ND-18-0266, Voglte, Units 3 and 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.05 (Index Number 291)

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Voglte, Units 3 and 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.05 (Index Number 291)
ML18057A434
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 02/23/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.3.02.05.i, ND-18-0266
Download: ML18057A434 (12)
v • d • e


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Southern Nuclear FEB 2 3 2018 Docket Nos.:

52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road WayneslDoro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0266 10CFR 52.99(c)(3)

Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit3 and Unit4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.02.05.1 [Index Number 291]

Ladies and Gentlemen:

Pursuantto 10 CFR52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 23, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) Item 2.3.02.05.1

[Index Number 291] 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 forwhich required inspections, tests, or analyses have not been performed or have been only partially completed.

All ITAAC will befully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC tosupport the Commission finding thatall acceptance criteria are met prior to plant operation, as required by10 CFR52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contactTom Petrakat 706-848-1575.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.05.1 [Index Number 291]

MJY/PGUamw

U.S. Nuclear Regulatory Commission ND-18-0266 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Companv 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. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. 0. 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. P. B. Donnelly 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 Oolethoroe Power Corporation Mr. R. B. Brinkman MunlciDal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0266 Page 3 of 3 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. 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 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-18-0266 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-18-0266 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.05.1 [Index Number 291]

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 2 of 9 ITAAC Statement Design Commitment

5. The seismic Category I equipment identified in Table 2.3.2-1 can withstand seismic design basis loads without loss of safety function.

6.a) The Class 1E equipment identified inTable 2.3.2-1 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 forthe time requiredto perform the safety function.

Insoections. Tests. Analvses i) Inspection will be performed to verify thatthe seismic Category Iequipment identified in Table 2.3.2-1 is located on the Nuclear Island.

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

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

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

ii) Inspection will be performed of theas-built Class 1E equipment andtheassociated wiring, cables, and terminations located in a harsh environment.

Acceptance Criteria i) The seismic Category Iequipment identified in Table 2.3.2-1 is located on the Nuclear Island.

ii) Areport exists and concludes that the seismic Category Iequipment can withstand seismic design basis dynamic loadswithout loss of safetyfunction.

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

i) Areport exists and concludes that the Class 1E equipment identified in Table 2.3.2-1 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 thetime required to performthe safety function.

ii) Areport exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, andterminations identified in Table 2.3.2-1 as being qualified for a harsh environment are bounded by type tests, analyses, ora combination of type tests andanalyses.

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 3 of 9 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Chemical and Volume Control System (CVS) equipment identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 2.3.2-1 (the Table) is designed and constructed in accordance with applicable requirements.

i) The seismic Category I eouioment identified in Table 2.3.2-1 is located on the Nuclear Island.

To assure that seismic Category I equipment can withstand seismic design basis loads without loss of safety function, all the equipment in the Table is designed to be located on the seismic Category I Nuclear Island. In accordance with EquipmentQualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the CVS to confirmthe 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 A document the results of the inspection and conclude that the seismic Category I equipment is located on the Nuclear Island.

ih A report exists and concludes that the seismic Cateoorv I eauioment can withstand seismic desion basis dvnamic loads without loss of safetv function.

Seismic Category Iequipmentin the Table requirestype tests and/or analyses to demonstrate structural integrity and operability. Structural integrity ofthe seismic Category Ivalves is demonstrated byanalysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of the subsetof 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 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 active valve accessories such as electric actuators, position switches, pilot solenoid valves and electrical connectorassemblies. The specific qualification method (i.e.,type testing, analysis, or combination) usedfor each piece ofequipment 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 Acontain applicable test reports and associated documentation and conclude that the seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function.

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

An inspection (Reference 1)isconducted to confirm thesatisfactory installation of the seismically qualified equipment 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 ofinstalled configuration of

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 4 of 9 seismically qualified equipment 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) identifythe equipment mounting employed for qualificationand establish interface requirements for assuring that subsequent in-plantinstallation does not degrade the established qualification.

Interface requirements are defined based on the test configuration and other design requirements.

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 f^RC Regulatory Guide (RG) 1.100 (Reference 8).

i1 A reoort exists and concludes that the Class 1E eouioment identified in Table 2.3.2-1 as being Qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and followino a desion basis accident without loss of safetv function for the time reouired to perform the safetv function.

The harsh environment Class 1E equipment in the Table is qualified bytypetestingand/or analyses. Class 1E electrical equipment type testing isperformed in accordance with IEEE Standard 323-1974 (Reference 9)and RG 1.89 (Reference 10) to meet the requirements of 10CFR 50.49. Type testing of safety-related equipment meetsthe requirements of 10CFR Part 50, Appendix A, General Design Criterion 4. Attachment Aidentifies the EQ program and specific qualification method for each piece of safety-related mechanical equipment located in a harsh environment. Additional information about the methods used to qualify API000 safety-related equipment isprovided in the UFSAR Appendix 3D (Reference 6). EQ Reports (Reference 7) identified in Attachment Acontain applicable testreports and associated documentation and concludethat the equipmentcan withstand the environmental conditions thatwould exist before, during, andfollowing a design basisaccident without lossof safety function for the time required to perform the safety function.

iil A report exists and concludes that the as-built Class 1E eouioment and the associated wiring, cables, and terminations identified in Table 2.3.2-1 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 CVS to confirm the satisfactory installation of the Class1Eequipment in theTable. Theinspection verifies the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirmsthat the environmental conditionsforthe zone (Attachment A) inwhich the equipment ismounted are bounded by the tested and/or analyzed conditions. It also documents the installed configuration with photographs orsketches/drawings of equipment mounting and connections. The EQRR (Reference 2) identified in Attachment Adocument this inspection and conclude that the as-built harsh environment Class 1E equipment and the associated wiring, cables, and terminations are bounded by thequalified configuration and IEEE Standard 323-1974 (Reference 9).

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 5 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 2.3.2-1 is located on the Nuclear Island; A report exists and concludes that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function; A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions; A report exists and concludes that the Class 1E equipment identified in Table 2.3.2-1 as being qualifiedfor 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 2.3.2-1 as beingqualified fora harsh environmentare bounded by type tests, analyses, or a combination oftype tests and analyses.

References 2 and 7 are available for NRCinspection as part of the Unit 3 and Unit 4 ITAAC 2.3.02.05.i Completion Packages (References 11 and 12, respectively).

List of ITAAC Findings In accordance with plantproceduresfor ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review ofall ITAAC findings and associated corrective actions.

This review, which included nowconsolidated ITAAC Indexes 292, 293, 294 and 295, found the following relevant ITAAC findings associated with this ITAAC:

1) Notice of Nonconformance (NGN) 99901412/2012-201-02 (Closed)

References ^available for NRC inspection) 1.

ND-xx-xx-001, "EG Walkdown ITAACGuideline"

2. EGAs-Built Reconciliation Reports (EORR) as identified in Attachment Afor Units 3 and 4
3. American Society of Mechanical Engineers (ASME) Boiler and PressureVessel (B&PV)

Code,Section III, "RulesforConstruction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda

4. ASME QME-1-2007, "Qualification of Active Mechanical EquipmentUsed 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 Equipmentfor Nuclear Power Generating Stations"

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 6 of 9 6.

Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment" 7.

Equipment Qualification (EQ) 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, Rev1, "Environmental Qualification ofCertain Electric Equipment Important to Safety for Nuclear Power Plants" 11.2.3.02.05.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.3.02.05.i [Index Number 291]"

12.2.3.02.05.i-U4-CP-RevX, "Completion Package for Unit 4 ITAAC 2.3.02.05.1 [Index Number 291]"

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

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 7 of 9 Attachment A System; Chemical and Volume Control System (CVS)

Equipment Name ^

Tag No.

  • Seismic Cat. i ^

Ciass 1E/

Quai. for Harsh Envir.+ 3 Envir.

Zone^

Envir Quai Program^

Type of Quai.

EQ Reports (Reference 7)

As-Buiit EQRR (Reference 2)

RCS Purification Motor-operated Isolation Valve CVS-PL-V001 Yes YesA'es 1

M*ES Type Testing

& Analysis APP-PV01-VBR-012/

APP-PV01-VBR-011 2.3.02.05.i-U3-EQRR-PCDXXX-RevO RCS Purification Motor-operated Isolation Valve CVS-PL-V002 Yes YesA'es 1

M*ES Type Testing

& Analysis APP-PV01-VBR-012/

APP-PV01-VBR-011 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 RCS Purification Motor-operated Isolation Valve CVS-PL-V003 Yes YesA'es 1

M*ES Type Testing

& Analysis APP-PV01-VBR-014/

APP-PV01-VBR-013 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Resin Flush Line Containment Isolation Valve CVS-PL-V040 Yes

-/-

NA NA Type Testing

& Analysis APP-PV10-VBR-008/

APP-PV10-VBR-007 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Resin Flush Line Containment Isolation Valve CVS-PL-V041 Yes

-/-

NA NA Type Testing

& Analysis APP-PV10-VBR-008 /

APP-PV10-VBR-007 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Demineralizer Resin Flush Line Containment Isolation Thermal Relief Valve CVS-PL-V042 Yes

-/-

NA NA Type Testing

& Analysis APP-PV16-VBR-002 /

APP-PV16-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Letdown Containment Isolation Valve CVS-PL-V045 Yes YesA'es 1

M* E S Type Testing

& Analysis APP-PV14-VBR-002 /

APP-PV14-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Letdown Containment Isolation Valve CVS-PL-V047 Yes Yes/No NA NA Type Testing

& Analysis APP-PV14-VBR-002 /

APP-PV14-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Letdown Line Containment Isolation Thermal Relief Valve CVS-PL-V058 Yes

-/-

NA NA Type Testing

& Analysis APP-PV16-VBR-002 /

APP-PV16-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Makeup Return Line Bypass Check Valve CVS-PL-V067 Yes

-/-

NA NA Type Testing

& Analysis APP-PV02-VBR-012/

APP-PV02-VBR-011 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 8 of 9 Equipment Name ^

Tag No.

  • Seismic Cat. 1 ^

Class 1E/

Qua!, for Harsh Envir.+

Envir.

Zone^

Envir Qual Program^

Type of Qual.

EG Reports (Reference 7)

As-Built EORR (Reference 2)

CVS Purification Return Line Pressure Boundary Check Valve CVS-PL-V080 Yes

-/-

NA NA Analysis APP-PV03-VBR-014/

APP-PV03-VBR-013 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Purification Return Line Pressure Boundary Isolation Check Valve CVS-PL-V081 Yes

-/-

NA NA Type Testing

& Analysis APP-PV14-VBR-190002

/

APP-PV14-VBR-190001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Purification Return Line Pressure Boundary Check Valve CVS-PL-V082 Yes

-/-

NA NA Analysis APP-PV03-VBR-014 /

APP-PV03-VBR-013 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Auxiliary Pressurizer Spray Line Pressure Boundary Vaive CVS-PL-V084 Yes Yes/Yes 1

M*ES Type Testing

& Anaiysis APP-PV14-VBR-002 /

APP-PV14-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-RevO CVS Auxiliary Pressurizer Spray Line Pressure Boundary Check Valve CVS-PL-V085 Yes

-/-

NA NA Analysis APP-PV02-VBR-012/

APP-PV02-VBR-011 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V090 Yes Yes/No NA NA Type Testing

& Analysis APP-PV01-VBR-012/

APP-PV01-VBR-011 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Makeup Line Containment isolation Motor-operated Vaive CVS-PL-V091 Yes YesA'es 1

M*ES Type Testing

& Analysis APP-PV01-VBR-012/

APP-PV01-VBR-011 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Zinc Injection Containment Isolation Valve ORC CVS-PL-V092 Yes Yes/Yes 10 M*ES Type Testing

& Analysis APP-PV14-VBR-002 /

APP-PV14-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Zinc injection Containment Isolation Valve IRC CVS-PL-V094 Yes Yes / Yes 1

M*ES Type Testing

& Analysis APP-PV14-VBR-002/

APP-PV14-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Zinc Addition Line Ctmt Isol Thermal Relief Valve CVS-PL-V098 Yes

-/-

NA NA Type Testing

& Analysis APP-PV16-VBR-002/

APP-PV16-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0

U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 9 of 9 Equipment Name ^

Tag No.

  • Seismic Cat. i ^

Class 1E/

Qual. for Harsh Envir.+ 3 Envir.

Zone^

Envir Qual Program^

Type of Qual.

EQ Reports (Reference 7)

As-Built EQRR (Reference 2)

CVS Makeup Line Containment Isolation Thermal Relief Valve CVS-PL-V100 Yes

-/-

NA NA Analysis APP-PV02-VBR-012 /

APP-PV02-VBR-011 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Demineralized Water Isolation Valve CVS-PL-V136A Yes Yes/No NA NA Type Testing

& Analysis APP-PV11-VBR-004/

APP-PV11-VBR-003 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Demineralized Water Isolation Valve CVS-PL-V136B Yes Yes/No NA NA Type Testing

& Analysis APP-PV11-VBR-004/

APP-PV11-VBR-003 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Hydrogen Injection Containment Isolation Check Valve IRC CVS-PL-V217 Yes

-/-

NA NA Analysis APP-PV02-VBR-017/

APP-PV02-VBR-018 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 CVS Hydrogen Injection Containment Isolation Vaive ORC CVS-PL-V219 Yes YesA'es 10 M*ES Type Testing

& Analysis APP-PV14-VBR-002 /

APP-PV14-VBR-001 2.3.02.05.i-U3-EQRR-PCDXXX-Rev 0 Notes:

+ Excerpt from COL Appendix C Table 2.3.2-1 1.

See Table 3D.5-1 of UFSAR

2. E - Electrical EquipmentProgram (limit switch and the motoroperator, squib operator, soienoid operator)

M-Mechanical Equipment Program (valve)

S = Qualified for submergence or operation with spray

  • - Harsh Environment 3.

Dash (-) indicates not applicable 4.

The Unit 4 As-Built EQRR are numbered "2.3.02.05.i-U4-EQRR-PCDXXX-Rev 0"

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