ND-18-0045, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.i (Index Number 75)

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Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.i (Index Number 75)
ML18032A260
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 01/25/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-18-0045
Download: ML18032A260 (14)
v • d • e


Text

LSouthern Nuclear JAN 2 5 2018 Docket Nos.:

52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road WaynesiDoro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox @southernco. com ND-18-0045 10CFR 52.99(c)(3)

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 2.1.03.06.1 findex Number 751 Ladies and Gentlemen:

Pursuantto 10 CFR52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as ofJanuary 16, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.03.06.1 [Index Number 75] has notbeen completed greater than 225-days prior to initial fuel load. The Enclosure describes the planfor completing this ITAAC. Southern Nuclear Operating Companywill, at a later date, provide additional notifications for ITAAC that have not been completed 225-daysprior to initial fuel load.

This notification is informed bythe guidance described in NEI 08-01, Industry Guideline forthe 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, oranalyses 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.

J\\mnda Pu^h -ftr Michael J. Yox Regulatory Affairs Director Vogtie 3 &4

U.S. Nuclear Regulatory Commission ND-18-0045 Page 2 of 4

Enclosure:

Vogtle ElectricGenerating Plant (VEGP) Unit 3 and Unit 4 Compietion Plan for Uncompleted ITAAC 2.1.03.06.1 [Index Number 75]

MJY/PGLyamw

U.S. Nuclear Regulatory Commission ND-18-0045 Page 3 of 4 To:

Southern Nuclear Operating Company / Georgia Power Company M

M M

M M

M M

M M

M M

M M

M M

M M

D. A. Bost (w/o enclosures)

M. D. Rauckhorst (w/o enclosures)

M. D. Meier D. H. Jones (w/o enclosures)

D. L. McKinney M. J. Yox D. L. Fulton J. D. Williams F. H. Willis Ms. A. L. Pugh A. 8. Parton W. A. Sparkman C. E. Morrow Ms. K. M. Stacy

. M. K. Washington

. J. P. Redd Ms. A. C. Chamberlain D. R. Culver R. L. Beiike

. 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. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Oalethorpe Power Corporation Mr. K. T. Haynes Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0045 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westlnahouse 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. 8. DiTommaso Mr. J. L. Coward Ms. N. E. Deangells 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-18-0045 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-18-0045 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Completion Plan for Uncompleted ITAAC 2.1.03.06.1 [Index Number 75]

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 2 of 10 ITAAC Statement Design Commitment:

6. Theseismic 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 loss of safety function for the time required to perform the safety function.

Inspections. Tests. Analvses:

i) Inspection will be performed toverify thattheseismic Category Iequipment identified in Table 2.1.3-1 is located on the Nuclear Island.

ii) Type tests, analyses, ora combination of type tests andanalyses of seismic Category I equipment will be performed.

ill) Inspection will be performed for the existence of a report verifying thatthe as-built equipment including anchorageis seismically bounded bythe tested or analyzed conditions.

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

ii) Inspection will be performed of theas-built Class1Eequipment andtheassociated wiring, cables, and terminations iocated in a harsh environment.

Acceptance Criteria:

i) The seismic Category Iequipment identified in Table 2.1.3-1 islocated onthe Nuclear Island.

ii) Areport exists andconcludes thatthe seismic Category Iequipment canwithstand seismic design basis loads without loss of safety function.

iii) Areport exists andconcludes thatthe as-built equipment including anchorage isseismically bounded by the tested or analyzed conditions.

i) Areport exists andconcludes thatthe Class 1Eequipment identified in Table 2.1.3-1 as being qualified for a harsh environment canwithstand theenvironmental conditions that would exist before, during, andfollowing a design basisaccident without lossof safety function for the time required to perform the safety function.

ii) Areport exists andconcludes thatthe as-built Class1Eequipment andtheassociated wiring, cables, and terminations identified inTable 2.1.3-1 as being qualified for a harsh environment are bounded bytype tests, analyses, or a combination oftype tests and analyses.

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 3 of 10 ITAAC ComDietion Description This ITAAC requires that inspections, tests, and analysesbe performed and documented to ensurethe Reactor System (RXS) components identified as seismic Category IorClass1E in the Combined License (COL) Appendix C,Table 2.1.3-1 (theTable) are designed and constructed in accordance with applicable requirements.

\\) The seismic Category I eouioment identified in Table 2.1.3-1 is located on the Nuclear Island.

To assure that seismicCategory Icomponentscan withstand seismicdesign basis loads without lossof safety function, all the components in the Table are designed to be located on the seismic Category INuclear Island. In accordance with Equipment Qualification (EG)

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

W) A report exists and concludes that the seismic Cateaorv Iequipment can withstand seismic design basis loads without loss of safetv function.

Seismic Category Icomponents in theTable require type tests and/or analyses todemonstrate structural integrity and operability. Structural integrity of theseismic Category Ivalves, as well as other passive seismic Category Imechanical equipment, isdemonstrated by analysis in accordance with American Societyof Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidanceofASME QME-1-2007 (Reference4).

Safety-related (Class 1E) electrical equipment in theTable isseismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). This equipment includes safety-related (Class 1E) field sensors andthesafety-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, orcombination) used for each component in theTable isidentified in Attachment A. Additional information about themethods used toqualify API 000 safety-related equipment isprovided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6). The EG Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation and conclude thattheseismic Category Iequipment canwithstand seismic design basisloads without lossof safety function.

iiil A reoort exists and concludes that the as-built eouioment includinganchorage is seismicallv bounded bv the tested or analvzed conditions.

An inspection (Reference 1) isconducted to confirm thesatisfactory 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. Thedocumentation of installed configuration of

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 4 of 10 seismically qualified components includes photographs and/or sketches/drawings of equipment/mounting/interfaces.

As part ofthe seismic qualification program, consideration is givento the definition of the clearances needed around the equipment mounted in the plant to permit the equipment to move during a postulatedseismic event without causing impact between adjacent pieces ofsafety-related equipment. This is done as part of seismic testing by measuring the maximum dynamic relative displacement ofthe top and bottom of the equipment. EQ Reports (Reference 7) identify the equipmentmounting employedforqualification 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. In accordance with NEI 08-01, Section 9.5, inspection ofthe RXS equipment mounting and verification ofcritical attributes from the seismicanalyses are performed at other than the final installed location, due to inaccessibility of the equipment after installation.

Attachment A identifiesthe EQRR (Reference 2) completed to verify that the as-built seismic 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 reoort exists and concludes that the Class 1E eouioment 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 reouired to oerform the safetv function.

The harsh environment Class 1Ecomponents in the Tableare qualified bytypetestingand/or analyses. Class1Eelectrical component type testing isperformed in accordance with IEEE Standard323-1974 (Reference 9) and RG 1.89(Reference 10)to meetthe requirements of 10 CFR 50.49. Type testing ofsafety-related equipment meets the requirements of10CFR Part50,Appendix A, General Design Criterion 4. Attachment Aidentifies the EQ program and specific qualification method for each safety-related mechanical orClass1Eelectrical component located in a harsh environment. Additional information about the methods usedto qualify API000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 6).

EQ Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation and conclude that the equipment can withstand the environmental conditions that would existbefore, during, and following a designbasis 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 eouioment and the associated wiring, cables, and terminations identified in Table 2.1.3-1 as being Qualified for a harsh environment are bounded bv tvoe tests, analvses. or a combination of tvoe tests and analvses.

An inspection (Reference 1) isconducted of the RXS toconfirm thesatisfactory installation of the Class 1E components inthe Table. The inspection verifies the equipmentlocation, make/model/serial number, as-designed equipmentmounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the component is mounted are bounded bythe tested and/oranalyzed conditions. 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-18-0045 Enclosure Page 5 of 10 inspection and conclude thatthe as-built harsh environment Class 1Eequipment and the associated wiring, cables, and terminations are bounded bythe qualified configuration and IEEE Standard 323-1974 (Reference 9).

Together, these reports (References 2 and 7) provide evidence thatthe ITAAC Acceptance Criteria requirements are met:

The seismicCategory Iequipment identified in Table2.1.3-1 is locatedon the Nuclear Island; Areport exists and concludes thatthe seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function; Areport existsand concludes thatthe as-built equipment including anchorageis seismically bounded by the tested or analyzed conditions; Areport exists and concludes thatthe Class 1Eequipment identified in Table 2.1.3-1 as being qualified for a harsh environment canwithstand the environmental conditions that would exist before, during, andfollowing a design basis accident without lossof safety function for the time required to performthe safety function; and Areport exists andconcludes that theas-built Class 1E equipment and theassociated wiring, cables, and terminations identified in Table 2.1.3-1 as being qualified for a harsh environment are bounded bytype tests, analyses, ora combination of type tests and analyses.

References 2 and 7 are available for NRC inspection as partofthe Unit 3 and Unit 4 ITAAC 2.1.03.06.1 Completion Packages (References 11 and 12, 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 tothe subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 76, 77, 81,and82,found norelevant ITAAC findings associated with this ITAAC.

References favailabie for NRC inspection) 1.

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

2. EG As-Built Reconciliation Reports 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 ofNuclear 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

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 6 of 10 5.

IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification 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 Reports as identified inAttachmentA
8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipmentfor Nuclear Power Plants"
9. IEEEStandard 323-1974, "IEEE Standard for Qualifying Class 1E Equipmentfor Nuclear Power Generating Stations"
10. Regulatory Guide 1.89, Rev 1,"Environmental Qualification of Certain Electric Equipment Important to Safetyfor Nuclear Power Plants" 11.2.1.03.06.i-U3-CP-Rev X, "Completion Packagefor Unit 3 ITAAC 2.1.03.06.i [Index Number 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 for the ITAAC Closure Process Under 10CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 7 of 10 Attachment A System: Reactor System (RXS)

Equipment Name"^

Tag No/

Seismic Cat. i ^

Ciass 1E/

Quai. For Harsh Envir.^3 Envir.

Zone ^

Envir Quai Program 2

Type of Quai.

EQ Reports (Reference 7)

As-Buiit 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-Rev 0 Reactor Upper Internals Assembly RXS-MI-01 Yes N/A N/A Type Testing Analysis APP-MI01-S3R-002 2.1.03.06.i-U3-EQRR-PCDXXX-Rev 0 Reactor Lower Internals Assembly RXS-MI-02 Yes N/A N/A Type Testing Analysis APP-MI01-S3R-002 2.1.03.06.i-U3-EQRR-PODXXX-Rev 0

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 8 of 10 Equipment Name^

Fuel Assemblies (157 locations)

Rod Cluster Oontrol Assemblies (ROOAs)

(minimum 53 locations)

Gray Rod Cluster Assemblies (GR0As)(16 locations)

Tag No.*

RXS-FA-A07/ A08/ A09/ 605/ 806/ 607/ 608/

609/ 610/611/ 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/ E12/ E13/ E14/

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

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

G06/ G07/ G08/ G09/ G10/ G11/ G12/ G13/

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

H08/ H09/ H10/ H11/ HI2/ HI3/ HI4/ 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/ Ml 0/ N11/ N12/ P05/ P06/ P07/

P08/P09/P10/P11/ R07/ R08/ R09 RXS-FR-606/ 610/ 005/ 007/ 009/ 011/ 006/

008/ 010/ E03/ E05/ E07/ E09/ El 1/ El 3/ 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/ M10/ N05/ N07/ N09/ N11/ P06/

P10 RXS-FG-608/ 004/ 012/ F06/ F08/ F10/ H02/

H06/ H10/ H14/ K06/ K08/ K10/ M04/ M12/ P08 Seismic Cat. i

  • Yes Yes Yes Class IE/

Quai. For Harsh Envir.*

Envir.

Zone ^

N/A N/A N/A Envir Qua!

Program 2

N/A N/A N/A Type of Quai.

Type Testing Analysis Type Testing Analysis Type Testing Analysis EG Reports (Reference 7)

ON-NRFE-10-21 ON-NRFE-13-1 NRFE-14-1 NRFE-14-1 As-Buiit EQRR (Reference 2Y 2.1.03.06.1-U3-EQRR-POOXXX-Rev 0 2.1.03.06.1-U3-EQRR-POOXXX-Rev 0 2.1.03.06.I-U3-EQRR-POOXXX-Rev 0

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 9 of 10 Equipment Name^

Tag No/

Seismic Cat. 1 +

Class IE/

Quai. For Harsh Envir.^

Envir.

Zone ^

Envir Quai 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 DOS/ 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/ 11L11/ 11L13/ 11M04/ 11M0B/

11M08/ 11M10/ 11M12/ 11N0S/ 11N07/ 11N09/

11N11/11P0B/11P08/11P10 Yes No/No N/A N/A Type Testing Analysis APP-MV11-S3R-002 2.1.03.0B.i-U3-EQRR-PCDXXX-Rev 0 Incore Instrument QuickLoc Assemblies (8 Locations)

RXS-MY-Y11 through Y18 Yes N/A N/A Type Testing Analysis APP-MV01-S3R-002 2.1.03.0B.i-U3-EQRR-PCDXXX-Rev 0 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-Rev 0 Intermediate Range Detectors (4)

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

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

APP-JE92-V8R-002 2.1.03.0B.i-U3-EQRR-PCDXXX-Rev 0 Power Range Detectors -

Lower (4)

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

E*S Type Testing 1Analysis APP-JE92-V8R-001 /

APP-JE92-V8R-002 2.1.03.0B.i-U3-EQRR-PCDXXX-Rev 0

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 10 of 10 Equipment Name*

Tag No.*

Seismic Cat. 1

  • Class IE/

Qual. For Harsh Envir.*

Envir.

Zone ^

Envir Qual Program 2

Type of Qual.

EQ Reports (Reference 7)

As-Bullt 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.I-U3-EQRR-PCDXXX-Rev 0 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 motoroperator,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-Rev 0"
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