ND-21-1035, 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 Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6426 tel Southern Nuclear 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 API 000 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 G 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:
G 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)
- 3. As-Built EQ Reconciliation Reports (EQRR) as identified in Attachment A for Units 3
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 API 000 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 Cat. I ^
Type of Qual.
Equipment Name Tag No. ^
EQ Reports)
As-Built EQRR MCR Load Shed Panel 1 Type Testing APP-EP10-VBR-003/
APP-EP10-VBR-004 2.2.05.05a.i-U3-EQRR-PCD002 VES-EP-01 Yes MCR Load Shed Panel 2 Type Testing APP-EP10-VBR-003/
APP-EP10-VBR-004 2.2.05.05a.i-U3-EQRR-PCD002 VES-EP-02 Yes Emergency Air Storage Tank 01 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-01 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 02 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-02 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 03 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-03 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 04 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-04 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 05 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-05 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 06 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-06 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 07 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-07 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 08 2.2.05.05a.i-U3-EQRR-PCD003 2.2,05.05a.i-U3-EQRR-PCD003 VES-MT-08 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 09 VES-MT-09 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 10 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-10 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 11 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-11 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 12 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-12 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 13 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-13 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 14 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-14 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 15 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-15 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 16 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-16 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 17 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-17 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 18 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-18 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 19 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-19 Analysis Yes APP-MS23-VDR-001
U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure Page 7 of 9 Seismic Cat. I ^
Type of Qual.
Equipment Name ^
Tag No. ^
EQ Reports)
As-Built EQRR Emergency Air Storage Tank 20 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-20 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 21 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-21 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 22 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-22 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 23 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-23 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 24 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-24 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 25 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-25 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 26 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-26 Analysis Yes APP-MS23-VDR-001 Emergency Air Storage Tank 27 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-27 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 28 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-28 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 29 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-29 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 30 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-30 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 31 2.2.05.05a.i-U3-EQRR-PCD003 VES-MT-31 Yes Analysis APP-MS23-VDR-001 Emergency Air Storage Tank 32 2.2.05.05a,i-U3-EQRR-PCD003 VES-MT-32 Analysis Yes APP-MS23-VDR-001 Type Testing &
Analysis Air Delivery Alternate Isolation Valve VES-PL-SV3-PV02-VBR-010/
SV3-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PCD001 Yes V001 Type Testing &
Analysis Eductor Flow Path Isolation Valve VES-PL-V045 SV3-PV02-VBR-010/
SV3-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Eductor Bypass Isolation Valve VES-PL-V046 SV3-PV02-VBR-010/
SV3-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Pressure Regulating Valve A VES-PL-V002A SV3-PV15-VBR-002/
SV3-PV15-VBR-001 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Pressure Regulating Valve B VES-PL-V002B SV3-PV15-VBR-002/
SV3-PV15-VBR-001 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis MCR Air Delivery Isolation Valve A VES-PL-V005A SV3-PV13-VBR-012/
SV3-PV13-VBR-011 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis MCR Air Delivery Isolation Valve B VES-PL-V005B SV3-PV13-VBR-012/
SV3-PV13-VBR-011 2.2.05.05a.i-U3-EQRR-PCD001 Yes
U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure Page 8 of 9 Seismic Cat. I
- Type of Qual.
Equipment Name ^
Tag No. ^
EQ Reports)
As-Built EQRR Temporary Instrument Isolation Valve A Type Testing &
Analysis VES-PL-V018 SV3-PV02-VBR-010/
SV3-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PCD001 Yes Temporary Instrument Isolation Valve B Type Testing &
Analysis VES-PL-V019 SV3-PV02-VBR-010/
SV3-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis MCR Pressure Relief Isolation Valve A VES-PL-V022A SV3-PV11-VBR-004/
SV3-PV11-VBR-003 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis MCR Pressure Relief Isolation Valve B VES-PL-V022B SV3-PV11-VBR-004/
SV3-PV11-VBR-003 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Air Tank Safety Relief Valve A VES-PL-V040A SV3-PV16-VBR-002/
SV3-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Air Tank Safety Relief Valve B VES-PL-V040B SV3-PV16-VBR-002/
SV3-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Air Tank Safety Relief Valve C VES-PL-V040C SV3-PV16-VBR-002/
SV3-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Air Tank Safety Relief Valve D VES-PL-V040D SV3-PV16-VBR-002/
SV3-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PCD001 Yes Type Testing &
Analysis Main Air Flow Path Isolation Valve VES-PL-V044 SV3-PV02-VBR-010/
SV3-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PCD001 Yes MCR Air Filtration Line Eductor 2.2.05.05a.i-U3-EQRR-PCD002 VES-PY-N01 Yes Analysis SV3-PY82-VDR-001 MCR Air Filtration Line Charcoal Filter 2.2.05.05a.i-U3-EQRR-PCD002 VES-MY-F01 Yes Analysis SV3-MS59-VDR-001 MCR Air Filtration Line HEPA Filter 2.2,05.05a.i-U3-EQRR-PCD002 VES-MY-F02 Yes Analysis SV3-MS59-VDR-001 MCR Air Filtration Line Postfilter 2.2.05.05a.i-U3-EQRR-PCD002 VES-MY-F03 Yes Analysis SV3-MS59-VDR-001 MCR Gravity Relief Dampers VES-MD-D001A 2.2.05.05a.i-U3-EQRR-PCD002 Yes Analysis SV3-MD27-VGC-850000 MCR Gravity Relief Dampers VES-MD-D001B 2.2.05.05a.i-U3-EQRR-PCD002 Yes Analysis SV3-MD27-VGC-850000 MCR Air Filtration Line Supply Damper VES-MD-D002 2.2.05.05a.i-U3-EQRR-PCD002 Analysis Yes SV3-MD30-VDR-001 MCR Air Filtration Line Supply Damper VES-MD-D003 2.2.05.05a.i-U3-EQRR-PCD002 Yes Analysis SV3-MD30-VDR-001 MCR Air Filtration Line Silencer 2.2.05.05a.i-U3-EQRR-PCD002 VES-MY-Y01 Yes Analysis SV3-MY71-VDR-001 MCR Air Filtration Line Silencer 2.2.05.05a.i-U3-EQRR-PCD002 VES-MY-Y02 Analysis Yes SV3-MY71-VDR-001
U.S. Nuclear Regulatory Commission ND-21-1035 Enclosure Page 9 of 9 Seismic Cat. I ^
Type of Qual.
Equipment Name ^
Tag No.
- EQ Reports)
As-Built EQRR Type Testing &
Analysis MCR Air Delivery Line Flow Sensor SV3-JE54-VBR-002/
SV3-JE54-VBR-001 2.2.05.05a.i-U3-EQRR-PCD002 VES-003A Yes Type Testing &
Analysis MCR Air Delivery Line Flow Sensor SV3-JE54-VBR-002/
SV3-JE54-VBR-001 2.2.05.05a.i-U3-EQRR-PCD002 VES-003B Yes Type Testing &
Analysis MCR Differential Pressure Sensor A SV3-JE52-VBR-006/
SV3-JE52-VBR-005 2.2.05.05a.i-U3-EQRR-PCD002 VES-004A Yes Type Testing &
Analysis MCR Differential Pressure Sensor B SV3-JE52-VBR-006/
SV3-JE52-VBR-005 2.2.05.05a.i-U3-EQRR-PCD002 VES-004B Yes Type Testing &
Analysis 2.2.05.05a.i-U3-EQRR-PCD002 MCR Filter Shielding 12401-NS-01 Yes SV3-MS59-VDR-001
+ Excerpt from COL Appendix C Table 2.2.5-1