ND-18-0187, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.05.05a.i (Index Number 259)
| ML18065A063 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/05/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.2.05.05a.i, ND-18-0187 | |
| Download: ML18065A063 (12) | |
Text
Sk. Southern Nuclear MAK 0 a 20tfl Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Vox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynestxaro, GA 30830 706-848-6459 tei 410-474-8587 ceil myox@southernco.com ND-18-0187 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtie ElectricGenerating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.05.05a.i (Index Number 2591 Ladies and Gentlemen:
Pursuant to 10CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 28, 2018, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.05.05a.i
[Index Number 259] hasnot been completed greater than 225-days prior to initial fuel load. The Enclosure describesthe plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.
This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.
All ITAAC will befully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC tosupport the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).
This letter contains no new NRC regulatory commitments.
If there are any questions, please contactTom Petrakat 706-848-1575.
Respectfully submitted.
Yoy//
Michael J.
Regulatory Affairs Director Vogtie 3&4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.05.05a.i [Index Number 259]
MJY/LBP/amw
U.S. Nuclear Regulatory Commission ND-18-0187 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Rauckhorst (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Reouiatorv Commission Mr. W. Jones (w/o enclosures)
Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Oaiethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0187 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, Inc.
Mr. 8. Roetger, GeorgiaPublicService Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-18-0187 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.05.05a.l [Index Number 259]
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 2 of 9 ITAAC Statement Desion Commitment:
5.a) The seismic Category Iequipment identified inTable 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 thatthe seismic Category Iequipment and valves identified in Table 2.2.5-1 are located on the Nuclear Island.
ii) Type tests, analyses, ora combination of type tests and analysesof seismic Category I equipment will be performed.
ill) Inspection will be performed for the existence of a report verifying that theas-built equipment including anchorage isseismically bounded bythe tested oranalyzed conditions.
Acceptance Criteria:
i) The seismic Category Iequipment identified in Table 2.2.5-1 is located on the Nuclear Island.
ii) Areport exists and concludes that the seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function.
iii) Areport exists and concludes that the as-built equipment including anchorage is seismically bounded bythe tested or analyzed conditions.
ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses beperformed arid documented to ensurethe Main Control Room Emergency Habitability System (VES) equipment identified as seismic Category Iin the Combined License (COL) Appendix C, Table 2.2.5-1 (the Table) is designed andconstructed in accordance with applicable requirements.
\\) The seismic Cateoorv Ieouioment identified in Table 2.2.5-1 is located on the Nuclear Island To assurethat seismic Category Iequipment canwithstand seismic design basis loads without loss of safety function, all the equipment in the Table is designed to belocated on the seismic Category INuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection isconducted of theVES to confirm the satisfactory installation of theseismically qualified equipment. The inspection includes verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment Adocument the results ofthe inspection and conclude thatthe seismic Category I equipmentis locatedon the Nuclear Island.
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 3 of 9 in A report exists and concludes that the seismic Cateoorv I eouioment can withstand seismic desion basis loads without loss of safety function.
Seismic Category I equipment 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 equipment, is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionalityof the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).
Safety-related (Class 1E) electrical equipment inthe Table is seismically qualified bytype testing, analysis, or a combination oftype tests and analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). This equipment includessafety-related(Class 1E)field sensors and the safety-relatedactivevalveaccessories such as electric actuators, position switches, pilotsolenoid valves and electrical connector assemblies. The specific qualification method (i.e., type testing,analysis, or combination) used foreach pieceofequipment inthe Table is identified inAttachment A. Additional information about the methods used to qualify API000 safety-relatedequipmentis provided in the Updated Final SafetyAnalysis Report (UFSAR) Appendix 3D(Reference6). The EQ Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation and conclude that the seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function.
iiil A reoort exists and concludes that the as-built eouioment includino anchoraoe is seismicallv bounded bv the tested or analvzed conditions.
An inspection isconducted toconfirm thesatisfactory installation of theseismically qualified equipment in theTable. The inspection verifies theequipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other interfaces. The documentation of installedconfiguration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.
As part of theseismic qualification program, consideration isgiven tothedefinition of the clearances needed around the equipmentmounted in the plantto permit the equipmentto move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This isdone as part of seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of theequipment. EQ Reports (Reference 7) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation doesnot degrade theestablished qualification.
Interface requirements are defined based onthe test configuration and other design requirements.
Attachment Aidentifies the EQRR (Reference2) completed to verify that the as-built seismic Category Iequipment listed in the Table, including anchorage, areseismically bounded by the tested oranalyzed conditions, IEEE Standard 344-1987 (Reference 5), and NRG Regulatory Guide 1.100 (Reference 8).
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 4 of 9 Together, these reports (References 2 and 7) 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 Areport exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
References 2 and 7 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.05.05a.i Completion Packages (References 9 and 10, respectively).
List of ITAAC Findings In accordance with plantprocedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining tothesubject ITAAC and associated corrective actions. Thisfinding review, which included now-consolidated ITAAC Indexes260 and 261,found the following relevant ITAAC findings associated with this ITAAC:
Notice of Nonconformance 99901412/2012-201 -02 (Closed)
Before submissionofthe ICN, corrective actions will be completefor relevant findings identified prior to ICN submission.
References (available for NRC inspection) 1.
ND-xx-xx-001, "EQ Walkdown ITAAC Guideline"
- 2. As-Built EQ Reconciliation Reports (EQRR) as identified in Attachment Afor Units 3 and 4
Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda
- 4. ASME QME-1-2007, "Qualification ofActive Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007
- 5. IEEE Standard 344-1987, "IEEE Recommended Practicesfor SeismicQualification ofClass 1E Equipment for Nuclear PowerGeneratingStations"
- 6. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment"
- 7. Equipment Qualification (EQ) Reports as identified in Attachment A
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 5 of 9 8.
Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants" 9.
2.2.05.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.2.05.05a.i [Index Number 259]"
10.2.2.05.05a.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.2.05.05a.i [Index Number 259]"
- 11. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 6 of 9 Attachment A System; Main Control Room Emergency Habitability System Equipment Name
- Tag No.
- Seismic Cat. 1 +
Type of Qual.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)
- MCR Load Shed Panel 1 VES-EP-01 Yes Type Testing APP-EP10-VBR-002/
APP-EP10-VBR-001 2.2.05.05a.i-U3-EQRR-PCDXXX MCR Load Shed Panel 2 VES-EP-02 Yes Type Testing APP-EP10-VBR-002/
APP-EP10-VBR-001 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 01 VES-MT-01 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 02 VES-MT-02 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 03 VES-MT-03 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 04 VES-MT-04 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 05 VES-MT-05 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 06 VES-MT-06 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 07 VES-MT-07 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 08 VES-MT-08 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 09 VES-MT-09 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 10 VES-MT-10 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 11 VES-MT-11 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 12 VES-MT-12 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 13 VES-MT-13 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 14 VES-MT-14 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 15 VES-MT-15 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX EmergencyAir Storage Tank 16 VES-MT-16 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX Emergency Air Storage Tank 17 VES-MT-17 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX EmergencyAir Storage Tank 18 VES-MT-18 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX EmergencyAir Storage Tank 19 VES-MT-19 Yes Analysis APP-MS23-S2C-XXX 2.2.05.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 7 of 9 Equipment Name
- Tag No.
- Seismic Cat. 1 +
Type of Qual.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)
- Emergency Air Storage Tank 20 VES-MT-20 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX EmergencyAir Storage Tank 21 VES-MT-21 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Emergency Air Storage Tank 22 VES-MT-22 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX EmergencyAir Storage Tank 23 VES-MT-23 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Emergency Air Storage Tank 24 VES-MT-24 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX EmergencyAir Storage Tank 25 VES-MT-25 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Emergency Air Storage Tank 26 VES-MT-26 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX EmergencyAir Storage Tank 27 VES-MT-27 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX EmergencyAir Storage Tank 28 VES-MT-28 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Emergency Air Storage Tank 29 VES-MT-29 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Emergency Air Storage Tank 30 VES-MT-30 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Emergency Air Storage Tank 31 VES-MT-31 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Emergency Air Storage Tank 32 VES-MT-32 Yes Analysis APP-MS23-S2G-XXX 2.2.05.05a.i-U3-EQRR-PGDXXX Air Delivery Alternate Isolation Valve VES-PL-V001 Yes Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PGDXXX Eductor Flow Path Isolation Valve VES-PL-V045 Yes Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PGDXXX Eductor Bypass Isolation Valve VES-PL-V046 Yes Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PGDXXX Pressure Regulating Valve A VES-PL-V002A Yes Type Testing &
Analysis APP-PV15-VBR-002/
APP-PV15-VBR-001 2.2.05.05a.i-U3-EQRR-PGDXXX Pressure Regulating Valve B VES-PL-V002B Yes Type Testing &
Analysis APP-PV15-VBR-002/
APP-PV15-VBR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Delivery Isolation Valve A VES-PL-V005A Yes Type Testing &
Analysis APP-PV13-VBR-XXX/
APP-PV13-VBR-YYY 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Delivery Isolation Valve B VES-PL-V005B Yes Type Testing &
Analysis APP-PV13-VBR-XXX/
APP-PV13-VBR-YYY 2.2.05.05a.i-U3-EQRR-PGDXXX
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 8 of 9 Equipment Name
- Tag No.
- Seismic Cat. 1^
Type of Quai.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)
- Temporary Instrument Isolation Valve A VES-PL-V018 Yes Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PGDXXX Temporary Instrument Isolation Valve B VES-PL-V019 Yes Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Pressure Relief Isolation Valve A VES-PL-V022A Yes Type Testing &
Analysis APP-PV11-VBR-004/
APP-PV11-VBR-003 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Pressure Relief Isolation Valve B VES-PL-V022B Yes Type Testing &
Analysis APP-PV11-VBR-004/
APP-PV11-VBR-003 2.2.05.05a.i-U3-EQRR-PGDXXX AirTank Safety Relief Valve A VES-PL-V040A Yes Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PGDXXX AirTank Safety Relief Valve B VES-PL-V040B Yes Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PGDXXX Air Tank Safety Relief Valve G VES-PL-V040G Yes Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PGDXXX AirTank Safety Relief Valve D VES-PL-V040D Yes Type Testing &
Analysis APP-PV16-VBR-002 /
APP-PV16-VBR-001 2.2.05.05a.i-U3-EQRR-PGDXXX Main Air Flow Path Isolation Valve VES-PL-V044 Yes Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line Eductor VES-PY-N01 Yes Analysis APP-PY82-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line Charcoal Filter VES-MY-F01 Yes Analysis APP-MS59-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line HEPA Filter VES-MY-F02 Yes Analysis APP-MS59-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line Postfilter VES-MY-F03 Yes Analysis APP-MS59-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGRGravity Relief Dampers VES-MD-D001A Yes Analysis SV3-MD27-VQR-850002 or SV4-MD27-VQR-850003 2.2.05.05a.i-U3-EQRR-PGDXXX MGRGravity Relief Dampers VES-MD-D001B Yes Analysis SV3-MD27-VQR-850002 or SV4-MD27-VQR-850003 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line Suppiv Damper VES-MD-D002 Yes Analysis APP-MD30-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line Suppiv Damper VES-MD-D003 Yes Analysis APP-MD30-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line Silencer VES-MY-Y01 Yes Analysis APP-MY71-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX MGR Air Filtration Line Silencer VES-MY-Y02:
Yes Analysis APP-MY71-VDR-001 2.2.05.05a.i-U3-EQRR-PGDXXX
U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 9 of 9 Equipment Name
- Tag No.
- Seismic Cat. i +
Type of Qual.
EQ Reports (Reference 7)
As-Buiit EQRR (Reference 2)
- MCR Air Delivery Line Flow Sensor VES-003A Yes Type Testing &
Analysis APP-JE54-VBR-002 /
APP-JE54-VBR-001 2.2.05.05a.i-U3-EQRR-PCDXXX MCR Air Delivery Line Flow Sensor VES-003B Yes Type Testing &
Analysis APP-JE54-VBR-002 /
APP-JE54-VBR-001 2.2.05.05a.i-U3-EQRR-PCDXXX MCR Differential Pressure Sensor A VES-004A Yes Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.05.05a.i-U3-EQRR-PCDXXX MCR Differential Pressure Sensor B VES-004B Yes Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.05.05a.i-U3-EQRR-PCDXXX
+ Excerpt from COL Appendix C Table 2.2.5-1
- Tfie Unit 4 As-Built EQRR are numbered "2.2.05.05a.i-U4-EQRR-PCDXXX"