ND-19-1333, Unit 4 - Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.i (Index Number 75)

Unit 4 - Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.i (Index Number 75)

ML19305A429
Person / Time
Site:	Vogtle
Issue date:	10/31/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1333
Download: ML19305A429 (14)

Text

Michael J. Yox 7825 River Road

^Southern NucIear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel OCT 3 1 2019 Docket Nos.: 52-025 52-026 ND-19-1333 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 Resubmittai of Notice of Uncompleted ITAAC 225-davs Prior to initial Fuel Load item 2.1.03.06.1 [index Number 751 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 30, 2019, Vogtle Electric Generating Plant(VEGP) IJnit 3 and Unit 4 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-18-0419

[ML18100A068] dated April 9, 2018. This resubmittai supersedes ND-18-0419 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 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. Yox Regulatory Affairs Director Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-19-1333 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/GCW/sfr

U.S. Nuclear Regulatory Commission ND-19-1333 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

Mr. M. D. Meier (w/o enclosures)

Mr. D. H. Jones (w/o enclosures)

Mr. G. Chick Mr. M. Page Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes 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 Mr. W.Jones (w/o enclosures)

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1333 Page 4 of 4 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse 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. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-19-1333 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.03.06.1 [Index Number 75]

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 2 of 10 ITAAC Statement Design Commitment:

6. The seismic Category i equipment identified in Table 2.1.3-1 can withstand seismic design basis loads without loss of safety function.

9.a) The Class 1E equipment 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 of safety function for the time required to perform the safety function.

Inspections. Tests. Analvses:

I) Inspection will be performed to verify that the seismic Category I equipment Identified In Table 2.1.3-1 Is 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.

III) Inspection will be performed for the existence of a report verifying that the as-bullt equipment Including anchorage Is selsmlcally bounded by the tested or analyzed conditions.

I) Type tests, analysis, or a combination of type tests and analysis will be performed on Class 1E equipment located In a harsh environment.

II) Inspection will be performed of the as-bullt Class IE equipment and the associated wiring, cables, and terminations located In a harsh environment.

Acceptance Criteria:

I) The seismic Category I equipment Identified In Table 2.1.3-1 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-bullt equipment Including anchorage Is selsmlcally bounded by the tested or analyzed conditions.

I) A report exists and concludes that the Class 1E equipment 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 of safety function for the time required to perform the safety function.

II) A report exists and concludes that the as-bullt Class 1E equipment and 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-19-1333 Enclosure Page 3 of 10 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Reactor System (RXS)components identified as seismic Category I or Class 1E in the Combined License(COL) Appendix C, Table 2.1.3-1 (the Table) are designed and constructed in accordance with applicable requirements.

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

To assure that seismic Category I components can withstand seismic design basis loads without loss of safety function, all the components in the Table are designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EG)

Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the RXS to confirm the satisfactory installation of the seismically qualified components. The inspection includes verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). Fuel assemblies and rod cluster control assemblies are not installed in their final location until after the 10 CFR 52.103(g)finding has been made as part of initial fuel load. Per item ii below, the assemblies are seismically qualified when located on the nuclear island. In accordance with NEI 08-01, Section 9.5, inspection of the fuel assemblies and rod cluster control assemblies are performed at other than the final installed location, due to inaccessibility of the equipment after installation. The EG As-Built Reconciliation Reports (EQRR)(Reference 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category I components are located on the Nuclear Island.

ii) A report exists and concludes that the seismic Cateoorv I equipment can withstand seismic design basis loads without loss of safetv 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 equipment, is demonstrated by analysis in accordance with American Society of Mechanical Engineers(ASME)Code Section III (Reference 3). Functionality of 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 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 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 in the 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 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.

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 4 of 10 III) A report exists and concludes that the as-bullt eouloment Includlno anchoraoe Is selsmlcallv bounded by the tested or analyzed conditions.

An Inspection (Reference 1) Is conducted to confirm the satisfactory Installation of the selsmlcally qualified components In the Table. The Inspection verifies the equipment make/model/serlal number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other Interfaces. The documentation of Installed configuration of selsmlcally qualified components 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. This Is done 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. In accordance with NEI 08-01, Section 9.5, Inspection of the RXS equipment mounting and verification of critical attributes from the seismic analyses are performed at other than the final Installed location, due to Inaccessibility of the equipment after Installation.

Attachment A Identifies the EQRR (Reference 2)completed to verify that the as-bullt seismic Category I equipment listed In the Table, Including anchorage, are selsmlcally bounded by the tested or analyzed conditions, IEEE Standard 344-1987(Reference 5) and NRG Regulatory Guide(RG) 1.100 (Reference 8).

I) A report exists and concludes that the Class 1E eouloment Identified In Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, durlna. and followlno a deslon basis accident without loss of safetv function for the time required to perform the safetv function.

The harsh environment Class 1E components In the Table are qualified by type testing and/or analyses. Class IE electrical component type testing Is performed In accordance with IEEE Standard 323-1974(Reference 9) and RG 1.89 (Reference 10) to meet the requirements of 10 CFR 50.49. Type testing of safety-related equipment meets the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment A Identifies the EQ program and specific qualification method for each safety-related mechanical or Class 1E electrical component located In a harsh environment. Additional Information about the methods used to qualify API000 safety-related equipment Is provided In the UFSAR Appendix 3D (Reference 6).

EQ Reports (Reference 7) Identified In Attachment A contain applicable test 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 for the time required to perform the safety function.

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 5 of 10

11) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.1.3-1 as beino aualified for a harsh environment are bounded by type tests, analyses, or a combination of tvoe tests and analyses.

An inspection (Reference 1) is conducted of the RXS to confirm the satisfactory installation of the Class 1E components in the Table. The inspection verifies the equipment location, make/modei/seriai number, as-designed equipment mounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the component is mounted are bounded by the tested and/or analyzed conditions. It also documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 2) identified in Attachment A document this inspection and conclude that the as-built harsh environment Class 1E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974(Reference 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 2.1.3-1 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;

• A report exists and concludes that the as-built equipment including anchorage is seismicaliy bounded by the tested or analyzed conditions;

• A report exists and concludes that the Class 1E equipment 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 of safety function for the time required to perform the safety function; and

• A report exists and concludes that the as-built Class 1E equipment and 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.

References 2 and 7 are available for NRC inspection as part of the 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 to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 76, 77, 81, and 82,found no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 6 of 10 References ^available for NRC inspection)

1. ND-RA-001-014, Rev. 2, "EQ Walkdown ITAAC Guideline"

2. EQ As-Built Reconciliation Reports as identified in Attachment A for 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 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 in Attachment A

8. Regulatory Guide 1.100, Rev. 2,"Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

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

10. Regulatory Guide 1.89, Rev 1, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants" 11.2.1.03.06.i-U3-CP-Rev X, ITAAC Completion Package 12.2.1.03.06.i-U4-CP-RevX, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 7 of 10 Attachment A System: Reactor System (RXS)

Class 1E/ Envir Equipment EG Reports Tag No.*

Seismic Quai. For Envir. Qua! Type of As-Buiit EGRR Name* (Reference Cat. i

• Harsh Zone ^ Program Quai. (Reference 2Y Envir.*^ 2 7)

RV (Reactor APP- 2.1.03.06.1-RXS-MV-01 Yes N/A N/A Analysis MV01- U3/4-EQRR-Vessel) -

ZOR-101 PCDXXX Reactor Upper 2.1.03.06.1-APP-MI01-RXS-MI-01 Yes -

N/A N/A Analysis U3/4-EQRR-Internals S3R-002 Assembly PCDXXX Reactor Lower 2.1.03.06.1-APP-MI01-RXS-MI-02 Yes -

N/A N/A Analysis U3/4-EQRR-Internals S3R-002 Assembly PCDXXX

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 8 of 10 Class 1E/ Envlr Equipment EQ Reports Tag No/

Seismic Qual. For Envlr. Qual Type of As-Bullt EQRR Name^ Cat. 1 (Reference Harsh Zone ^ Program Qual. (Reference 2Y Envlr.^ 2 7)

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

609/ 610/ 611/ 004/ 005/ 006/ 007/ 008/ 009/

010/ 011/ 012/ D03/ D04/ 005/ D06/ 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/

Fuel G06/ G07/ G08/ G09/ G10/ G11/ G12/ G13/ ON-NRFE-Assemblies G14/ G15/ HOI/ H02/ H03/ H04/ H05/ H06/ H07/ 2.1.03.06.1-10-21 (157 H08/ H09/ H10/ H11/ H12/ H13/ H14/ H15/ J01/

Yes N/A N/A Analysis U3/4-EQRR-ON-NRFE-locations) J02/ J03/ J04/ J05/ J06/ J07/ J08/ J09/ J10/ J11/ POOXXX 13-1 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/

LI2/ LI 3/ LI 4/ M03/ M04/ M05/ M06/ M07/ M08/

M09/ M10/ Ml 1/ Ml2/ Ml3/ N04/ N05/ N06/

N07/ N08/ N09/ N10/ Ml 1/ N12/ P05/ P06/ P07/

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

Rod Cluster 008/ 010/ E03/ E05/ E07/ E09/ El 1/ El 3/ F02/

Oontrol F04/ F12/ F14/ G03/ G05/ G07/ G09/ G11/ G13/ 2.1.03.06.1-Assemblies H04/ H08/ H12/ J03/ J05/ J07/ J09/ J11/ J13/ Yes N/A N/A Analysis NRFE-14-1 U3/4-EQRR-(ROOAs)

K02/ K04/ K12/ K14/ L03/ L05/ L07/ L09/ L11/ POOXXX (minimum 53 LI 3/ M06/ M08/ M10/ N05/ N07/ N09/ N11/ P06/

locations)

P10 Gray Rod Cluster 2.1.03.06.1-RXS-FG-608/ 004/ 012/ F06/ F08/ F10/ H02/

Assemblies Yes N/A N/A Analysis NRFE-14-1 U3/4-EQRR-H06/ H10/ H14/ K06/ K08/ K10/ M04/ M12/ P08 (GROAs)(16 POOXXX locations)

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 9 of 10 Giass 1E/ Envir Equipment EQ Reports Tag No/

Seismic Quai. For Envir. Quai Type of As-Buiit EQRR (Reference Name^ Cat. 1 + Harsh Zone ^ Program Quai. (Reference 2)*

Envir.* 2 7)

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

11C09/11C11/11D04/11D06/11D08/11D10/

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

11E13/ 11F02/ 11F04/ 11 FOG/ 11F08/ 11F10/

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

Drive APP- 2.1.03.0G.i-11G11/11G13/11H02/11H04/11H0G/11H08/

Mechanisms Yes No/No N/A N/A Analysis MV11- U3/4-EQRR-11H10/ 11H12/ 11H14/ 11J03/ 11 JOS/ 11J07/

(CRDMs)(69 S3R-002 PCDXXX 11J09/ 11J11/ 11J13/ 11K02/ 11K04/ 11KOG/

Locations) 11K08/11K10/11K12/11K14/11L03/11L0S/

11L07/11L09/11L11/11L13/11M04/11M0G/

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

11N11/11P0G/11P08/11P10 Incore Instrument APP- 2.1.03.0G.i-QuickLoc RXS-MY-Y11 through Y18 Yes -

N/A N/A Analysis MV01- U3/4-EQRR-Assemblies S3R-002 PCDXXX (8 Locations)

Source Type APP-JE92-2.1.03.0G.i-Range RXS-JE-NE001A/ NE0018/ NE001C/ NE001D Testing V8R-001 /

Yes Yes/ Yes 1 E* U3/4-EQRR-

& APP-JE92-Detectors(4) PCDXXX Analysis V8R-002 Intermediate Type APP-JE92-2.1.03.0G.i-Range RXS-JE-NE002A/ NE0028/ NE002C/ NE002D Testing V8R-001 /

Yes Yes/ Yes 1 E*S U3/4-EQRR-

& APP-JE92-Detectors(4) PCDXXX Analysis V8R-002 Power Range Type APP-JE92-2.1.03.0G.i-Detectors -

Testing V8R-001 /

RXS-JE-NE003A/ NE0038/ NE003C/ NE003D Yes Yes/ Yes 1 E*S U3/4-EQRR-

& APP-JE92-Lower (4) PCDXXX Analysis V8R-002

U.S. Nuclear Regulatory Commission ND-19-1333 Enclosure Page 10 of 10 Class 1E/ Envir Equipment EQ Reports Tag No/

Seismic Quai. For Envir. Quai Type of As-Built EQRR Name^ Cat. i Harsh Zone ^ Program (Reference Quai. (Reference 2)"

Envir.^3 2 7)

Power Range Type APP-JE92-2.1.03.06.1-Detectors - RXS-JE-NE004A/ NE004B/ NE004C/ NE004D Testing VBR-001 /

Yes Yes/ Yes 1 E*S U3/4-EQRR-

& APP-JE92-Upper(4) PCDXXX Analysis VBR-002 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 3/4 As-Built EQRR are numbered "2.1.03.06.i-U3/4-EQRR-PCDXXX"