ND-18-0187, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.05.05a.i (Index Number 259)

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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  Southern Nuclear icon.png
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)
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Text

Michael J. Vox 7825 River Road Regulatory Affairs Director Waynestxaro, GA 30830 Sk. Southern Nuclear Vogtie 3 & 4 706-848-6459 tei MAK 0 a 20tfl 410-474-8587 ceil myox @southernco.com Docket Nos.: 52-025 52-026 ND-18-0187 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating 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 10 CFR 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] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the 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 be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support 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 contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yoy//

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, Georgia PublicService 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) Unit 3 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 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.

ill) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded bythe tested or analyzed 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 of safety function.

iii) Areport exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed 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 and constructed in accordance with applicable requirements.

\) The seismic Cateoorv I eouioment identified in Table 2.2.5-1 is located on the Nuclear Island To assurethat seismic Category Iequipment can withstand 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 the seismically 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 equipment is located on 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 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 5). This equipment includessafety-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 inthe 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 6). The EQ Reports (Reference 7) identified in Attachment Acontain 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.

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 to confirm thesatisfactory installation of theseismically qualified equipment in theTable. 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 isgiven to the definition of the clearances needed around the equipment mounted 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 the equipment. EQ Reports (Reference 7) 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 (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
  • A report 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 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. Thisfinding 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)

Before submission ofthe ICN, corrective actions will be complete for 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
3. 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

4. ASME QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007
5. IEEE Standard 344-1987, "IEEE Recommended Practicesfor SeismicQualification of Class 1E Equipment for Nuclear Power Generating Stations"
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 Seismic Type of As-Built EQRR Equipment Name

  • Tag No.
  • EQ Reports (Reference 7) (Reference 2)
  • Cat. 1 + Qual.

MCR Load Shed Type APP-EP10-VBR-002/ 2.2.05.05a.i-U3-VES-EP-01 Yes Panel 1 Testing APP-EP10-VBR-001 EQRR-PCDXXX MCR Load Shed Type APP-EP10-VBR-002/ 2.2.05.05a.i-U3-VES-EP-02 Yes EQRR-PCDXXX Panel 2 Testing APP-EP10-VBR-001 Emergency Air 2.2.05.05a.i-U3-VES-MT-01 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 01 Emergency Air 2.2.05.05a.i-U3-VES-MT-02 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 02 Emergency Air 2.2.05.05a.i-U3-VES-MT-03 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 03 Emergency Air 2.2.05.05a.i-U3-VES-MT-04 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 04 Emergency Air 2.2.05.05a.i-U3-VES-MT-05 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 05 Emergency Air 2.2.05.05a.i-U3-VES-MT-06 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 06 Emergency Air 2.2.05.05a.i-U3-VES-MT-07 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 07 Emergency Air 2.2.05.05a.i-U3-VES-MT-08 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 08 Emergency Air 2.2.05.05a.i-U3-VES-MT-09 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 09 Emergency Air 2.2.05.05a.i-U3-VES-MT-10 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 10 Emergency Air 2.2.05.05a.i-U3-VES-MT-11 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 11 Emergency Air 2.2.05.05a.i-U3-VES-MT-12 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 12 Emergency Air 2.2.05.05a.i-U3-VES-MT-13 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 13 Emergency Air 2.2.05.05a.i-U3-VES-MT-14 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 14 Emergency Air 2.2.05.05a.i-U3-VES-MT-15 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 15 Emergency Air 2.2.05.05a.i-U3-VES-MT-16 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 16 Emergency Air 2.2.05.05a.i-U3-VES-MT-17 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 17 Emergency Air 2.2.05.05a.i-U3-VES-MT-18 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 18 Emergency Air 2.2.05.05a.i-U3-VES-MT-19 Yes Analysis APP-MS23-S2C-XXX EQRR-PCDXXX Storage Tank 19

U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 7 of 9 Seismic Type of As-Built EQRR Equipment Name

  • Tag No.
  • EQ Reports (Reference 7)

Cat. 1 + Qual. (Reference 2)

  • Emergency Air 2.2.05.05a.i-U3-VES-MT-20 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 20 Emergency Air 2.2.05.05a.i-U3-VES-MT-21 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 21 Emergency Air 2.2.05.05a.i-U3-VES-MT-22 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 22 Emergency Air 2.2.05.05a.i-U3-VES-MT-23 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 23 Emergency Air 2.2.05.05a.i-U3-VES-MT-24 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 24 Emergency Air 2.2.05.05a.i-U3-VES-MT-25 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 25 Emergency Air 2.2.05.05a.i-U3-VES-MT-26 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 26 Emergency Air 2.2.05.05a.i-U3-VES-MT-27 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 27 Emergency Air 2.2.05.05a.i-U3-VES-MT-28 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 28 Emergency Air 2.2.05.05a.i-U3-VES-MT-29 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 29 Emergency Air 2.2.05.05a.i-U3-VES-MT-30 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 30 Emergency Air 2.2.05.05a.i-U3-VES-MT-31 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 31 Emergency Air 2.2.05.05a.i-U3-VES-MT-32 Yes Analysis APP-MS23-S2G-XXX EQRR-PGDXXX Storage Tank 32 Type 2.2.05.05a.i-U3-Air Delivery Alternate VES-PL- APP-PV02-VBR-010/

Yes Testing & EQRR-PGDXXX Isolation Valve V001 APP-PV02-VBR-009 Analysis Type 2.2.05.05a.i-U3-Eductor Flow Path VES-PL- APP-PV02-VBR-010/

Yes Testing & EQRR-PGDXXX Isolation Valve V045 APP-PV02-VBR-009 Analysis Type 2.2.05.05a.i-U3-Eductor Bypass VES-PL- APP-PV02-VBR-010/

Yes Testing & EQRR-PGDXXX Isolation Valve V046 APP-PV02-VBR-009 Analysis Type APP-PV15-VBR-002/ 2.2.05.05a.i-U3-Pressure Regulating VES-PL-Yes Testing &

Valve A V002A APP-PV15-VBR-001 EQRR-PGDXXX Analysis Type 2.2.05.05a.i-U3-Pressure Regulating VES-PL- APP-PV15-VBR-002/

Yes Testing & EQRR-PGDXXX Valve B V002B APP-PV15-VBR-001 Analysis Type 2.2.05.05a.i-U3-MGR Air Delivery VES-PL- APP-PV13-VBR-XXX/

Yes Testing & APP-PV13-VBR-YYY EQRR-PGDXXX Isolation Valve A V005A Analysis Type 2.2.05.05a.i-U3-MGR Air Delivery VES-PL- APP-PV13-VBR-XXX/

Yes Testing & EQRR-PGDXXX Isolation Valve B V005B APP-PV13-VBR-YYY Analysis

U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 8 of 9 Seismic Type of As-Built EQRR Equipment Name

  • Tag No.
  • EQ Reports (Reference 7) (Reference 2)
  • Cat. 1 ^ Quai.

Temporary Type 2.2.05.05a.i-U3-VES-PL- APP-PV02-VBR-010/

Instrument Yes Testing &

V018 APP-PV02-VBR-009 EQRR-PGDXXX Isolation Valve A Analysis Temporary Type 2.2.05.05a.i-U3-VES-PL- APP-PV02-VBR-010/

Instrument Yes Testing & EQRR-PGDXXX V019 APP-PV02-VBR-009 Isolation Valve B Analysis Type 2.2.05.05a.i-U3-MGR Pressure Relief VES-PL- APP-PV11-VBR-004/

Yes Testing & EQRR-PGDXXX Isolation Valve A V022A APP-PV11-VBR-003 Analysis Type APP-PV11-VBR-004/ 2.2.05.05a.i-U3-MGR Pressure Relief VES-PL-Yes Testing & EQRR-PGDXXX Isolation Valve B V022B APP-PV11-VBR-003 Analysis Type APP-PV16-VBR-002/ 2.2.05.05a.i-U3-AirTank Safety Relief VES-PL-Yes Testing &

Valve A V040A APP-PV16-VBR-001 EQRR-PGDXXX Analysis Type 2.2.05.05a.i-U3-AirTank Safety Relief VES-PL- APP-PV16-VBR-002/

Yes Testing & EQRR-PGDXXX Valve B V040B APP-PV16-VBR-001 Analysis Type APP-PV16-VBR-002/ 2.2.05.05a.i-U3-Air Tank Safety Relief VES-PL-Yes Testing &

Valve G V040G APP-PV16-VBR-001 EQRR-PGDXXX Analysis Type APP-PV16-VBR-002 / 2.2.05.05a.i-U3-AirTank Safety Relief VES-PL-Yes Testing &

V040D APP-PV16-VBR-001 EQRR-PGDXXX Valve D Analysis Type 2.2.05.05a.i-U3-Main Air Flow Path VES-PL- APP-PV02-VBR-010/

Yes Testing & APP-PV02-VBR-009 EQRR-PGDXXX Isolation Valve V044 Analysis 2.2.05.05a.i-U3-MGR Air Filtration Yes Analysis APP-PY82-VDR-001 VES-PY-N01 EQRR-PGDXXX Line Eductor 2.2.05.05a.i-U3-MGR Air Filtration Analysis APP-MS59-VDR-001 VES-MY-F01 Yes EQRR-PGDXXX Line Charcoal Filter 2.2.05.05a.i-U3-MGR Air Filtration Yes Analysis APP-MS59-VDR-001 VES-MY-F02 EQRR-PGDXXX Line HEPA Filter 2.2.05.05a.i-U3-MGR Air Filtration Yes Analysis APP-MS59-VDR-001 VES-MY-F03 EQRR-PGDXXX Line Postfilter VES-MD- SV3-MD27-VQR-850002 or 2.2.05.05a.i-U3-MGR Gravity Relief Yes Analysis SV4-MD27-VQR-850003 EQRR-PGDXXX Dampers D001A SV3-MD27-VQR-850002 or 2.2.05.05a.i-U3-MGR Gravity Relief VES-MD-Yes Analysis SV4-MD27-VQR-850003 D001B EQRR-PGDXXX Dampers VES-MD- 2.2.05.05a.i-U3-MGR Air Filtration Yes Analysis APP-MD30-VDR-001 D002 EQRR-PGDXXX Line Suppiv Damper VES-MD- 2.2.05.05a.i-U3-MGR Air Filtration Analysis APP-MD30-VDR-001 Yes EQRR-PGDXXX Line Suppiv Damper D003 2.2.05.05a.i-U3-MGR Air Filtration Yes Analysis APP-MY71-VDR-001 VES-MY-Y01 EQRR-PGDXXX Line Silencer 2.2.05.05a.i-U3-MGR Air Filtration Analysis APP-MY71-VDR-001 VES-MY-Y02: Yes EQRR-PGDXXX Line Silencer

U.S. Nuclear Regulatory Commission ND-18-0187 Enclosure Page 9 of 9 Seismic Type of As-Buiit EQRR Equipment Name

  • Tag No.
  • EQ Reports (Reference 7)

Cat. i + Qual. (Reference 2)

  • Type MCR Air Delivery Line APP-JE54-VBR-002 / 2.2.05.05a.i-U3-VES-003A Yes Testing &

Flow Sensor APP-JE54-VBR-001 EQRR-PCDXXX Analysis Type MCR Air Delivery Line Testing &

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

Pressure Sensor A APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type 2.2.05.05a.i-U3-MCR Differential APP-JE52-VBR-006 /

VES-004B Yes Testing &

Pressure Sensor B APP-JE52-VBR-005 EQRR-PCDXXX Analysis

+ 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"
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