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Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.01.02.i (Index Number 579)
	ML18067A136
Person / Time
Site:	Vogtle
Issue date:	03/06/2018
From:	Yox M; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of New Reactors
References
	ITAAC 2.6.01.02.i, ND-18-0304
	Download: ML18067A136 (8)
	v • d • e

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830

^ Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 ceii myox@southernco.com MAR 0 6 2018 Docket Nos.: 52-025 52-026 ND-18-0304 10 CFR 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 2.6.01.02.i [Index Number 5791 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 1, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.6.01.02.1

[Index Number579] 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:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.6.01.02.1 [Index Number 579]

MUY/PGLVamw

U.S. Nuclear Regulatory Commission ND-18-0304 Page 2 of 3 To:

Southern Nuclear Operating Company / Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKlnney Mr. M. J. Vox Mr. D. L. Fulton Mr. J. D. Williams 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 Reaulatorv 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. P. B. Donnelly 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 Qqiethoroe Power Corporation Mr. R. B. Brinkman Municipal Eiectric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0304 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. J. 8. 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., CDS Associates, inc.

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0304 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0304 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.6.01.02.1 [Index Number 579]

U.S. Nuclear Regulatory Commission ND-18-0304 Enclosure Page 2 of 5 ITAAC Statement Design Commitment

2. The seismic Category I equipment identified in Table 2.6.1-1 can withstand seismic design basis loads without loss of safety function.

Inspections. Tests. Analyses i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 2.6.1-1 is located on the Nuclear Island.

ii) Typetests, analyses, or a combination oftype tests and analyses of seismic Category I equipment will be performed.

ill) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

Acceptance Criteria i) Theseismic Category Iequipment identified in Table 2.6.1-1 is located on the Nuclear Island.

ii) Areport exists and concludes that the seismic Category Iequipment can withstand seismic design basis loads without loss of safety function.

iii) Areport exists and concludes that the as-built equipment including anchorage isseismically bounded by the tested or analyzed conditions.

ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Main ac Power System (ECS) equipment identified as seismic Category Ior Class 1E in the Combined License (COL) Appendix C, Table 2.6.1-1 (theTable) are designed and constructed in accordance with applicable requirements.

ii The seismic Category I eouioment identified in Table 2.6.1-1 is located on the Nuclear Island.

To assure that seismic Category Iequipment can withstand seismic design basis loads without loss of safety function, all the equipment in theTable is designed to be located onthe seismic Category INuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the ECS to confirm the satisfactory installation ofthe seismically qualified equipment. The inspection includes verification of equipment make/model/serial number andverification of equipment location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category I equipment is located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-18-0304 Enclosure Page 3 of 5 ii) A report exists and concludes that the seismic Cateoorv I eauioment can withstand seismic design basis loads without loss of safety function.

Seismic Category I equipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Safety-related (Class 1E) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 3). The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment in the Table is identified in Attachment A. Additional information about the methods used to qualify API 000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 4). The EQ Reports (Reference 5) identified in Attachment A contain applicable test reports and associated documentation and conclude that the seismic Category I equipmentcan withstand seismic design basis loads without loss of safety function.

iii) A report exists and concludes that the as-built eauioment including anchorage is seismicallv bounded bv the tested or analyzed conditions.

An inspection (Reference 1) is conducted to confirm the satisfactory installation of the seismically qualified equipment in the Table. The inspection verifies the equipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other interfaces. The documentation of installed configuration of seismically qualified equipment includes photographs and/orsketches/drawings of equipment/mounting/interfaces.

As part of the seismic qualification program, consideration is given to the definition ofthe clearances needed around the equipment mounted in the plant to permit the equipment to move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This is done as part ofseismic testing by measuring the maximum dynamic relative displacement of the top and bottom ofthe equipment. EQ Reports (Reference 5) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification.

Interface requirements are defined based on the test configuration and otherdesign requirements.

Attachment A identifies the EQRR (Reference 2) completed to verify that the as-built seismic Category Iequipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 3) and NRG Regulatory Guide (RG) 1.100 (Reference 6).

Together, these reports (References 2 and 5) provide evidence thatthe ITAAC Acceptance Criteria requirements are met:

The seismicCategory Iequipment identified in Table 2.6.1-1 is located on the Nuclear Island;

Areport exists and concludes that the seismic Category 1equipment can withstand seismic design basis loads without loss of safety function; and

U.S. Nuclear Regulatory Commission ND-18-0304 Enclosure Page 4 of 5

A report exists and concludes that the as-bullt equipment Including anchorage Is selsmlcally bounded by the tested or analyzed conditions.

References 2 and 5 are available for NRG Inspection as part of the Unit 3 and Unit 4 ITAAC 2.6.01.02.1 Completion Packages (References 7 and 8, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertainingto the subject ITAAC and associated corrective actions. This finding review, which Included now-consolidated ITAAC Indexes 580 and 581, found there are no relevant ITAAC findings associated with this ITAAC.

References (available for NRG inspection)

1. ND-xx-xx-001, "EG Walkdown ITAAC Guideline"

2. EQ As-Bullt Reconciliation Reports (EQRR) as Identified In Attachment A for Units 3 and 4

3. IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"

4. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API 000 Safety-Related Electrical and Mechanical Equipment"

5. Equipment Qualification (EQ) Reports as Identified In Attachment A

6. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

7. 2.6.01.02.l-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.6.01.02.1 [Index Number 579]"

8. 2.6.01.02.l-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.6.01.02.1 [Index Number 579]"

9. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0304 Enclosure Page 5 of 5 Attachment A System: Main ac Power System (ECS)

Seismic Type of As-Buiit EQRR Equipment Name ^ Tag No.

EQ Reports (Reference 5)

Cat. 1 ^ Qual. (Reference 2)

Reactor Coolant Type APP-ES02-VBR-003 / 2.6.01.02.i-U3-Pump (RCP) Circuit ECS-ES-31 Yes Test &

APP-ES02-VBR-001 EQRR-PCDXXX Breaker Analysis Type APP-ES02-VBR-003 / 2.6.01.02.i-U3-RCP Circuit Breaker ECS-ES-32 Yes Test &