ND-21-0021, ITAAC Closure Notification on Completion of ITAAC 2.7.01.05.i (Index Number 684)

ITAAC Closure Notification on Completion of ITAAC 2.7.01.05.i (Index Number 684)

ML21027A405
Person / Time
Site:	Vogtle
Issue date:	01/27/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0021
Download: ML21027A405 (9)

Text

Michael J. Yox 7825 River Road Sk. Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-843-6459 tel JAN 2 7 2021 Docket No.: 52-025 ND-21-0021 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 2.7.01.05.i (Index Number 6841 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 2.7.01.05.1 [Index Number 684], This ITAAC confirms that the seismic Category I equipment identified in VEGP Combined Operating License (COL) Appendix C Table 2.7.1-1 for the Nuclear Island Nonradioactive Ventilation System (VBS)can withstand seismic design basis loads without loss of safety function. 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 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 Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox i Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.7.01.05.1 [Index Number 684]

MJY/DCM/sfr

U.S. Nuclear Regulatory Commission ND-21-0021 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

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

Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reouiatorv Commission Ms. M. Bailey (w/o enclosures)

M . M. King M . H. K. Nieh M . C. P. Patel M . G. J. Khouri M C. J. Even M B. J. Kemker Ms. N. C. Coovert M . C. Welch M . J. Gaslevic M O. Lopez-Santiago M G. Armstrong M M. Webb M T. Fredette M C. Santos M B. Davis M J. Vasquez M J. Eargle M E. Davidson M T. Fanelli M S. Rose Ms. K. McCurry

U.S. Nuclear Regulatory Commission ND-21-0021 Page 3 of 3 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse Eiectric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Mr. Z. S. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, 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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-21-0021 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-21-0021 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.7.01.05.i [Index Number 684]

U.S. Nuclear Regulatory Commission ND-21-0021 Enclosure Page 2 of 6 ITAAC Statement Design Commitment

5. The seismic Category I equipment identified in Table 2.7.1-1 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 2.7.1-1 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 I equipment identified in Table 2.7.1-1 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 Nuclear Island Nonradioactive Ventilation System (VBS)equipment identified as seismic Category I in the Combined License(COL)Appendix C, Table 2.7.1-1 was designed and constructed in accordance with applicable requirements.

i) The seismic Category I equipment identified in Table 2.7.1-1 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 Table 2.7.1-1 was designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EQ)ITAAC As-Built Walkdown Guideline (Reference 1) and EQ ITAAC As-built Installation Documentation Guideline (Reference 2), inspections were conducted of the VBS to confirm the satisfactory installation of the seismically qualified equipment. The inspections included verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). The EQ As-Built Reconciliation Reports(EQRRs)(Reference 3) identified in Attachment A document the results of the inspections and conclude that the seismic Category I equipment is located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-21-0021 Enclosure Page 3 of6 in A report exists and concludes that the seismic Category I eauloment can withstand seismic design basis loads without loss of safety function.

Seismic Category I equipment in Table 2.7.1-1 required type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves was demonstrated by analysis in accordance with American Society of Mechanical Engineers(ASME)Code Section III (Reference 4). Functionality of the subset of active safety-related valves under seismic loads was determined using the guidance of ASME QME-1-2007 (Reference 5).

Safety-related (Class IE) electrical equipment in Table 2.7.1-1 is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers(IEEE) Standard 344-1987(Reference 6). This equipment includes safety-related active valve accessories such as electric actuators, position switches, pilot solenoid valves and electrical connector assemblies.

The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment in Table 2.7.1-1 is identified in Attachment A. Additional information about the methods used to qualify API000 safety-related equipment is provided in the Updated Final Safety Analysis Report(UFSAR) Appendix 3D (Reference 7). The EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and conclude 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 seismicallv bounded bv the tested or analyzed conditions.

Inspections(Reference 1 and Reference 2) were conducted to confirm the satisfactory installation of the seismically qualified equipment in Table 2.7.1-1. The inspections verified 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. When required, seismic testing measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports(Reference 8) 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 were defined based on the test configuration and/or other design requirements.

Attachment A identifies the EQRR (Reference 3) completed to verify that the as-built seismic Category I equipment listed in Table 2.7.1-1, including anchorage, is seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987(References), and NRG Regulatory Guide 1.100(Reference 9).

U.S. Nuclear Regulatory Commission ND-21-0021 Enclosure Page 4 of6 Together, these reports (References 3 and 8) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 2.7.1-1 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 8 are available for NRC inspection as part of the Unit 3 ITAAC 2.7.01.05.1 Completion Package (Reference 10).

ITAAC Finding Review 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 Index Numbers 685 and 686,found the following relevant ITAAC finding associated with this ITAAC.

1. NGN 99901412/2012-201-02(Closed)

ITAAC Compietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.7.01.05.1 was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

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

References (available for NRC inspection)

1. ND-RA-001-014,"EQ ITAAC 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

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

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

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

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

7. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D,"Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment", Revision 9.1

8. Equipment Qualification (EQ) Reports as identified in Attachment A

U.S. Nuclear Regulatory Commission ND-21-0021 Enclosure Page 5 of 6

9. Regulatory Guide 1.100, Rev. 2,"Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants" 10.2.7.01.05.i-U3-CP-Rev 0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-21-0021 Enclosure Page 6 of 6 Attachment A System: Nuclear Island Nonradioactive Ventilation System Equipment Tag No.+ Seismic Type of EQ Reports As-Buiit EQRR Name+ Cat. 1+ Quai. (Reference 8) (Reference 3)

MCR Supply Type Test SV3-PV11-VBR-006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V186* Yes

& Analysis SV3-PV11-VBR-005 PCD002-Rev 0 Valve MCR Supply Type Test SV3-PV11-VBR-006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V187* Yes

& Analysis SV3-PV11-VBR-005 PCD002-Rev 0 Valve MCR Return Type Test SV3-PV11-VBR-006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V188* Yes &Analysis SV3-PV11-VBR-005 PCD005-Rev 0 Valve MCR Return Type Test SV3-PV11-VBR-006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V189* Yes & Analysis SV3-PV11-VBR-005 PCD005-Rev 0 Valve MCR Exhaust Type Test SV3-PV11-VBR-006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V190* Yes & Analysis SV3-PV11-VBR-005 PCD006-Rev 0 Valve MCR Exhaust Type Test SV3-PV11-VBR-006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V191* Yes & Analysis SV3-PV11-VBR-005 PCD006-Rev 0 Valve PWS MCR Type Test SV3-PV02-VBR-010 / 2.7.01.05.i-U3-EQRR-Isolation Valve PWS-PL-V418 Yes & Analysis SV3-PV02-VBR-009 PCD003-Rev 0 PWS MCR Type Test SV3-PV02-VBR-010/ 2.7.01.05.i-U3-EQRR-PWS-PL-V420 Yes Isolation Valve & Analysis SV3-PV02-VBR-009 PCD003-Rev 0 PWS MCR Type Test SV3-PV18-VBR-002 2.7.01.05.i-U3-EQRR-PWS-PL-V498 Yes Vacuum Relief & Analysis /SV3-PV18-VBR 001 PCD004-Rev 0 MCR SDS Type Test SV3-PV11-VBR-006 2.7.01.05.i-U3-EQRR-(Vent) SDS-PL-VOOr Yes

&Analysis /SV3-PV11-VBR-005 PCD006-Rev 0 Isolation Valve MCR SDS Type Test SV3-PV11-VBR-006/ 2.7.01.05.i-U3-EQRR-(Vent) SDS-PL-V002* Yes SAnalysis SV3-PV11-VBR-005 PCD006-Rev 0 Isolation Valve MCR WWS SV3-PV03-VBR- 006 / 2.7.01.05.i-U3-EQRR-WWS-PL-V506 Isolation Valve Yes Analysis SV3-PV03-VBR-005 PCDOOI-RevO

+ Excerpt from COL Appendix C, Table 2.7.1-1

• Indicates IE component, per Table 2.7.1-1 Attachment A Page 1 of 1