ND-21-1035, Vogtie Electric Generating Plant Unit 3 - ITAAC Closure Notification on Completion of Item 2.2.05.05a.I (Index Number 259)

Vogtie Electric Generating Plant Unit 3 - ITAAC Closure Notification on Completion of Item 2.2.05.05a.I (Index Number 259)

ML22102A326
Person / Time
Site:	Vogtle
Issue date:	04/07/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.205.05a, ND-21-1035
Download: ML22102A326 (12)

Text

Jamie M Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Southern Nuclear Vogtie 3 & 4 706-848-6426 tel Docket No.: 52-025 APR 0 7 2022 ND-21-1035 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of Item 2.2.05.05a.I [Index Number 2591 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 Vogtie Electric Generating Plant(VEGP)

Unit 3 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 U

Jamie M. Coleman Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.05.05a.i [Index Number 259]

JMC/BSZ/sfr

U.S. Nuclear Regulatory Commission ND-21-1035 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J. B. Williams 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 cc:

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. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. 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-21-1035 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 Ms. S. L. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS 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-21-1035 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-21-1035 Enclosure Vogtie Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.05.05a.i [Index Number 259]

U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure 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.

lii) 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 Waikdown 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(EQRR)(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-21-1035 Enclosure 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 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 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 EQRR (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-21-1035 Enclosure 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 3 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 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 Waikdown 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(EQRR)as identified in Attachment A for Units 3

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-21-1035 Enclosure 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. Vogtie 3&4 Updated Final Safety Analysis Report Appendix 3D,Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment

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-U3-CP-Rev0, Completion Package for Unit 3 ITAAC 2.2.05.05a.i [Index Number 259]

U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure Page 6 of 9 Attachment A System: Main Control Room Emergency Habitability System Seismic Type of Equipment Name Tag No. ^ Cat. I ^ Qual. EQ Reports) As-Built EQRR MCR Load Shed Type APP-EP10-VBR-003/ 2.2.05.05a.i-U3-VES-EP-01 Yes Panel 1 Testing APP-EP10-VBR-004 EQRR-PCD002 MCR Load Shed Type APP-EP10-VBR-003/ 2.2.05.05a.i-U3-VES-EP-02 Yes Panel 2 Testing APP-EP10-VBR-004 EQRR-PCD002 Emergency Air VES-MT-01 Yes 2.2.05.05a.i-U3-Analysis APP-MS23-VDR-001 Storage Tank 01 EQRR-PCD003 Emergency Air VES-MT-02 2.2.05.05a.i-U3-Yes Analysis APP-MS23-VDR-001 Storage Tank 02 EQRR-PCD003 Emergency Air VES-MT-03 Yes 2.2.05.05a.i-U3-Analysis APP-MS23-VDR-001 Storage Tank 03 EQRR-PCD003 Emergency Air VES-MT-04 Yes 2.2.05.05a.i-U3-Analysis APP-MS23-VDR-001 Storage Tank 04 EQRR-PCD003 Emergency Air VES-MT-05 2.2.05.05a.i-U3-Yes Analysis APP-MS23-VDR-001 Storage Tank 05 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-06 Yes Analysis APP-MS23-VDR-001 Storage Tank 06 EQRR-PCD003 Emergency Air VES-MT-07 2.2.05.05a.i-U3-Yes Analysis APP-MS23-VDR-001 Storage Tank 07 EQRR-PCD003 Emergency Air VES-MT-08 2.2.05.05a.i-U3-Yes Analysis APP-MS23-VDR-001 Storage Tank 08 EQRR-PCD003 Emergency Air 2.2,05.05a.i-U3-VES-MT-09 Yes Analysis APP-MS23-VDR-001 Storage Tank 09 EQRR-PCD003 Emergency Air VES-MT-10 2.2.05.05a.i-U3-Yes Analysis APP-MS23-VDR-001 Storage Tank 10 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-11 Yes Analysis APP-MS23-VDR-001 Storage Tank 11 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-12 Yes Analysis APP-MS23-VDR-001 Storage Tank 12 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-13 Yes Analysis APP-MS23-VDR-001 Storage Tank 13 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-14 Yes Analysis APP-MS23-VDR-001 Storage Tank 14 EQRR-PCD003 Emergency Air VES-MT-15 2.2.05.05a.i-U3-Yes Analysis APP-MS23-VDR-001 Storage Tank 15 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-16 Yes Analysis APP-MS23-VDR-001 Storage Tank 16 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-17 Yes Analysis APP-MS23-VDR-001 Storage Tank 17 EQRR-PCD003 Emergency Air VES-MT-18 2.2.05.05a.i-U3-Yes Analysis APP-MS23-VDR-001 Storage Tank 18 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-19 Yes Analysis APP-MS23-VDR-001 Storage Tank 19 EQRR-PCD003

U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure 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-U3-VES-MT-20 Yes Analysis APP-MS23-VDR-001 Storage Tank 20 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-21 Yes Analysis APP-MS23-VDR-001 Storage Tank 21 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-22 Yes Analysis APP-MS23-VDR-001 Storage Tank 22 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-23 Yes Analysis APP-MS23-VDR-001 Storage Tank 23 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-24 Yes Analysis APP-MS23-VDR-001 Storage Tank 24 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-25 Yes Analysis APP-MS23-VDR-001 Storage Tank 25 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-26 Yes Analysis APP-MS23-VDR-001 Storage Tank 26 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-27 Yes Analysis APP-MS23-VDR-001 Storage Tank 27 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-28 Yes Analysis APP-MS23-VDR-001 Storage Tank 28 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-29 Yes Analysis APP-MS23-VDR-001 Storage Tank 29 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-30 Yes Analysis APP-MS23-VDR-001 Storage Tank 30 EQRR-PCD003 Emergency Air 2.2.05.05a.i-U3-VES-MT-31 Yes Analysis APP-MS23-VDR-001 Storage Tank 31 EQRR-PCD003 Emergency Air 2.2.05.05a,i-U3-VES-MT-32 Yes Analysis APP-MS23-VDR-001 Storage Tank 32 EQRR-PCD003 VES-PL- Type SV3-PV02-VBR-010/ 2.2.05.05a.i-U3-Air Delivery Alternate Yes Isolation Valve V001 Testing & SV3-PV02-VBR-009 EQRR-PCD001 Analysis Eductor Flow Path VES-PL- Type SV3-PV02-VBR-010/ 2.2.05.05a.i-U3-Yes Testing &

Isolation Valve V045 SV3-PV02-VBR-009 EQRR-PCD001 Analysis VES-PL- Type SV3-PV02-VBR-010/ 2.2.05.05a.i-U3-Eductor Bypass Yes Isolation Valve V046 Testing & SV3-PV02-VBR-009 EQRR-PCD001 Analysis VES-PL- Type SV3-PV15-VBR-002/ 2.2.05.05a.i-U3-Pressure Regulating Yes Valve A V002A Testing & SV3-PV15-VBR-001 EQRR-PCD001 Analysis VES-PL- Type SV3-PV15-VBR-002/ 2.2.05.05a.i-U3-Pressure Regulating Yes Valve B V002B Testing & SV3-PV15-VBR-001 EQRR-PCD001 Analysis VES-PL- Type SV3-PV13-VBR-012/ 2.2.05.05a.i-U3-MCR Air Delivery Yes Isolation Valve A V005A Testing & SV3-PV13-VBR-011 EQRR-PCD001 Analysis VES-PL- Type SV3-PV13-VBR-012/ 2.2.05.05a.i-U3-MCR Air Delivery Yes Isolation Valve B V005B Testing & SV3-PV13-VBR-011 EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure Page 8 of 9 Seismic Type of Equipment Name ^ Tag No. ^ EQ Reports) As-Built EQRR Cat. I

• Qual.

Temporary VES-PL- Type SV3-PV02-VBR-010/ 2.2.05.05a.i-U3-Instrument Yes Testing &

V018 SV3-PV02-VBR-009 EQRR-PCD001 Isolation Valve A Analysis Temporary VES-PL- Type SV3-PV02-VBR-010/ 2.2.05.05a.i-U3-Instrument Yes Testing &

V019 SV3-PV02-VBR-009 EQRR-PCD001 Isolation Valve B Analysis MCR Pressure Relief VES-PL- Type SV3-PV11-VBR-004/ 2.2.05.05a.i-U3-Yes Testing &

Isolation Valve A V022A SV3-PV11-VBR-003 EQRR-PCD001 Analysis MCR Pressure Relief VES-PL- Type SV3-PV11-VBR-004/ 2.2.05.05a.i-U3-Yes Testing &

Isolation Valve B V022B SV3-PV11-VBR-003 EQRR-PCD001 Analysis VES-PL- Type SV3-PV16-VBR-002/ 2.2.05.05a.i-U3-Air Tank Safety Relief Yes Valve A V040A Testing & SV3-PV16-VBR-001 EQRR-PCD001 Analysis VES-PL- Type SV3-PV16-VBR-002/ 2.2.05.05a.i-U3-Air Tank Safety Relief Yes Valve B V040B Testing & SV3-PV16-VBR-001 EQRR-PCD001 Analysis VES-PL- Type SV3-PV16-VBR-002/ 2.2.05.05a.i-U3-Air Tank Safety Relief Yes Valve C V040C Testing & SV3-PV16-VBR-001 EQRR-PCD001 Analysis VES-PL- Type SV3-PV16-VBR-002/ 2.2.05.05a.i-U3-Air Tank Safety Relief Yes Valve D V040D Testing & SV3-PV16-VBR-001 EQRR-PCD001 Analysis Main Air Flow Path VES-PL- Type SV3-PV02-VBR-010/ 2.2.05.05a.i-U3-Yes Testing &

Isolation Valve V044 SV3-PV02-VBR-009 EQRR-PCD001 Analysis MCR Air Filtration 2.2.05.05a.i-U3-VES-PY-N01 Yes Analysis SV3-PY82-VDR-001 Line Eductor EQRR-PCD002 MCR Air Filtration 2.2.05.05a.i-U3-VES-MY-F01 Yes Analysis SV3-MS59-VDR-001 Line Charcoal Filter EQRR-PCD002 MCR Air Filtration 2.2,05.05a.i-U3-VES-MY-F02 Yes Analysis SV3-MS59-VDR-001 Line HEPA Filter EQRR-PCD002 MCR Air Filtration 2.2.05.05a.i-U3-VES-MY-F03 Yes Analysis SV3-MS59-VDR-001 Line Postfilter EQRR-PCD002 MCR Gravity Relief VES-MD- 2.2.05.05a.i-U3-Yes Analysis SV3-MD27-VGC-850000 Dampers D001A EQRR-PCD002 MCR Gravity Relief VES-MD- 2.2.05.05a.i-U3-Yes Analysis SV3-MD27-VGC-850000 Dampers D001B EQRR-PCD002 MCR Air Filtration VES-MD- 2.2.05.05a.i-U3-Yes Analysis SV3-MD30-VDR-001 Line Supply Damper D002 EQRR-PCD002 MCR Air Filtration VES-MD- 2.2.05.05a.i-U3-Yes Analysis SV3-MD30-VDR-001 Line Supply Damper D003 EQRR-PCD002 MCR Air Filtration 2.2.05.05a.i-U3-VES-MY-Y01 Yes Analysis SV3-MY71-VDR-001 Line Silencer EQRR-PCD002 MCR Air Filtration 2.2.05.05a.i-U3-VES-MY-Y02 Yes Analysis SV3-MY71-VDR-001 Line Silencer EQRR-PCD002

U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure Page 9 of 9 Seismic Type of Equipment Name ^ Tag No.

• EQ Reports) As-Built EQRR Cat. I ^ Qual.

Type SV3-JE54-VBR-002/ 2.2.05.05a.i-U3-MCR Air Delivery Line VES-003A Yes Flow Sensor Testing & SV3-JE54-VBR-001 EQRR-PCD002 Analysis Type SV3-JE54-VBR-002/ 2.2.05.05a.i-U3-MCR Air Delivery Line VES-003B Yes Flow Sensor Testing & SV3-JE54-VBR-001 EQRR-PCD002 Analysis MCR Differential Type SV3-JE52-VBR-006/ 2.2.05.05a.i-U3-VES-004A Yes Testing &

Pressure Sensor A SV3-JE52-VBR-005 EQRR-PCD002 Analysis MCR Differential Type SV3-JE52-VBR-006/ 2.2.05.05a.i-U3-VES-004B Yes Testing &

Pressure Sensor B SV3-JE52-VBR-005 EQRR-PCD002 Analysis Type 2.2.05.05a.i-U3-MCR Filter Shielding 12401-NS-01 Yes Testing & SV3-MS59-VDR-001 EQRR-PCD002 Analysis

+ Excerpt from COL Appendix C Table 2.2.5-1