A YesAes Vaive IRWST Injection B Squib PXS-PL-V125B YesAes Valve