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

Michael J. Yox 7825 River Road Regulatory Affairs Director WaynesiDoro, GA 30830 LSouthern Nuclear Vogtie 3 & 4 706-848-6459 tei 410-474-8587 ceii myox @southe rnco. com JAN 2 5 2018 Docket Nos.: 52-025 52-026 ND-18-0045 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 2.1.03.06.1 findex Number 751 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 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 not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Companywill, 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.

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 Electric Generating 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 D. A. Bost (w/o enclosures)

M M. D. Rauckhorst (w/o enclosures)

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

M D. L. McKinney M M. J. Yox M D. L. Fulton M J. D. Williams M F. H. Willis Ms. A. L. Pugh M A. 8. Parton M W. A. Sparkman M C. E. Morrow Ms. K. M. Stacy M . M. K. Washington M . J. P. Redd Ms. A. C. Chamberlain M D. R. Culver M R. L. Beiike M . 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) Unit 3 and Unit 4 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. The seismic Category I equipment identified in Table2.1.3-1 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 basisaccident without loss of safety 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, 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.

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-built Class 1Eequipment and the associated wiring, cables, and terminations iocated in a harsh environment.

Acceptance Criteria:

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

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

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

i) Areport exists and 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 of safety function for the time required to perform the safety function.

ii) Areport exists and concludes thatthe 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.

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 3 of 10 ITAAC ComDietion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Reactor System (RXS) components identified as seismic Category Ior 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.

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

To assure that seismic Category Icomponents can withstand seismic design basis loads without lossof 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 conductedof 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). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment A document the results of the inspection and conclude that the seismic CategoryIcomponents are located on the Nuclear Island.

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

Seismic Category Icomponents in the Table require type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category Ivalves, 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 (Reference4).

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 thesafety-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 API 000 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 Acontain applicable test reports and associated documentation and conclude that the seismic Category Iequipment can withstand seismic design basis loads without loss of safety function.

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

An inspection (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. 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 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 employedfor 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 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 analyzed conditions, IEEE Standard 344-1987 (Reference 5) 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 1E components in the Table are qualified bytype testing and/or analyses. Class 1E 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 Aidentifies 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 usedto qualify API 000 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 exist before, during, and following a design basis accident without loss of safety function for the 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) 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/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 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 that the as-built harsh environment Class 1E equipment 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 that the ITAAC Acceptance Criteria requirements are met:

  • The seismic Category I equipment identified in Table 2.1.3-1 is locatedon the Nuclear Island;
  • A report exists and concludes that the seismic Category Iequipment can withstand seismic design basis loads without loss of safety function;
  • Areport existsand concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions;
  • Areport 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
  • Areport exists andconcludes that the as-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, 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 tothe 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.

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 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

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 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 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)

Ciass 1E/ Envir EQ Reports Equipment Seismic Quai. For Envir. Quai Type of As-Buiit EQRR Tag No/ (Reference Name"^ Cat. i ^ Harsh Zone ^ Program Quai. (Reference 2)"

Envir.^3 2 7)

APP- 2.1.03.06.i-U3-RV (Reactor Yes N/A N/A Analysis MV01- EQRR-RXS-MV-01 -

Vessel) ZOR-101 PCDXXX-Rev 0 Reactor Type 2.1.03.06.i-U3-Upper Testing APP-MI01-RXS-MI-01 Yes - N/A N/A EQRR-Internals & S3R-002 PCDXXX-Rev 0 Assembly Analysis Reactor Type 2.1.03.06.i-U3-Lower Testing APP-MI01-RXS-MI-02 Yes - N/A N/A EQRR-Internals & S3R-002 PODXXX-Rev 0 Assembly Analysis

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 8 of 10 Class IE/ Envir EG Reports Equipment Seismic Quai. For Envir. Qua! Type of As-Buiit EQRR Tag No.* (Reference Name^ Cat. i

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

Envir.*

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/

Fuel G06/ G07/ G08/ G09/ G10/ G11/ G12/ G13/ Type ON-NRFE-2.1.03.06.1-U3-Assemblies G14/ G15/ HOI/ H02/ H03/ H04/ H05/ H06/ H07/ Testing 10-21 Yes N/A N/A EQRR-(157 H08/ H09/ H10/ H11/ HI2/ HI3/ HI4/ H15/J01/ & ON-NRFE-POOXXX-Rev 0 locations) J02/ J03/ J04/ J05/ J06/ J07/ J08/ J09/ J10/ J11 / Analysis 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/

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/

Rod Cluster 008/ 010/ E03/ E05/ E07/ E09/ El 1/ El 3/ F02/ Type Oontrol 2.1.03.06.1-U3-F04/ F12/ F14/ G03/ G05/ G07/ G09/ G11 / G13/ Testing Assemblies N/A NRFE-14-1 EQRR-H04/ H08/ H12/ J03/ J05/ J07/ J09/ J11 / J13/ Yes N/A (ROOAs) &

K02/ K04/ K12/ K14/ L03/ L05/ L07/ L09/ L11/ POOXXX-Rev 0 (minimum 53 Analysis L13/ M06/ M08/ M10/ N05/ N07/ N09/ N11/ P06/

locations)

P10 Gray Rod Type Cluster 2.1.03.06.I-U3-RXS-FG-608/ 004/ 012/ F06/ F08/ F10/ H02/ Testing Assemblies Yes N/A N/A NRFE-14-1 EQRR-H06/ H10/ H14/ K06/ K08/ K10/ M04/ M12/ P08 &

(GR0As)(16 POOXXX-Rev 0 Analysis locations)

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 9 of 10 Class IE/ Envir EQ Reports Equipment Seismic Quai. For Envir. Quai Type of As-Built EQRR Tag No/ (Reference Name^ Cat. 1 + Harsh Zone ^ Program Quai. (Reference 2)^

2 7)

Envir.^

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/

Control Rod Type 11F12/ 11F14/ 11G03/ 11G05/11G07/ 11G09/ APP- 2.1.03.0B.i-U3-Drive Testing 11G11/11G13/11H02/ 11H04/ 11 HOB/11H08/ Yes No/No N/A N/A MV11- EQRR-Mechanisms &

11H10/ 11H12/ 11H14/ 11J03/ 11J05/ 11J07/ S3R-002 PCDXXX-Rev 0 (CRDMs) (69 Analysis 11J09/ 11J11/ 11J13/ 11K02/ 11K04/ 11KOB/

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

11L07/ 11L09/ 11L11/ 11L13/ 11M04/ 11M0B/

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

11N11/11P0B/11P08/11P10 Incore Type Instrument APP- 2.1.03.0B.i-U3-Testing QuickLoc RXS-MY-Y11 through Y18 Yes - N/A N/A MV01- EQRR-Assemblies S3R-002 PCDXXX-Rev 0 Analysis (8 Locations)

Type APP-JE92-Source 2.1.03.0B.i-U3-Testing V8R-001 /

Range RXS-JE-NE001A/ NE0018/ NE001C/ NE001D Yes Yes/ Yes 1 E* EQRR-

& APP-JE92-Detectors (4) PCDXXX-Rev 0 Analysis V8R-002 Type APP-JE92-Intermediate 2.1.03.0B.i-U3-Testing V8R-001 /

Range RXS-JE-NE002A/ NE0028/ NE002C/ NE002D Yes Yes/ Yes 1 E*S EQRR-

& APP-JE92-Detectors (4) PCDXXX-Rev 0 Analysis V8R-002 Type APP-JE92-Power Range 2.1.03.0B.i-U3-Testing V8R-001 /

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

& APP-JE92-Lower (4) PCDXXX-Rev 0 1Analysis V8R-002

U.S. Nuclear Regulatory Commission ND-18-0045 Enclosure Page 10 of 10 Class IE/ Envir EQ Reports Equipment Seismic Qual. For Envir. Qual Type of As-Bullt EQRR Tag No.* (Reference Name* Cat. 1

  • Harsh Zone ^ Program Qual. (Reference 2)*

2 7)

Envir.*

Type APP-JE92-Power Range 2.1.03.06.I-U3-Testing VBR-001 /

Detectors - RXS-JE-NE004A/ NE004B/ NE004C/ NE004D Yes Yes/ Yes 1 E*S EQRR-

& APP-JE92-Upper (4) PCDXXX-Rev 0 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 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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