ND-23-0071, 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 Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 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)
- 3. As-Built EQ Reconciliation Reports (EQRRs) as identified in Attachment A for Unit 4
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 Equipment Name +
Tag No. +
Seismic Cat. I +
Type of Qual.
EQ Reports As-Built EQRR MCR Load Shed Panel 1 VES-EP-01 Yes Type Testing SV4-EP10-VBR-003 /
SV4-EP10-VBR-004 2.2.05.05a.i-U4-EQRR-PCD002 MCR Load Shed Panel 2 VES-EP-02 Yes Type Testing SV4-EP10-VBR-003 /
SV4-EP10-VBR-004 2.2.05.05a.i-U4-EQRR-PCD002 Emergency Air Storage Tank 01 VES-MT-01 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 02 VES-MT-02 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 03 VES-MT-03 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 04 VES-MT-04 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 05 VES-MT-05 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 06 VES-MT-06 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 07 VES-MT-07 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 08 VES-MT-08 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 09 VES-MT-09 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 10 VES-MT-10 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 11 VES-MT-11 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 12 VES-MT-12 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 13 VES-MT-13 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 14 VES-MT-14 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 15 VES-MT-15 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 16 VES-MT-16 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 17 VES-MT-17 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 18 VES-MT-18 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 19 VES-MT-19 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003
U.S. Nuclear Regulatory Commission ND-23-0071 Page 7 of 9 Equipment Name +
Tag No. +
Seismic Cat. I +
Type of Qual.
EQ Reports As-Built EQRR Emergency Air Storage Tank 20 VES-MT-20 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 21 VES-MT-21 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 22 VES-MT-22 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 23 VES-MT-23 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 24 VES-MT-24 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 25 VES-MT-25 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 26 VES-MT-26 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 27 VES-MT-27 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 28 VES-MT-28 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 29 VES-MT-29 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 30 VES-MT-30 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 31 VES-MT-31 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Emergency Air Storage Tank 32 VES-MT-32 Yes Analysis APP-MS23-VDR-001 2.2.05.05a.i-U4-EQRR-PCD003 Air Delivery Alternate Isolation Valve VES-PL-V001 Yes Type Testing &
Analysis SV4-PV02-VBR-010 /
SV4-PV02-VBR-009 2.2.05.05a.i-U4-EQRR-PCD001 Eductor Flow Path Isolation Valve VES-PL-V045 Yes Type Testing &
Analysis SV4-PV02-VBR-010 /
SV4-PV02-VBR-009 2.2.05.05a.i-U4-EQRR-PCD001 Eductor Bypass Isolation Valve VES-PL-V046 Yes Type Testing &
Analysis SV4-PV02-VBR-010 /
SV4-PV02-VBR-009 2.2.05.05a.i-U4-EQRR-PCD001 Pressure Regulating Valve A VES-PL-V002A Yes Type Testing &
Analysis SV4-PV15-VBR-002 /
SV4-PV15-VBR-001 2.2.05.05a.i-U4-EQRR-PCD001 Pressure Regulating Valve B VES-PL-V002B Yes Type Testing &
Analysis SV4-PV15-VBR-002 /
SV4-PV15-VBR-001 2.2.05.05a.i-U4-EQRR-PCD001 MCR Air Delivery Isolation Valve A VES-PL-V005A Yes Type Testing &
Analysis SV4-PV13-VBR-012 /
SV4-PV13-VBR-011 2.2.05.05a.i-U4-EQRR-PCD001 MCR Air Delivery Isolation Valve B VES-PL-V005B Yes Type Testing &
Analysis SV4-PV13-VBR-012 /
SV4-PV13-VBR-011 2.2.05.05a.i-U4-EQRR-PCD001
U.S. Nuclear Regulatory Commission ND-23-0071 Page 8 of 9 Equipment Name +
Tag No. +
Seismic Cat. I +
Type of Qual.
EQ Reports As-Built EQRR Temporary Instrument Isolation Valve A VES-PL-V018 Yes Type Testing &
Analysis SV4-PV02-VBR-010 /
SV4-PV02-VBR-009 2.2.05.05a.i-U4-EQRR-PCD001 Temporary Instrument Isolation Valve B VES-PL-V019 Yes Type Testing &
Analysis SV4-PV02-VBR-010 /
SV4-PV02-VBR-009 2.2.05.05a.i-U4-EQRR-PCD001 MCR Pressure Relief Isolation Valve A VES-PL-V022A Yes Type Testing &
Analysis SV4-PV11-VBR-004 /
SV4-PV11-VBR-003 2.2.05.05a.i-U4-EQRR-PCD001 MCR Pressure Relief Isolation Valve B VES-PL-V022B Yes Type Testing &
Analysis SV4-PV11-VBR-004 /
SV4-PV11-VBR-003 2.2.05.05a.i-U4-EQRR-PCD001 Air Tank Safety Relief Valve A VES-PL-V040A Yes Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.05.05a.i-U4-EQRR-PCD001 Air Tank Safety Relief Valve B VES-PL-V040B Yes Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.05.05a.i-U4-EQRR-PCD001 Air Tank Safety Relief Valve C VES-PL-V040C Yes Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.05.05a.i-U4-EQRR-PCD001 Air Tank Safety Relief Valve D VES-PL-V040D Yes Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.05.05a.i-U4-EQRR-PCD001 Main Air Flow Path Isolation Valve VES-PL-V044 Yes Type Testing &
Analysis SV4-PV02-VBR-010 /
SV4-PV02-VBR-009 2.2.05.05a.i-U4-EQRR-PCD001 MCR Air Filtration Line Eductor VES-PY-N01 Yes Analysis SV4-PY82-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Filtration Line Charcoal Filter VES-MY-F01 Yes Analysis SV4-MS59-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Filtration Line HEPA Filter VES-MY-F02 Yes Analysis SV4-MS59-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Filtration Line Postfilter VES-MY-F03 Yes Analysis SV4-MS59-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Gravity Relief Dampers VES-MD-D001A Yes Analysis SV4-MD27-VGC-850000 2.2.05.05a.i-U4-EQRR-PCD002 MCR Gravity Relief Dampers VES-MD-D001B Yes Analysis SV4-MD27-VGC-850000 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Filtration Line Supply Damper VES-MD-D002 Yes Analysis SV4-MD30-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Filtration Line Supply Damper VES-MD-D003 Yes Analysis SV4-MD30-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Filtration Line Silencer VES-MY-Y01 Yes Analysis SV4-MY71-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Filtration Line Silencer VES-MY-Y02 Yes Analysis SV4-MY71-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002
U.S. Nuclear Regulatory Commission ND-23-0071 Page 9 of 9 Equipment Name +
Tag No. +
Seismic Cat. I +
Type of Qual.
EQ Reports As-Built EQRR MCR Air Delivery Line Flow Sensor VES-003A Yes Type Testing &
Analysis SV4-JE54-VBR-002 /
SV4-JE54-VBR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Air Delivery Line Flow Sensor VES-003B Yes Type Testing &
Analysis SV4-JE54-VBR-002 /
SV4-JE54-VBR-001 2.2.05.05a.i-U4-EQRR-PCD002 MCR Differential Pressure Sensor A VES-004A Yes Type Testing &
Analysis SV4-JE52-VBR-006 /
SV4-JE52-VBR-005 2.2.05.05a.i-U4-EQRR-PCD002 MCR Differential Pressure Sensor B VES-004B Yes Type Testing &
Analysis SV4-JE52-VBR-006 /
SV4-JE52-VBR-005 2.2.05.05a.i-U4-EQRR-PCD002 MCR Filter Shielding 12401-NS-01 Yes Type Testing &
Analysis SV4-MS59-VDR-001 2.2.05.05a.i-U4-EQRR-PCD002
+ Excerpt from COL Appendix C Table 2.2.5-1