ND-21-1023, ITAAC Closure Notification on Completion of ITAAC 2.3.05.02.i (Index Number 340)

ITAAC Closure Notification on Completion of ITAAC 2.3.05.02.i (Index Number 340)

ML22067A134
Person / Time
Site:	Vogtle
Issue date:	03/08/2022
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-1023
Download: ML22067A134 (1)

Text

Mich ael J. Yox 7825 River Road A Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel Docket Nos.: 52-025 MAR O*a 2022 ND-21-1023 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.05.02.i (Index Number 3401 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1 ), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP) Unit 3 Inspections, Tests , Analyses , and Acceptance Criteria (ITAAC) Item 2.3.05.02.i (Index Number 3401 to demonstrate that the Mechanical Handling System (MHS) equipment identified as seismic Category I in the Combined License (COL) Appendix C, Table 2.3.5-1 is designed and constructed in accordance with applicable requirements.

The closure process for this ITAAC is based on 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 .

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52 .99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted ,

~ I Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.05.02.i (Index Number 3401 MJY/BSZ/sfr

U.S. Nuclear Regulatory Co mmission ND-21-1023 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M . Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE : VND.LI.L06 File AR.01 .02 .06 Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coove rt Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelli Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-21-1023 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Mr. J. L. Coward Other Mr. S. W. Kline , Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton , Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-1023 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-21-1023 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.05.02.i [Index Number 340]

U.S. Nuclear Regulatory Commission ND-21-1023 Enclosure Page 2 of 6 IT AAC 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.

Inspections, Tests, Analyses:

i) Inspection will be performed to verify that the seismic Category I equipment 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 by the tested or analyzed conditions .

Acceptance Criteria:

i) The seismic Category I equipment identified in Table 2.3 .5-1 is located on the Nuclear Island.

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

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

ITAAC Determination Basis 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.

i) The seismic Category I equipment identified in Table 2.3.5-1 is located on the Nuclear Island.

To assure that seismic Category I equipment can withstand seismic design basis loads without loss of safety function , all the equipment in the Table is designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EQ) ITAAC As-built Walkdown Guideline and the EQ ITAAC As-built Installation Documentation Guideline (References 1 and 2) , an inspection was 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 EQ As-Built Reconciliation Reports (EQRR) (Reference 3) identified in Attachment A document the results of the inspection and concludes that the seismic Category I equipment is located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-21-1023 Enclosure Page 3 of 6 ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function .

Seismic Category I equipment components in the Table require type tests and/or analyses be performed to verify that the equipment can withstand seismic design basis loads without 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 of a heavy load in accordance with the American Society of Mechanical Engineers (ASM E) NOG-1-1998 (Reference 4) . 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 4 and the American Institute of Steel Construction (AISC) N690-1994 (Reference 5).

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 AP1000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6).

The EO Reports (References 7 through 12) are identified in Attachment A for the seismic Category I equipment and conclude that the equipment identified in Table 2.3.5-1 can withstand seismic design basis loads without loss of safety function.

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

An inspection (References 1 and 2) was 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/or sketches/drawings of equipment/mounting/interfaces.

As part of the seismic qualification program , consideration was given 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. Where required , seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports (References 7 through 12) 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 A identifies the EQRR (Reference 3) completed to verify that the as-built seismic Category I equipment listed in the Table , including anchorage, is seismically bounded by the tested or analyzed conditions.

U.S. Nuclear Regulatory Commission ND-21-1023 Enclosure Page 4 of 6 Together, these reports (References 3 and 7 through 12) 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 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 3 and 7 through 12 are available for NRC inspection as part of the Unit 3 ITAAC 2.3.05.02 .i Completion Package (References 13).

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.

IT AAC Completion Statement Based on the above information , SNC hereby notifies the NRC that ITAAC 2.3.05.02.i was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with the approved plant programs and procedures.

References (available for NRC inspection)

1. ND-RA-001-014 As-built Walkdown Guideline, Version 3.1

2. ND-RA-001-016, EQ ITAAC As-built Installation Documentation Guideline, Version 1.0

3. EQ As-Built Reconciliation Reports (EQRR) as identified in Attachment A for Unit 3

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

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

6. VEGP 3 UFSAR Appendix 3D, "Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment"

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

U.S. Nuclear Regulatory Commission ND-21-1023 Enclosure Page 5 of 6

8. CN-PAR-15-031 Revision 7, "AP1000 Polar Crane Mechanical Calculations"

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

10. CN-PAR-13-043 Revision 7, "AP1000 Cask Crane Mechanical Calculations"

11. APP-MH40-S2C-002 Revision 3, "AP1000 Hatch Hoist and Hoist Platform Structural Qualification"

12. CN-PAR-14-044 Revision 6, "Domestic AP1000 Hatch Hoists Mechanical Calculations"

13. 2.3.05.02.i-U3-CP-Rev0, "Completion Package for Unit 3 ITAAC 2.3.05.02.i [Index Number 340]"

U.S. Nuclear Regulatory Commission ND-21-1023 Enclosure Page 6 of 6 Attachment A System: Mechanical Handling System (MHS)

As-Built EQ Equipment Name Seismic Type of

+ Tag No.+ EQ Reports Reconciliation Cat. I+ Qual.

Report (EQRR)

Containment Polar MHS-MH-01 Yes Analysis APP-MH01-S2C-006 / 2.3.05.02.i-U3-EQRR-Crane CN-PAR-15-031 PCD001 Cask Handling MHS-MH-02 Yes Analysis APP-MH02-S2C-002 / 2.3.05.02.i-U3-EQRR-Crane CN-PAR-13-043 PCD001 Equipment Hatch MHS-MH-05 Yes Analysis APP-MH40-S2C-002 / 2.3.05.02.i-U3-EQRR-Hoist CN-PAR-14-044 PCD001 Maintenance MHS-MH-06 Yes Analysis APP-MH40-S2C-002 / 2.3.05.02.i-U3-EQRR-Hatch Hoist CN-PAR-14-044 PCD001

+ Excerpt from COL Appendix C Table 2.3.5-1