ND-18-0419, Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.1 (Index Number 75)

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Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.1 (Index Number 75)
ML18100A068
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 04/09/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.1.03.06.1, ND-18-0419
Download: ML18100A068 (14)
v • d • e


Text

Ok. Southern Nuclear APR 0 9 2018 Docket Nos.;52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtle 3 &4 7825 River Road Waynesboro, GA30830 706-848-6459 tel 410-474-8587 cell myox <9southernco.com ND-18-0419 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Resubmittal of Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.03.06.1 [Index Number 75]

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 28, 2018, Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.03.06.1 [Index Number 75]

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.

Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.1.03.06.1 [Index Number 75] ND-18-0045

[ML18032A260] dated January 25, 2018. This resubmittal supersedes ND-18-0045 in its entirety.

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 ITAACfor 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.

Ifthere are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

oVrnfido fee Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-18-0419 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.03.06.1 [Index Number 75]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0419 Page 3 of 4 To:

Southern Nuclear Operating Companv/ Georgia Power ComDanv 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. Vox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. 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 Reoulatorv 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 Ms. N. C. Coovert Oalethorpe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0419 Page 4 of 4 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. 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. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, inc.

Mr. 8. Roetger, Georgia Public Service 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-18-0419 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-18-0419 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.1.03.06.1 [IndexNumber75]

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 2 of 10 ITAAC Statement Desion Commitment:

6. The seismic Category Iequipment identified in Table2.1.3-1 can withstand seismic design basis loads without loss of safety function.

9.a)The Class 1Eequipment identified in Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basisaccident without lossofsafety function for the time required to perform the safety function.

Inspections. Tests. Analvses:

i) Inspection will be performed to verify thatthe seismic Category Iequipment identified in Table 2.1.3-1 is 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 forthe existenceofa report verifying that the as-built equipment including anchorage is seismically bounded bythe tested or analyzed conditions.

i) Type tests, analysis, ora combination of type tests and analysis will be performed on Class 1E equipment located in a harsh environment.

ii) Inspection will be performed ofthe as-built Class 1Eequipment and the associated wiring, cables, and terminations located in a harsh environment.

Acceptance Criteria:

i) The seismic Category Iequipment identified in Table 2.1.3-1 is located on the Nuclear Island.

ii) Areport existsand concludes thatthe seismic Category Iequipment can withstand seismic design basis loads without loss of safety function.

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

i) Areport existsand concludes thatthe Class 1Eequipment identified in Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss ofsafety function forthe time required to perform the safety function.

ii) A reportexists and concludes that the as-built Class 1E equipmentand the associated wiring, cables, and terminations identified in Table 2.1.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 3 of 10 ITAAC ComDietion Description This ITAAC requires that inspections, tests, and analyses beperformed and documented to ensure the Reactor System (RXS) components identified as seismic Category IorClass 1E in the Combined License (COL) Appendix C, Table 2.1.3-1 (the Table) are designed and constructed in accordance with applicable requirements.

h The seismic Cateoorv Ieouioment identified inTable 2.1.3-1 is located on the Nuclear Island.

Toassure that seismicCategory Icomponents can withstand seismicdesign basis loads without lossofsafetyfunction, all the components in the Table are designed to be located on theseismic Category INuclear Island. In accordance with Equipment Qualification (EG)

Walkdown ITAAC Guideline (Reference1),an inspection is conductedofthe RXS to confirm the satisfactory installation ofthe seismically qualified components. The inspection includes verification ofequipment make/model/serial number and verification ofequipment location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identifiedin Attachment A document the results of the inspection and conclude that the seismic Category Icomponents are located on the Nuclear Island.

\\\\) A report exists and concludes that the seismic Cateoorv I equipment can withstand seismic desion basis loads without loss of safetv function.

Seismic Category Icomponents inthe Table require type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity ofthe seismic Category Ivalves, as well as other passive seismic Category Imechanical equipment, is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality ofthe subset ofactive safety-relatedvalves 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 by type testing combined with analysis inaccordance with Instituteof Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). 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 component inthe Table is identified inAttachment A. Additional information about the methods used to qualify API000 safety-related equipment is provided inthe Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6). The EG Reports (Reference 7) 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 eouioment includina anchoraoe is seismicallv bounded bv the tested or analvzed conditions.

Aninspection (Reference 1) is conducted to confirm the satisfactory installation of the seismically qualified components 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

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 4 of 10 seismlcally qualified components Includes photographs and/orsketches/drawings of equipment/mounting/interfaces.

Aspart of the seismic qualification program, consideration isgiven tothe definition ofthe clearances needed around the equipment mounted inthe plant to permitthe equipment to move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This isdoneas partof seismic testing bymeasuring the maximum dynamic relative displacement of the topand 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 notdegrade the established qualification.

Interface requirementsare defined based on the test configuration and other design requirements. In accordancewith NEI 08-01, Section 9.5, inspection ofthe RXS equipment mounting and verification ofcritical attributes from the seismic analyses are performed at other than the final installed location, due to inaccessibility of the equipment after installation.

AttachmentA identifies the EQRR(Reference 2) completed to verify that the as-builtseismic Category Iequipment listed in the Table, including anchorage, are seismically bounded bythe tested or analyzedconditions, IEEE Standard 344-1987 (Reference5) and NRG Regulatory Guide (RG) 1.100 (Reference 8).

\\) A report exists and concludes that the Class 1E ecuioment identified in Table 2.1.3-1 as beina Qualified for a harsh environment can withstand the environmental conditions that would exist before, durino. and followino a desion basis accident without loss of safetv function for the time recuired to oerform the safetv function.

The harsh environment Class 1E components in the Table are qualified bytype testing and/or analyses. Class 1Eelectrical component typetesting is performed in accordancewith IEEE Standard 323-1974(Reference 9) and RG 1.89 (Reference 10)to meet the requirementsof 10 CFR50.49. Typetestingofsafety-related equipment meets the requirements of10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment Aidentifies the EQprogram and specific qualification method for each safety-related mechanical or Class 1Eelectrical component located in a harsh environment. Additional information aboutthe methods used to qualify API000safety-related equipment is provided in the UFSAR Appendix 3D(Reference 6).

EQ Reports (Reference 7) identified in Attachment Acontainapplicabletest reports and associated documentation and conclude that the equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function forthe time required to perform the safety function.

W) A reoort exists and concludes that the as-built Class 1E ecuioment and the associated wirino.

cables, and terminations identified in Table 2.1.3-1 as beino Qualified for a harsh environment are bounded bv tvoe tests, analvses. or a combination of tvoe tests and analvses.

An inspection (Reference 1) is conducted ofthe RXS to confirm the satisfactory installation of the Class 1E components inthe Table. The inspection verifiesthe equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the componentis mounted are bounded bythe tested and/oranalyzedconditions. It also documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 2) identified in Attachment Adocument this

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 5 of 10 inspection andconclude thattheas-built harsh environment Class1Eequipment andthe associated wiring, cables, andterminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 9).

Together, these reports (References 2 and7)provide evidence thatthe ITAAC Acceptance Criteria requirements are met:

TheseismicCategory Iequipment identified in Table 2.1.3-1 is located on the Nuclear Island; Areport exists and concludes thatthe seismic Categoiy Iequipment can withstand seismic design basis loads without loss ofsafety function; Areport existsand concludes thatthe as-built equipment including anchorage is seismicallybounded by the tested or analyzed conditions; Areport exists and concludes thatthe Class1Eequipment identified in Table 2.1.3-1 as being qualified for a harsh environment canwithstand the environmental conditions that would existbefore, during, and following a design basis accidentwithout loss ofsafety function for the time required to perform the safety function; and Areport exists and concludes thattheas-built Class 1Eequipment andthe associated wiring, cables, andterminations identified in Table 2.1.3-1 as being qualified for a harsh environment are bounded bytype tests, analyses, or a combination oftype tests and analyses.

References 2 and 7 are available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.1.03.06.1 Completion Packages (References 11 and 12, respectively).

List of ITAAC Findings In accordancewith plant proceduresfor 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 Indexes 76, 77, 81, and 82, found no relevant ITAAC findings associated with this ITAAC.

References favaiiabie for NRC inspection) 1.

ND-xx-xx-001, "EG Walkdown ITAAC Guideline"

2. EG As-Built Reconciliation Reports as identified in AttachmentAfor Units 3 and 4
3. American Societyof 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. ASMEQME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 6 of 10 5.

IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualificationof Class 1E Equipment for Nuclear Power Generating Stations"

6. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Metfiodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment"
7. EquipmentQualification Reports as identified inAttachment A
8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear flower Plants" 9.

IEEE Standard 323-1974, "IEEEStandard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations"

10. Regulatory Guide 1.89, Rev 1, "Environmental Qualification ofCertain Electric Equipment Important to Safety for Nuclear Power Plants" 11.2.1.03.06.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.1.03.06.i [IndexNumber 75]"

12.2.1.03.06.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.1.03.06.1 [Index Number 75]"

13. NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 7 of 10 Attachment A System: Reactor System (RXS)

Equipment Name^

Tag No.+

Seismic Cat. i ^

Ciass 1E/

Qual. For Harsh Envir,^

Envir.

Zone ^

Envir Qual Program 2

Type of Quai.

EG Reports (Reference 7)

As-Built EQRR (Reference 2)^

RV (Reactor Vessel)

RXS-MV-01 Yes N/A N/A Analysis APP-MV01-ZOR-101 2.1.03.06.I-U3-EQRR-PCDXXX Reactor Upper Internals Assembly RXS-MI-01 Yes N/A N/A Analysis APP-MI01-S3R-002 2.1.03.06.1-U3-EQRR-PCDXXX Reactor Lower Internals Assembly RXS-MI-02 Yes N/A N/A Analysis APP-MI01-S3R-002 2.1.03.06.I-U3-EQRR-PCDXXX

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 8 of 10 Equipment Name^

Fuel Assemblies (157 locations)

Rod Cluster Oontrol Assemblies (ROOAs)

(minimum 53 locations)

Gray Rod Cluster Assemblies (GROAs) (16 locations)

Tag No/

RXS-FA-A07/ A08/ A09/ 805/ 806/ 807/ 808/

809/ 810/ 811/ 004/ 005/ 006/ 007/ 008/ 009/

010/ 011/ 012/ D03/ 004/ 005/ 006/ 007/ 008/

009/ 010/ 011/ 012/ 013/ E02/ E03/ E04/ E05/

E06/ E07/ E08/ E09/ E10/ El 1/ El 2/ El 3/ El 4/

F02/ F03/ F04/ F05/ F06/ F07/ F08/ F09/ F10/

F11/ F12/ F13/ F14/ G01/ G02/ G03/ G04/ G05/

G06/ G07/ G08/ G09/ G10/ Gil/ G12/ G13/

G14/ G15/ HOI/ H02/ H03/ H04/ H05/ H06/ H07/

H08/ H09/ H10/ H11/ H12/ H13/ H14/ H15/J01/

J02/ J03/ J04/ J05/ J06/ J07/ J08/ J09/ J10/ J11/

J12/ J13/ J14/ J15/ K02/ K03/ K04/ K05/ K06/

K07/ K08/ K09/ K10/ K11/ K12/ K13/ K14/ L02/

L03/ L04/ L05/ L06/ L07/ L08/ L09/ LI 0/ L11/

LI 2/ LI 3/ LI 4/ M03/ M04/ M05/ M06/ M07/ M08/

M09/ M10/ Ml 1/ M12/ M13/ N04/ N05/ N06/

N07/ N08/ N09/ N10/ N11/ N12/ P05/ P06/ P07/

P08/ P09/ P10/ P11/ R07/ R08/ R09 RXS-FR-806/ 810/ 005/ 007/ 009/ 011/ 006/

008/ 010/ E03/ E05/ E07/ E09/ El 1/ El3/ F02/

F04/ F12/ F14/ G03/ G05/ G07/ G09/ G11/ G13/

H04/ H08/ H12/ J03/ J05/ J07/ J09/ J11 / J13/

K02/ K04/ K12/ K14/ L03/ L05/ L07/ L09/ L11/

L13/ M06/ M08/ Ml0/ N05/ N07/ N09/ Nil/ P06/

P10 RXS-FG-808/ 004/ 012/ F06/ F08/ F10/ H02/

H06/ H10/ H14/ K06/ K08/ K10/ M04/ Ml2/ P08 Seismic Cat. I ^

Yes Yes Yes Class 1E/

Qual. For Harsh Envir.+ 3 Envir.

Zone ^

N/A N/A N/A Envir Qual Program 2

N/A N/A N/A Type of Qual.

Analysis Analysis Analysis EQ Reports (Reference 7)

ON-NRFE-10-21 ON-NRFE-13-1 NRFE-14-1 NRFE-14-1 As-Built EQRR (Reference 2}*

2.1.03.06.i-U3-EQRR-POOXXX 2.1.03.06.i-U3-EQRR-POOXXX 2.1.03.06.i-U3-EQRR-POOXXX

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 9 of 10 Equipment Name^

Tag No/

Seismic Cat. 1 ^

Ciass 1E/

Quai. For Harsh Envir.^3 Envir.

Zone ^

Envir Qua!

Program 2

Type of Quai.

EQ Reports (Reference 7)

As-Built EQRR (Reference 2)"

Control Rod Drive Mechanisms (CRDMs) (69 Locations)

RXS-MV-11 BOB/ 11808/ 11810/11 COS/ 11C07/

11C09/ 11C11/ 11D04/ 11 DOB/ 11D08/ 11D10/

11D12/11E03/11E05/11E07/11E09/11E11/

11E13/ 11F02/ 11F04/ 11 FOB/ 11F08/ 11F10/

11F12/ 11F14/ 11G03/ 11G05/11G07/11G09/

11G11/11G13/11H02/11H04/11 HOB/11H08/

11H10/ 11H12/11H14/11J03/ 11J05/ 11J07/

11J09/ 11J11/ 11J13/ 11K02/ 11K04/ 11KOB/

11K08/ 11K10/ 11K12/ 11K14/ 11L03/ 11 LOS/

11L07/ 11L09/ 11 L11 / 11L13/ 11M04/ 11 MOB/

11M08/ 11M10/ 11M12/ 11NOS/ 11N07/ 11N09/

11N11/11P0B/11P08/11P10 Yes No/No N/A N/A Analysis APP-MV11-S3R-002 2.1.03.0B.i-U3-EQRR-PCDXXX Incore instrument QuickLoc Assemblies (8 Locations)

RXS-MY-Y11 through Y18 Yes N/A N/A Anaiysis APP-MV01-S3R-002 2.1.03.0B.i-U3-EQRR-PCDXXX Source Range Detectors (4)

RXS-JE-NE001A/ NE0018/ NE001C/ NE001D Yes Yes/ Yes 1

E*

Type Testing Analysis APP-JE92-V8R-001 /

APP-JE92-V8R-002 2.1.03.0B.i-U3-EQRR-PCDXXX Intermediate Range Detectors (4)

RXS-JE-NE002A/ NE0028/ NE002C/ NE002D Yes Yes/ Yes 1

E*S Type Testing Anaiysis APP-JE92-V8R-001 /

APP-JE92-V8R-002 2.1.03.0B.i-U3-EQRR-PCDXXX Power Range Detectors -

Lower (4)

RXS-JE-NE003A/ NE0038/ NE003C/ NE003D Yes Yes/ Yes 1

E*S Type Testing Anaiysis APP-JE92-V8R-001 /

APP-JE92-V8R-002 2.1.03.0B.i-U3-EQRR-PCDXXX

U.S. Nuclear Regulatory Commission ND-18-0419 Enclosure Page 10 of 10 Equipment Name^

Tag No/

Seismic Cat. I ^

Class 1E/

Qual. For Harsh Envir.*

Envir.

Zone ^

Envir Qual Program 2

Type of Qual.

EQ Reports (Reference 7)

As-Built EQRR (Reference 2)"

Power Range Detectors -

Upper (4)

RXS-JE-NE004A/ NE004B/ NE004C/ NE004D Yes Yes/ Yes 1

E* S Type Testing Analysis APP-JE92-VBR-001 /

APP-JE92-VBR-002 2.1.03.06.1-U3-EQRR-PCDXXX Notes:

+Excerpt from COL Appendix C Table 2.1.3-1

1. See Table 3D.5-1 of UFSAR 2.

E = Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)

S = Qualified for submergence or operation with spray

  • =

Harsh Environment

3. Dash (-) Indicates not applicable
4. The Unit 4 As-Bullt EQRR are numbered "2.1.03.06.I-U4-EQRR-PCDXXX"
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