ND-18-0433, Voggle Electric Generating Plant Unit 3 and Unit 4 - Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.10.05a.1 (Index Number 437)

Voggle Electric Generating Plant Unit 3 and Unit 4 - Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.10.05a.1 (Index Number 437)

ML18106A848
Person / Time
Site:	Vogtle
Issue date:	04/06/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.3.10.05a.i, ND-18-0433
Download: ML18106A848 (10)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@souttiernco.com APR 0 6 2018 Docket Nos.: 52-025 52-026 ND-18-0433 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 Resubmlttal of Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.10.05a.l findex Number 4371 Ladles and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 3, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.10.05a.I [Index Number 437] 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.

Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Priorto Initial Fuel Loadfor Item 2.3.10.05a.l [Index Number437] ND-18-0087

[ML18032A471] dated January 26, 2018. This resubmlttal supersedes ND-18-0087 In Its entirety.

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-18-0433 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.10.OSa.i [Index Number 437]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0433 Page 3 of 4 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. 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 Reouiatorv 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 Oalethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0433 Page 4 of 4 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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. Deangells 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0433 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-18-0433 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.10.OSa.i [Index Number 437]

U.S. Nuclear Regulatory Commission ND-18-0433 Enclosure Page 2 of 6 ITAAC Statement Desion Commitment:

5.a) The seismic Category I equipment identified in Table 2.3.10-1 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 2.3.10-1 is located on the Nuclear Island.

ii) Type tests, analyses, or a combination of type 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) The seismic Category Iequipment identified in Table 2.3.10-1 is located on the Nuclear Island.

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

iii) Areport exists and concludes thatthe 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 ensurethe Liquid Radwaste System (WLS) components identified as seismic Category Iin the Combined License (COL) Appendix C, Table 2.3.10-1 (theTable) are designed and constructed in accordance with applicable requirements.

if The seismic Cateoorv I eouioment identified in Table 2.3.10-1 is located on the Nuclear Island.

To assure that seismic Category Icomponents can withstand seismic design basis loads without lossofsafetyfunction, all the components in the Table are designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EG)

Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the WLS to confirm the satisfactory installation of theseismically qualified components. The inspection includes verification of equipment make/model/serial number and verification 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 Icomponents are located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-18-0433 Enclosure Page 3 of 6 I!) A report exists and concludes that the seismic Category I eouipment can withstand seismic desion basis loads without loss of safety function.

Seismic Category I components in the Table require type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves, as well as other passive seismic Category I mechanical equipment, is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).

The specific qualification method (i.e., type testing, analysis, or combination) used for each component in the Table is identified in Attachment A. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 5). The EQ Reports (Reference 6) identified in Attachment Acontain applicable test reports and associated documentation and conclude thatthe seismic Category Iequipment can withstand seismic design basis loads without loss of safety function.

iii) A report exists and concludes that the as-built equipment includino anchoraoe is seismicallv bounded bv the tested or analvzed conditions.

An inspection (Reference 1) is conducted to confirm the satisfactory installation ofthe seismically qualified components 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. Thedocumentation of installed configuration of seismically qualified components includes photographs and/or sketches/drawings of equipment/mounting/interfaces.

As part of the seismic qualification program, consideration isgiven to the definition of the 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 of seismic testing by measuring the maximum dynamic relative displacement of the topand bottom of the equipment. EQ Reports (Reference 6) 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 theTable, including anchorage, are seismically bounded by the tested or analyzed conditions and NRG Regulatory Guide 1.100 (Reference 7).

Together, these reports (References 2 and 6) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category Iequipment identified in Table 2.3.10-1 is located on the Nuclear Island;

U.S. Nuclear Regulatory Commission ND-18-0433 Enclosure Page 4 of 6

• A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; and

• A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

References 2 and 6 are available for NRC inspection as part of the Unit 3 and Unit 4ITAAC 2.3.10.05a.i Completion Packages (References 8 and 9, 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 pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 438 and 439, found no relevant ITAAC findings associated with this ITAAC.

References ^available for NRC inspection)

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

2. EQ As-Built Reconciliation Reports (EQRR) as identified in Attachment Afor Units 3 and 4

3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

Code,Section III, "Rulesfor Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda

4. ASME QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007

5. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment"

6. Equipment Qualification (EQ) Reports as identified inAttachment A

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

8. 2.3.10.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.3.10.OSa.i [Index Number 437]"

9. 2.3.10.05a.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.3.10.05a.i [Index Number 437]"

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

U.S. Nuclear Regulatory Commission ND-18-0433 Enclosure Page 5 of 6 Attachment A System: Liquid Radwaste System (WLS)

As-Built EQ EQ Reports Reconciliation Equipment Name

• Tag No.

• Seismic Cat. 1

• Type of Qual. (Reference 6) Report (EQRR)

(Reference 2)*

WLS Containment Sump Level WLS-034 APP-JE27-VBR-XXX / 2.3.10.05a.i-U3-Yes Type Testing & Analysis APP-JE27-VBR-YYY EQRR-PCDXXX Sensor WLS Containment Sump Level APP-JE27-VBR-XXX / 2.3.10.05a.i-U3-WLS-035 Yes Type Testing & Analysis APP-JE27-VBR-YYY EQRR-PCDXXX Sensor WLS Containment Sump Level APP-JE27-VBR-XXX / 2.3.10.05a.i-U3-WLS-036 Yes Type Testing & Analysis APP-JE27-VBR-YYY EQRR-PCDXXX Sensor WLS Drain from Passive Core Cooling System (PXS) WLS-PL- APP-PV03-VBR-014/ 2.3.10.05a.i-U3-Yes Analysis Compartment A (Room 11206) V071B APP-PV03-VBR-013 EQRR-PCDXXX Check Valve WLS Drain from PXS APP-PV03-VBR-014/ 2.3.10.05a.i-U3-WLS-PL-Compartment A (Room 11206) Yes Analysis V072B APP-PV03-VBR-013 EQRR-PCDXXX Check Valve WLS Drain from PXS APP-PV03-VBR-014/ 2.3.10.05a.i-U3-WLS-PL-Compartment B (Room 11207) Yes Analysis V071C APP-PV03-VBR-013 EQRR-PCDXXX Check Valve WLS Drain from PXS APP-PV03-VBR-014 / 2.3.10.05a.i-U3-WLS-PL-Compartment B (Room 11207) Yes Analysis V072C APP-PV03-VBR-013 EQRR-PCDXXX Check Valve WLS Drain from Chemical and Volume Control System (CVS) WLS-PL- APP-PV03-VBR-014/ 2.3.10.05a.i-U3-Yes Analysis Compartment (Room 11209) V071A APP-PV03-VBR-013 EQRR-PCDXXX Check Valve WLS Drain from CVS APP-PV03-VBR-014/ 2.3.10.05a.i-U3-

• WLS-PL-Compartment (Room 11209) Yes Analysis V072A APP-PV03-VBR-013 EQRR-PCDXXX Check Valve

U.S. Nuclear Regulatory Commission ND-18-0433 Enclosure Page 6 of 6 As-Built EQ EQ Reports Reconciliation Equipment Name ^ Tag No. Seismic Cat. 1 ^ Type of Qual.

(Reference 6) Report (EQRR)

(Reference 2)*

WLS Auxiliary Building APP-JE52-VBR-002 / 2.3.10.05a.i-U3-Radiologically Controlled Area WLS-400A Yes Type Testing APP-JE52-VBR-001 EQRR-PCDXXX (RCA) Floodup Level Sensor WLS Auxiliary Building RCA APP-JE52-VBR-002 / 2.3.10.05a.i-U3-WLS-400B Yes Type Testing APP-JE52-VBR-001 EQRR-PCDXXX Floodup Level Sensor Notes:

+ Excerpt from COL Appendix C Table 2.3.10-1

• The Unit 4 As-Built EQRR are numbered "2.3.10.05a.i-U4-EQRR-PCDXXX"