ND-18-0270, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.05.02.i (Index Number 340)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.05.02.i (Index Number 340)

ML18060A011
Person / Time
Site:	Vogtle
Issue date:	02/28/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.3.05.02.i, ND-18-0270
Download: ML18060A011 (10)

Text

Michael J. Yox 7825 River Road NLICl03r Regulatory Affairs Director Vogtle3 &4 Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com FEB 2 8 2018 Docket Nos.: 52-025 52-026 ND-18-0270 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 2.3.05.02.1 [Index Number 3401 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 22, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.05.02.1 [Index Number 340] 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.

MichaelJ. Yox Regulatory Affairs Director Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-18-0270 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.05.02.1 [Index Number 340]

MJY/RAS/amw

U.S. Nuclear Regulatory Commission ND-18-0270 Page 3 of 4 To:

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

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

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

M D. L. McKinney M M. J. Yox M D. L. Fulton M . J. D. Williams M F. H. Willis Ms. A. L. Pugh M A. 8. Parton M W. A. Sparkman M *. 0. E. Morrow Ms. K. M. Stacy M. K. Washington

. J. P. Redd Ms. A. 0. Chamberlain M D. R. Culver M 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 Ooiethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0270 Page 4 of 4 Palton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Orlani (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. Deangelis Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Mails, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Sen/Ice Commission Ms. 8. W. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-0270 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-18-0270 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.05.02.1 [Index Number 340]

U.S. Nuclear Regulatory Commission ND-18-0270 Enclosure Page 2 of 6 ITAAC Statement Design Commitment:

2. The seismic Category I equipment identified in Table 2.3.5-1 can withstand seismic design basis loads without loss of safety function.

Insoections. Tests. Analyses:

i) Inspection will be performed to verify thcit the seismic Category Iequipment identified in Table 2.3.5-1 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.

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

Acceptance Criteria:

i) The seismic Category Iequipment identified in Table 2.3.5-1 islocated 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 is seismically 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 Mechanical Handling System (MHS) equipment identified as seismic Category I in the Combined License (COL) Appendix C, Table 2.3.5-1 (the Table) is designed and constructed in accordance with applicable requirements.

ii The seismic Cateoorv I eouioment identified in Table 2.3.5-1 is located on the Nuclear Island.

Toassure thatseismic Category Iequipment can withstand seismic design basis loads without loss of safety function, all the equipment in theTable is designed to be located on theseismic Category INuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the MHS to confirm the satisfactory installation of the seismically qualified equipment. 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 I equipment is located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-18-0270 Enclosure Page 3 of 6 ID A report exists and concludes that the seismic Cateoorv I eouioment can withstand seismic design basis loads without loss of safety function.

Seismic Category I equipmentcomponents in the Table requiretype tests and/or analyses be performed to verify thatthe equipment can withstand seismic design basis loadswithout loss of safety function.

The Containment Polar Crane and Cask Handling Crane were modeled and qualified using structural stress analyses of dynamic and gravity loads to demonstrate structural integrity to support the safety function, which is prevention of uncontrolled lowering ofa heavy load in accordance with the American Society of Mechanical Engineers (ASME) NOG-1-1998 (Reference 3). The Hatch Hoists were modeled and qualified using structural stress analyses of all dynamic and gravity loads to demonstrate structural integrity, to support the safety function which is prevention of uncontrolled lowering of a heavy load in accordance with Reference 3 and the American Institute of Steel Construction (AISG) N690-1994 (Reference 4).

The specific qualification method (i.e., type testing, analysis, orcombination) used for each piece of equipment 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 (References 6 through 11) are identified in Attachment Afor the seismic Category Iequipment and conclude that the equipment identified in Table 2.3.5-1 can withstand seismic design basis loads without loss of safety function.

iiil A report exists and concludes that the as-built eouioment including anchorage is seismicallv bounded bv the tested or analvzed conditions.

An inspection (Reference 1) isconducted 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/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 plantto 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 top and bottom of the equipment. EQ Reports (Reference 6 through 11) 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 other design requirements.

Attachment Aidentifies the EQRR (Reference 2) completed to verify that the as-built seismic Category Iequipment listed in the Table, including anchorage, is seismically bounded by the tested oranalyzed conditions and NRC Regulatory Guide 1.100, Rev. 2 (Reference 12).

U.S. Nuclear Regulatory Commission ND-18-0270 Enclosure Page 4 of 6 Together, these reports (References 2 and 6 through 11) provide evidence that the ITAAC Acceptance Criteria requirements are met.

• The seismic Category I equipment identified in Table 2.3.5-1 is located on the Nuclear Island;

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

• A report existsand concludes that the as-built equipment including anchorage is seismicallybounded by the tested or analyzed conditions.

References 2 and 6 through 11 are available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.3.05.02.i Completion Packages (References 13 and 14, 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 and associated corrective actions.

This review, which included now consolidated ITAAC Indexes 341 and 342, found no relevant ITAAC findings associated with this ITAAC.

References favaiiable for NRC inspection)

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

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

3. ASME NGG-1 -1998, "Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder)"

4. AISC N690-1994, "Specification for Safety-Related Steel Structures for Nuclear Facilities"

5. VEGP 3&4 UFSAR Appendix 3D, "Methodology for Qualifying API 000 Safety-Related Electrical and Mechanical Equipment"

6. APP-MH01-S2C-006 Revision 2, "PolarCrane Structural Qualification and Bridge Crane Wheel Forces"

7. CN-PAR-15-031 Revision 7, "API000 Polar Crane Mechanical Calculations"

8. APP-MH02-S2C-002 Revision 1, "Cask Handling Crane Structural Qualification and Bridge Crane Wheel Forces"

9. CN-PAR-13-043 Revision 7, "API 000 Cask Crane Mechanical Calculations"

10. APP-MH40-S2C-002 Revision 3, "API 000 Hatch Hoist and Hoist Platform Structural Qualification"

U.S. Nuclear Regulatory Commission ND-18-0270 Enclosure Page 5 of 6

11. CN-PAR-14-044 Revision 6, "Domestic API 000 Hatch Hoists Mechanical Calculations"

12. Regulatory Guide 1.100, Rev. 2, "SeismicQualification of Electric and Mechanical Equipment for Nuclear Power Plants" 13.2.3.05.02.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.3.05.02.i [Index Number 340]"

14.2.3.05.02.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.3.05.02.1 [Index Number 340]"

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

U.S. Nuclear Regulatory Commission ND-18-0270 Enclosure Page 6 of 6 Attachment A System: Mechanical Handling System (MHS)

As-Bullt EQ EQ Reports Equipment Name Seismic Type of Reconciliation Tag No. + (References 6

+

Cat. 1

• Qua!. Report (EQRR) through 11)

(Reference 2)*

Containment Polar MHS-MH-01 Yes Analysis APP-MH01-S2C-006/ 2.3.05.02.i-U3-EQRR-Crane CN-PAR-15-031 PCDXXX Cask Handling MHS-MH-02 Yes Analysis APP-MH02-S2C-002 / 2.3.05.02.i-U3-EQRR-Crane CN-PAR-13-043 PCDXXX Equipment Hatch MHS-MH-05 Yes Analysis APP-MH40-S2C-002 / 2.3.05.02.i-U3-EQRR-Hoist CN-PAR-14-044 PCDXXX Maintenance MHS-MH-06 Yes Analysis APP-MH40-S2C-002 / 2.3.05.02.i-U3-EQRR-Hatch Hoist CN-PAR-14-044 PCDXXX

+ Excerpt from COL Appendix C Table 2.3.5-1

• The Unit 4 As-Built EQRR are numbered "2.3.05.02.i-U4-EQRR-PCDXXX-Rev 0"