ND-23-0071, ITAAC Closure Notification on Completion of Item 2.2.05.05a.i (Index Number 259)

ITAAC Closure Notification on Completion of Item 2.2.05.05a.i (Index Number 259)

ML23048A275
Person / Time
Site:	Vogtle
Issue date:	02/17/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0071
Download: ML23048A275 (1)

Text

Jamie M Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel February 17, 2023 Docket No.: 52-026 ND-23-0071 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 4 ITAAC Closure Notification on Completion of Item 2.2.05.05a.i [Index Number 259]

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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.05.05a.i [Index Number 259] to demonstrate that the Main Control Room Emergency Habitability System (VES) components identified as seismic Category I in the Combined License (COL) Appendix C, Table 2.2.5-1 are 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, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.05.05a.i [Index Number 259]

JMC/AD/sfr

U.S. Nuclear Regulatory Commission ND-23-0071 Page 2 of 2 cc: Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-23-0071 Page 1 of 9 Southern Nuclear Operating Company ND-23-0071 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.05.05a.i [Index Number 259]

U.S. Nuclear Regulatory Commission ND-23-0071 Page 2 of 9 ITAAC Statement Design Commitment:

5.a) The seismic Category I equipment identified in Table 2.2.5-1 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 and valves identified in Table 2.2.5-1 are 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 2.2.5-1 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 Main Control Room Emergency Habitability System (VES) equipment identified as seismic Category I in the Combined License (COL) Appendix C, Table 2.2.5-1 (the Table) is designed and constructed in accordance with applicable requirements.

i) The seismic Category I equipment identified in Table 2.2.5-1 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 of 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 VES 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 (EQRRs) (Reference 3) 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-23-0071 Page 3 of 9 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 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 components, is 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 is determined using the guidance of ASME QME-1-2007 (Reference 5).

Safety-related (Class 1E) electrical equipment in the Table is seismically qualified by type testing, analysis, or a combination of type tests and analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 6). This equipment includes safety-related (Class 1E) field sensors and the 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 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 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 seismically bounded by the tested or analyzed conditions.

An inspection 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 is 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 by 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 are defined based on the test configuration and other design requirements.

Attachment A identifies the EQRRs (Reference 3) completed to verify that the as-built seismic Category I equipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 6), and NRC Regulatory Guide 1.100 (Reference 9).

U.S. Nuclear Regulatory Commission ND-23-0071 Page 4 of 9 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 2.2.5-1 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 8 are available for NRC inspection as part of the Unit 4 ITAAC 2.2.05.05a.i 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 Indexes 260 and 261, found the following relevant ITAAC findings associated with this ITAAC:

Notice of Nonconformance 99901412/2012-201-02 (Closed - ML18152B785)

The corrective actions for this finding have been completed and the finding is closed. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.05.05a.i (Reference 10) and is available for NRC review ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.05.05a.i was performed for VEGP Unit 4 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 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. As-Built EQ Reconciliation Reports (EQRRs) as identified in Attachment A for Unit 4

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

U.S. Nuclear Regulatory Commission ND-23-0071 Page 5 of 9

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 AP1000 Safety-Related Electrical and Mechanical Equipment Revision 11.1

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

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

10. 2.2.05.05a.i-U4-CP-Rev0, Completion Package for Unit 4 ITAAC 2.2.05.05a.i [Index Number 259]

U.S. Nuclear Regulatory Commission ND-23-0071 Page 6 of 9 Attachment A System: Main Control Room Emergency Habitability System Seismic Type of Equipment Name + Tag No. + EQ Reports As-Built EQRR Cat. I + Qual.

MCR Load Shed Type SV4-EP10-VBR-003 / 2.2.05.05a.i-U4-VES-EP-01 Yes Panel 1 Testing SV4-EP10-VBR-004 EQRR-PCD002 MCR Load Shed Type SV4-EP10-VBR-003 / 2.2.05.05a.i-U4-VES-EP-02 Yes Panel 2 Testing SV4-EP10-VBR-004 EQRR-PCD002 Emergency Air 2.2.05.05a.i-U4-VES-MT-01 Yes Analysis APP-MS23-VDR-001 Storage Tank 01 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-02 Yes Analysis APP-MS23-VDR-001 Storage Tank 02 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-03 Yes Analysis APP-MS23-VDR-001 Storage Tank 03 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-04 Yes Analysis APP-MS23-VDR-001 Storage Tank 04 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-05 Yes Analysis APP-MS23-VDR-001 Storage Tank 05 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-06 Yes Analysis APP-MS23-VDR-001 Storage Tank 06 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-07 Yes Analysis APP-MS23-VDR-001 Storage Tank 07 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-08 Yes Analysis APP-MS23-VDR-001 Storage Tank 08 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-09 Yes Analysis APP-MS23-VDR-001 Storage Tank 09 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-10 Yes Analysis APP-MS23-VDR-001 Storage Tank 10 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-11 Yes Analysis APP-MS23-VDR-001 Storage Tank 11 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-12 Yes Analysis APP-MS23-VDR-001 Storage Tank 12 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-13 Yes Analysis APP-MS23-VDR-001 Storage Tank 13 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-14 Yes Analysis APP-MS23-VDR-001 Storage Tank 14 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-15 Yes Analysis APP-MS23-VDR-001 Storage Tank 15 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-16 Yes Analysis APP-MS23-VDR-001 Storage Tank 16 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-17 Yes Analysis APP-MS23-VDR-001 Storage Tank 17 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-18 Yes Analysis APP-MS23-VDR-001 Storage Tank 18 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-19 Yes Analysis APP-MS23-VDR-001 Storage Tank 19 EQRR-PCD003

U.S. Nuclear Regulatory Commission ND-23-0071 Page 7 of 9 Seismic Type of Equipment Name + Tag No. + EQ Reports As-Built EQRR Cat. I + Qual.

Emergency Air 2.2.05.05a.i-U4-VES-MT-20 Yes Analysis APP-MS23-VDR-001 Storage Tank 20 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-21 Yes Analysis APP-MS23-VDR-001 Storage Tank 21 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-22 Yes Analysis APP-MS23-VDR-001 Storage Tank 22 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-23 Yes Analysis APP-MS23-VDR-001 Storage Tank 23 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-24 Yes Analysis APP-MS23-VDR-001 Storage Tank 24 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-25 Yes Analysis APP-MS23-VDR-001 Storage Tank 25 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-26 Yes Analysis APP-MS23-VDR-001 Storage Tank 26 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-27 Yes Analysis APP-MS23-VDR-001 Storage Tank 27 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-28 Yes Analysis APP-MS23-VDR-001 Storage Tank 28 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-29 Yes Analysis APP-MS23-VDR-001 Storage Tank 29 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-30 Yes Analysis APP-MS23-VDR-001 Storage Tank 30 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-31 Yes Analysis APP-MS23-VDR-001 Storage Tank 31 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U4-VES-MT-32 Yes Analysis APP-MS23-VDR-001 Storage Tank 32 EQRR-PCD003 Type Air Delivery Alternate VES-PL- SV4-PV02-VBR-010 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve V001 SV4-PV02-VBR-009 EQRR-PCD001 Analysis Type Eductor Flow Path VES-PL- SV4-PV02-VBR-010 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve V045 SV4-PV02-VBR-009 EQRR-PCD001 Analysis Type Eductor Bypass VES-PL- SV4-PV02-VBR-010 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve V046 SV4-PV02-VBR-009 EQRR-PCD001 Analysis Type Pressure Regulating VES-PL- SV4-PV15-VBR-002 / 2.2.05.05a.i-U4-Yes Testing &

Valve A V002A SV4-PV15-VBR-001 EQRR-PCD001 Analysis Type Pressure Regulating VES-PL- SV4-PV15-VBR-002 / 2.2.05.05a.i-U4-Yes Testing &

Valve B V002B SV4-PV15-VBR-001 EQRR-PCD001 Analysis Type MCR Air Delivery VES-PL- SV4-PV13-VBR-012 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve A V005A SV4-PV13-VBR-011 EQRR-PCD001 Analysis Type MCR Air Delivery VES-PL- SV4-PV13-VBR-012 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve B V005B SV4-PV13-VBR-011 EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-23-0071 Page 8 of 9 Seismic Type of Equipment Name + Tag No. + EQ Reports As-Built EQRR Cat. I + Qual.

Type Temporary Instrument VES-PL- SV4-PV02-VBR-010 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve A V018 SV4-PV02-VBR-009 EQRR-PCD001 Analysis Type Temporary Instrument VES-PL- SV4-PV02-VBR-010 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve B V019 SV4-PV02-VBR-009 EQRR-PCD001 Analysis Type MCR Pressure Relief VES-PL- SV4-PV11-VBR-004 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve A V022A SV4-PV11-VBR-003 EQRR-PCD001 Analysis Type MCR Pressure Relief VES-PL- SV4-PV11-VBR-004 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve B V022B SV4-PV11-VBR-003 EQRR-PCD001 Analysis Type Air Tank Safety Relief VES-PL- SV4-PV16-VBR-002 / 2.2.05.05a.i-U4-Yes Testing &

Valve A V040A SV4-PV16-VBR-001 EQRR-PCD001 Analysis Type Air Tank Safety Relief VES-PL- SV4-PV16-VBR-002 / 2.2.05.05a.i-U4-Yes Testing &

Valve B V040B SV4-PV16-VBR-001 EQRR-PCD001 Analysis Type Air Tank Safety Relief VES-PL- SV4-PV16-VBR-002 / 2.2.05.05a.i-U4-Yes Testing &

Valve C V040C SV4-PV16-VBR-001 EQRR-PCD001 Analysis Type Air Tank Safety Relief VES-PL- SV4-PV16-VBR-002 / 2.2.05.05a.i-U4-Yes Testing &

Valve D V040D SV4-PV16-VBR-001 EQRR-PCD001 Analysis Type Main Air Flow Path VES-PL- SV4-PV02-VBR-010 / 2.2.05.05a.i-U4-Yes Testing &

Isolation Valve V044 SV4-PV02-VBR-009 EQRR-PCD001 Analysis MCR Air Filtration Line 2.2.05.05a.i-U4-VES-PY-N01 Yes Analysis SV4-PY82-VDR-001 Eductor EQRR-PCD002 MCR Air Filtration Line 2.2.05.05a.i-U4-VES-MY-F01 Yes Analysis SV4-MS59-VDR-001 Charcoal Filter EQRR-PCD002 MCR Air Filtration Line 2.2.05.05a.i-U4-VES-MY-F02 Yes Analysis SV4-MS59-VDR-001 HEPA Filter EQRR-PCD002 MCR Air Filtration Line 2.2.05.05a.i-U4-VES-MY-F03 Yes Analysis SV4-MS59-VDR-001 Postfilter EQRR-PCD002 MCR Gravity Relief VES-MD- 2.2.05.05a.i-U4-Yes Analysis SV4-MD27-VGC-850000 Dampers D001A EQRR-PCD002 MCR Gravity Relief VES-MD- 2.2.05.05a.i-U4-Yes Analysis SV4-MD27-VGC-850000 Dampers D001B EQRR-PCD002 MCR Air Filtration Line VES-MD- 2.2.05.05a.i-U4-Yes Analysis SV4-MD30-VDR-001 Supply Damper D002 EQRR-PCD002 MCR Air Filtration Line VES-MD- 2.2.05.05a.i-U4-Yes Analysis SV4-MD30-VDR-001 Supply Damper D003 EQRR-PCD002 MCR Air Filtration Line 2.2.05.05a.i-U4-VES-MY-Y01 Yes Analysis SV4-MY71-VDR-001 Silencer EQRR-PCD002 MCR Air Filtration Line 2.2.05.05a.i-U4-VES-MY-Y02 Yes Analysis SV4-MY71-VDR-001 Silencer EQRR-PCD002

U.S. Nuclear Regulatory Commission ND-23-0071 Page 9 of 9 Seismic Type of Equipment Name + Tag No. + EQ Reports As-Built EQRR Cat. I + Qual.

Type MCR Air Delivery Line SV4-JE54-VBR-002 / 2.2.05.05a.i-U4-VES-003A Yes Testing &

Flow Sensor SV4-JE54-VBR-001 EQRR-PCD002 Analysis Type MCR Air Delivery Line SV4-JE54-VBR-002 / 2.2.05.05a.i-U4-VES-003B Yes Testing &

Flow Sensor SV4-JE54-VBR-001 EQRR-PCD002 Analysis Type MCR Differential SV4-JE52-VBR-006 / 2.2.05.05a.i-U4-VES-004A Yes Testing &

Pressure Sensor A SV4-JE52-VBR-005 EQRR-PCD002 Analysis Type MCR Differential SV4-JE52-VBR-006 / 2.2.05.05a.i-U4-VES-004B Yes Testing &

Pressure Sensor B SV4-JE52-VBR-005 EQRR-PCD002 Analysis Type 2.2.05.05a.i-U4-MCR Filter Shielding 12401-NS-01 Yes Testing & SV4-MS59-VDR-001 EQRR-PCD002 Analysis

+ Excerpt from COL Appendix C Table 2.2.5-1