ND-18-0185, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.05a.i (Index Number 165)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.05a.i (Index Number 165)

ML18054A413
Person / Time
Site:	Vogtle
Issue date:	02/22/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0185
Download: ML18054A413 (20)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii F£B 2 2 2018 myox @southernco.com Docket Nos.: 52-025 52-026 ND-18-0185 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 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.05a.i [Index Number 165]

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.05a.i

[Index Number 165] 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 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-18-0185 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.05a.i [Index Number 165]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0185 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. McKlnney M M. J. Vox M D. L. Fulton M J. D. Williams M 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 Oolethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0185 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinqhouse 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. 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., GDS 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-18-0185 Enclosure Page 1 of 16 Southern Nuclear Operating Company ND-18-0185 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Pian for Uncompleted ITAAC 2.2.03.05a.i [Index Number 165]

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 2 of 16 ITAAC Statement Desian Commitment:

5.a) The seismic Category I equipment identified in Table 2.2.3-1 can withstand seismic design basis loads without loss of safety function.

7.a) The Class 1E equipment identified in Table 2.2.3-1 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 and valves identified in Table 2.2.3-1 are 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 performedfor the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

i) Type tests, analyses, or a combination oftype tests and analyses will be performed on Class 1E equipment located in a harsh environment.

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

Acceptance Criteria:

i) The seismic Category Iequipment identified in Table 2.2.3-1 is locatedon the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function. Forthe PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights.

iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded bythe tested or analyzed conditions. Forthe PXS containment recirculation and IRWST screens, a report exists and concludes that the as-built screens including their anchorage are bounded bythe seismic loads and also post-accident operating loads, including head loss and debris weights.

i) A report exists and concludes that the Class 1E equipment identified inTable 2.2.3-1 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 forthe time required to perform the safety function.

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 3 of 16 ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Passive Core Cooling System (PXS) equipment identified as seismic Category I or Class IE in the Combined License (COL) Appendix C, Table 2.2.3-1 (the Table) is designed and constructed in accordance with applicable requirements.

n The seismic Cateoorv I eauioment identified in Table 2.2.3-1 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 Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the PXS to confirm the satisfactory installation of the seismicallyqualified 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.

W) A reoort exists and concludes that the seismic Cateoorv I equipment can withstand seismic desion basis dvnamic loads without loss of safetv function. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dvnamic loads and also oost-accident ooeratino loads, including head loss and debris weights.

Seismic Category I equipment in the Table requirestype tests and/or analyses to demonstrate structural integrity and operability. Structural integrity ofthe 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 ofthe subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1 -2007 (Reference 4). Structural integrity ofthe in-containment refueling water storage tank (IRWST) is demonstrated by analysis in accordance with American Concrete Institute (ACI) Standard 349-01 (Reference 5) and American Institute of Steel Construction (AISC) Specification N690 (Reference 6). Structural integrity of the pH adjustment baskets is demonstrated byanalysis in accordance with AISC Specification N690 (Reference 6).

Safety-related (Class 1E) electrical equipment in the Table is seismically qualified bytype testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 7). 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 piece of equipment 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 8). The EG Reports (Reference 9) identified

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 4 of 16 in Attachment A contain applicable test reports and associated documentation and conclude that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function. For the PXS containment recirculation and IRWST screens, the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights.

iii) A report exists and concludes that the as-built equipment includino anchorage is seismicallv bounded bv the tested or analyzed conditions. For the PXS containment recirculation and IRWST screens, a reoort exists and concludes that the as-built screens includino their anchorage are bounded bv the seismic loads and also post-accident ooeratino loads, including head loss and debris weights.

An inspection (Reference 1) is conducted to confirm the satisfactory 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. The documentation of installed configuration of 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 9) 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.

Attachment A identifies the EQRR (Reference 2) completed to verify that the as-built seismic Category Iequipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference7), and NRG Regulatory Guide (RG) 1.100 (Reference 10). Forthe PXS containment recirculation and IRWST screens, the as-built screens including their anchorage are bounded by the seismic loads and also post-accident operating loads, including head loss and debris weights.

n A report exists and concludes that the Class 1E equipment identified in Table 2.2.3-1 as being 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 required to perform the safetv function.

The harsh environment Class 1E equipment in the Table is qualified by type testing and/or analyses. Class 1E electrical equipment type testing is performed in accordance with IEEE Standard 323-1974 (Reference 11) and RG 1.89 (Reference 12) 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 piece ofsafety-related mechanical or Class 1E electrical equipment located in a harsh environment. Additional information about the methods used to qualify API 000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 8).

EQ Reports (Reference 9) identified in Attachment A contain applicable test reports and

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 5 of 16 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.

ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.3-1 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 PXS to confirm the satisfactory installation of the Class 1E equipment 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 equipment 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 Adocument this 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 11).

Together, these reports (References 2 and 9) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismicCategory I equipment identified in Table 2.2.3-1 is located on the Nuclear Island;

• Areport exists and concludes thatthe seismic Category Iequipment can withstand seismic design basis dynamic loads without lossof safety function. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights;

• Areport exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the as-built screens including their anchorage are bounded by the seismic loads and also post-accident operating loads, including head loss and debris weights;

• Areport exists and concludes that the Class 1E equipment identified in Table 2.2.3-1 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 and concludes that the as-built Class 1E equipment and theassociated wiring, cables, and terminations identified in Table 2.2.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination oftype tests and analyses.

References 2 and 9 are available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.2.03.05a.i Completion Packages (References 13 and 14, respectively).

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 6 of 16 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.

This review, which included now consolidated ITAAC Indexes 166,167,170, and 171, found the following relevant ITAAC findings associated with this ITAAC:

1) Notice of Nonconformance (NGN) 99901441/2014-201 -03 (Open)

2) NON 99901431/2013-201-01 (Closed)

3) NON 99901377/2012-201 -02 (Closed)

4) NON 99901377/2012-201-03 (Closed)

5) NON 99900404/2012-201-01 (Closed)

6) NON 99900404/2012-201-02 (Closed)

7) NON 99900404/2012-201-03 (Closed)

Before submission of the ITAAC Closure Notification (ICN), corrective actions will be completed for relevant findings identified prior to ICN submission.

References (available for NRG inspection)

1. ND-xx-xx-001, "EQ Walkdown IT/\AC Guideline"

2. EQ As-Built Reconciliation Reports (EQRR) 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, "Rulesfor 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. American Concrete Institute (ACI) Standard 349-01, "Code Requirements for Nuclear Safety Related Concrete Structures," 2001.

6. American National Standards Institute (ANSI) / American Institute of Steel Construction (AISC) N690-1994, "Specification for the Design, Fabrication and Erection of Safety-Related Steel Structures for Nuclear Facilities"

7. IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipmentfor Nuclear Power Generating Stations"

8. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment"

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 7 of 16

9. Equipment Qualification (EG) Reports as identified in Attachment A

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

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

12. Regulatory Guide 1.89, Rev 1, "Environmental Qualification of Certain Electric Equipment Importantto Safety for Nuclear Power Plants" 13.2.2.03.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.2.03.05a.i [Index Number 165]"

14.2.2.03.05a.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.2.03.05a.i [Index Number 165]"

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

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 8 of 16 Attachment A System; Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qua! Type of EQ Reports As-Built EORR Equipment Name ^ Tag No.

• Quai. Harsh Cat. i^3 Zone ^ Program ^ Quai. (Reference 9) (Reference 2)"

Envir.

Passive Residual Heat 2.2.03.05a.i-U3-EQRR-Removal Heat Exchanger PXS-ME-01 Yes -/- N/A N/A Analysis APP-ME02-Z0R-100 PCDXXX (PRHR HX) 2.2.03.05a.i-U3-EQRR-Accumulator Tank A PXS-MT-01A Yes -/- N/A N/A Analysis APP-MT02-Z0R-101 PCDXXX 2.2.03.05a.i-U3-EQRR-Accumulator Tank B PXS-MT-01B Yes -/- N/A N/A Analysis APP-MT02-Z0R-101 PCDXXX Core Makeup Tank (CMT) N/A N/A Analysis APP-MT01-Z0R-001 2.2.03.05a.i-U3-EQRR-PXS-MT-02A Yes A PCDXXX 2.2.03.05a.i-U3-EQRR-CMTB PXS-MT-02B Yes -/- N/A N/A Analysis APP-MT01-Z0R-001 PCDXXX 2.2.03.05a.i-U3-EQRR-IRWST PXS-MT-03 Yes -/- N/A N/A Analysis APP-MT03-VFR-XXX PCDXXX 2.2.03.05a.i-U3-EQRR-IRWST Screen A PXS-MY-Y01A Yes -/- N/A N/A Analysis APP-MY03-VDR-001 PCDXXX 2.2.03.05a.i-U3-EQRR-IRWST Screen B PXS-MY-Y01B Yes -/- N/A N/A Analysis APP-MY03-VDR-001 PCDXXX 2.2.03.05a.i-U3-EQRR-IRWST Screen C PXS-MY-Y01C Yes -/ - N/A N/A Analysis APP-MY03-VDR-001 PCDXXX Containment Recirculation 2.2.03.05a.i-U3-EQRR-PXS-MY-Y02A Yes N/A N/A Analysis APP-MY03-VDR-001 Screen A PCDXXX Containment Recirculation 2.2.03.05a. i-U3-EQRR-PXS-MY-Y02B Yes -/- N/A N/A Analysis APP-MY03-VDR-001 Screen B PCDXXX 2.2.03.05a. i-U3-EQRR-pH Adjustment Basket 3A PXS-MY-Y03A Yes N/A N/A Analysis APP-MY07-Z0C-002 PCDXXX 2.2.03.05a. i-U3-EQRR-pH Adjustment Basket 3B PXS-MY-Y03B Yes N/A N/A Analysis APP-MY07-Z0C-002 PCDXXX 2.2.03.05a.i-U3-EQRR-pH Adjustment Basket 4A PXS-MY-Y04A Yes N/A N/A Analysis APP-MY07-Z0C-002 PCDXXX

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 9 of 16 Attachment A System: Passive Core Cooling System Giass 1E/

Seismic Envir. Envir Quai Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No. ^ Cat. i+3 Quai. Harsh Zone ^ Program ^ Quai. (Reference 9) (Reference 2) ^

Envir.

2.2.03.05a.i-U3-EQRR-pH Adjustment Basket 48 PXS-MY-Y04B Yes N/A N/A Analysis APP-MY07-Z0C-002 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 1A PXS-MY-Y81 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 1B PXS-MY-Y82 Yes N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 1C PXS-MY-Y83 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 1D PXS-MY-Y84 Yes N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 2A PXS-MY-Y85 Yes N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 2B PXS-MY-Y86 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 2C PXS-MY-Y87 Yes N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX 2.2.03.05a.i-U3-EQRR-Downspout Screen 2D PXS-MY-Y88 Yes - / - N/A N/A Analysis APP-MY02-Z0C-001 PCDXXX Type CMT A Inlet Isolation APP-PV01-VBR-012/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V002A Yes YesA'es 1 M* ES Testing &

Motor-operated Valve Analysis APP-PV01-VBR-011 PCDXXX Type CMT B Inlet Isolation APP-PV01-VBR-012/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V002B Yes YesA'es 1 M* ES Testing &

Motor-operated Valve Analysis APP-PV01-VBR-011 PCDXXX Type CMT A Discharge Testing &

APP-PV14-VBR-002/ 2.2.03.05a. i-U3-EQRR-PXS-PL-V014A Yes Yes/Yes 1 M* ES Isolation Valve APP-PV14-VBR-001 PCDXXX Analysis

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 10 of 16 Attachment A System: Passive Core Cooling System CiasslE/

Seismic Envir. Envir Quai Type of EG Reports As-Buiit EQRR Equipment Name

• Tag No.

• Qual. Harsh Zone ^ Program ^ Quai. (Reference 9) (Reference 2)"

Cat.

Envir.

Type CMT B Discharge APP-PV14-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V014B Yes Yes/Yes 1 M* ES Testing &

Isolation Valve APP-PV14-VBR-001 PCDXXX Analysis Type CMT A Discharge APP-PV14-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V015A Yes YesA'es 1 M*ES Testing &

Isolation Valve APP-PV14-VBR-001 PCDXXX Analysis Type CMT B Discharge APP-PV14-VBR-002 / 2.2.03.05a. i-U3-EQRR-PXS-PL-V015B Yes YesA'es 1 M* ES Testing &

Isolation Valve APP-PV14-VBR-001 PCDXXX Analysis CMT A Discharge Check APP-PV03-VBR-004/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V016A Yes -/ - N/A N/A Analysis Valve APP-PV03-VBR-003 PCDXXX CMT B Discharge Check PXS-PL-V016B APP-PV03-VBR-004/ 2.2.03.05a.i-U3-EQRR-Yes N/A N/A Analysis Valve APP-PV03-VBR-003 PCDXXX CMT A Discharge Check PXS-PL-V017A APP-PV03-VBR-004 / 2.2.03.05a.i-U3-EQRR-Yes N/A N/A Analysis Valve APP-PV03-VBR-003 PCDXXX CMT B Discharge Check APP-PV03-VBR-004 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V017B Yes N/A N/A Analysis Valve APP-PV03-VBR-003 PCDXXX Type Accumulator A Pressure APP-PV16-VBR-002/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V022A Yes N/A N/A Testing &

Relief Valve APP-PV16-VBR-001 PCDXXX Analysis Type Accumulator B Pressure APP-PV16-VBR-002/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V022B Yes - / - N/A N/A Testing &

Relief Valve APP-PV16-VBR-001 PCDXXX Analysis Type Accumulator A Discharge APP-PV01-VBR-012/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V027A Yes -/- N/A N/A Testing &

Isolation Valve APP-PV01-VBR-011 PCDXXX Analysis Type Accumulator B Discharge APP-PV01-VBR-012/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V027B Yes N/A N/A Testing &

Isolation Valve APP-PV01-VBR-011 PCDXXX Analysis

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 11 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Quai Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No. ^ Quai. Harsh Zone ^ Program ^ Quai. (Reference 9) (Reference 2)

• Envir.*'

Accumulator A Discharge APP-PV03-VBR-014 / 2.2.03.05a.l-U3-EQRR-PXS-PL-V028A Yes -/- N/A N/A Analysis Check Valve APP-PV03-VBR-013 PCDXXX Accumulator B Discharge APP-PV03-VBR-014 / 2.2.03.05a.l-U3-EQRR-PXS-PL-V028B Yes -/- N/A N/A Analysis Check Valve APP-PV03-VBR-013 PCDXXX Accumulator A Discharge APP-PV03-VBR-014 / 2.2.03.05a.l-U3-EQRR-PXS-PL-V029A Yes -/- N/A N/A Analysis Check Valve APP-PV03-VBR-013 PCDXXX Accumulator B Discharge APP-PV03-VBR-014 / 2.2.03.05a.l-U3-EQRR-PXS-PL-V029B Yes -/- N/A N/A Analysis Check Valve APP-PV03-VBR-013 PCDXXX Nitrogen Supply Type APP-PV14-VBR-002 / 2.2.03.05a.l-U3-EQRR-Containment Isolation PXS-PL-V042 Yes Yes/No N/A N/A Testing &

APP-PV14-VBR-001 PCDXXX Valve Analysis Nitrogen Supply APP-PV02-VBR-016 / 2.2.03.05a.l-U3-EQRR-Containment Isolation PXS-PL-V043 Yes -/- N/A N/A Analysis APP-PV02-VBR-015 PCDXXX Check Valve Type PRHR HX Inlet Isolation APP-PV01-VBR-012 / 2.2.03.05a.l-U3-EQRR-PXS-PL-V101 Yes YesA'es 1 M*ES Testing &

Motor-operated Valve APP-PV01-VBR-011 PCDXXX Analysis Type APP-PV20-VBR-002 / 2.2.03.05a.l-U3-EQRR-PRHR HX Control Valve PXS-PL-V108A Yes YesA'es 1 M*ES Testing &

APP-PV20-VBR-001 PCDXXX Analysis Type APP-PV20-VBR-002 / 2.2.03.05a.l-U3-EQRR-PRHR HX Control Valve PXS-PL-V108B Yes Yes/Yes 1 M*ES Testing &

APP-PV20-VBR-001 PCDXXX Analysis Containment Reclrculatlon Type APP-PV01-VBR-012 / 2.2.03.05a.l-U3-EQRR-A Isolation Motor-operated PXS-PL-V117A Yes YesA'es 1 M*ES Testing &

APP-PV01-VBR-011 PCDXXX Valve Analysis Containment Reclrculatlon Type APP-PV01-VBR-012 / 2.2.03.05a.l-U3-EQRR-B Isolation Motor-operated PXS-PL-V117B Yes YesA'es 1 M*ES Testing &

APP-PV01-VBR-011 PCDXXX Valve Analysis

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 12 of 16 Attachment A System: Passive Core Cooling System Ciass IE/

Seismic Envir. Envir Quai Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No.

• Cat. i+3 Quai. Harsh Zone ^ Program ^ Quai. (Reference 9) (Reference 2) ^

Envir.

Type Containment Recirculation APP-PV70-VBR-003 / 2.2.03.05a. i-U3-EQRR-PXS-PL-V118A Yes Yes/Yes 1 M* ES Testing &

A Squib Valve APP-PV70-VBR-002 PCDXXX Analysis Type Containment Recirculation APP-PV70-VBR-003/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V118B Yes Yes/Yes 1 M*ES Testing &

B Squib Valve Analysis APP-PV70-VBR-002 PCDXXX Containment Recirculation APP-PV03-VBR-014/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V119A Yes -/- N/A N/A Analysis A Check Valve APP-PV03-VBR-013 PCDXXX Containment Recirculation APP-PV03-VBR-014/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V119B Yes -/- N/A N/A Analysis B Check Valve APP-PV03-VBR-013 PCDXXX Type Containment Recirculation APP-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V120A Yes Yes/Yes 1 M* ES Testing &

A Squib Valve APP-PV70-VBR-002 PCDXXX Analysis Type Containment Recirculation APP-PV70-VBR-003/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V120B Yes Yes/Yes 1 M*ES Testing &

B Squib Valve Analysis APP-PV70-VBR-002 PCDXXX IRWST Injection A Check APP-PV03-VBR-014/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V122A Yes -/- N/A N/A Analysis Vaive APP-PV03-VBR-013 PCDXXX IRWST Injection B Check APP-PV03-VBR-014/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V122B Yes -/- N/A N/A Analysis Valve APP-PV03-VBR-013 PCDXXX Type IRWST Injection A Squib APP-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V123A Yes Yes/Yes 1 M*ES Testing &

Valve APP-PV70-VBR-002 PCDXXX Analysis Type IRWST Injection B Squib APP-PV70-VBR-003/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V123B Yes Yes/Yes 1 M*ES Testing &

Valve APP-PV70-VBR-002 PCDXXX Analysis IRWST Injection A Check APP-PV03-VBR-014/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V124A Yes -/- N/A N/A Analysis Valve APP-PV03-VBR-013 PCDXXX

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 13 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name ^ Tag No. Qual. Harsh Program ^ (Reference 9) (Reference 2) ^

Cat. i Zone ^ Qual.

Envir.

IRWST Injection B Check PXS-PL-V124B APP-PV03-VBR-014/ 2.2.03.05a.i-U3-EQRR-Yes -/- N/A N/A Analysis Valve APP-PV03-VBR-013 PCDXXX Type IRWST Injection A Squib APP-PV70-VBR-003 / 2.2.03.05a. i-U3-EQRR-PXS-PL-V125A Yes YesA'es 1 M*ES Testing &

Valve APP-PV70-VBR-002 PCDXXX Analysis Type IRWST Injection B Squib PXS-PL-V125B APP-PV70-VBR-003 / 2.2.03.05a. i-U3-EQRR-Yes YesA'es 1 M*ES Testing &

Valve APP-PV70-VBR-002 PCDXXX Analysis Type IRWST Gutter Isolation APP-PV10-VBR-003/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V130A Yes Yes/Yes 1 M* ES Testing &

Valve APP-PV10-VBR-004 PCDXXX Analysis Type IRWST Gutter Isolation APP-PV10-VBR-003/ 2.2.03.05a.i-U3-EQRR-PXS-PL-V130B Yes YesA'es 1 M* ES Testing &

Valve APP-PV10-VBR-004 PCDXXX Analysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT A Level Sensor PXS-011A Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-CMT A Level Sensor PXS-011B Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT A Level Sensor PXS-011C Yes YesA^es 1 E* S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT A Level Sensor PXS-011D Yes Yes/Yes 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT B Level Sensor PXS-012A Yes Yes/Yes 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 14 of 16 Attachment A System: Passive Core Cooiing System Giass 1E/

Seismic Envir. Envir Quai Type of EG Reports As-Buiit EORR Equipment Name ^ Tag No. ^ Quai. Harsh Cat. i^3 Zone ^ Program Quai. (Reference 9) (Reference 2)

Envir.^

Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT B Level Sensor PXS-012B Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Anaiysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT B Level Sensor PXS-012C Yes YesA'es 1 E* S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT B Level Sensor PXS-012D Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Anaiysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT A Level Sensor PXS-013A Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Anaiysis Type APP-JE61-VBR-002/ 2.2.03.05a. i-U3-EQRR-CMT A Level Sensor PXS-013B Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT A Level Sensor PXS-013C Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Anaiysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT A Level Sensor PXS-013D Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Anaiysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT B Level Sensor PXS-014A Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-CMT B Level Sensor PXS-014B Yes YesA'es 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Anaiysis

U.S. Nuclear Regulatory Commission N D-18-0185 Enclosure Page 15 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name ^ Tag No.

• Qual. Harsh Cat. 1^3 Zone ^ Program ^ Qual. (Reference 9) (Reference 2) ^

Envir.

Type APP-JE61-VBR-002/ 2.2.03.05a. i-U3-EQRR-CMT B Level Sensor PXS-014C Yes Yes/Yes 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-CMT 8 Level Sensor PXS-014D Yes Yes/Yes 1 E*S Testing &

APP-JE61-VBR-001 PCDXXX Analysis Type IRWST Wide Range Level Testing &

APP-JE52-VBR-002/ 2.2.03.05a.i-U3-EQRR-PXS-046 Yes Yes/Yes 1 E*S Sensor APP-JE52-VBR-001 PCDXXX Analysis Type IRWST Wide Range Level APP-JE52-VBR-002/ 2.2.03.05a.i-U3-EQRR-PXS-047 Yes Yes/Yes 1 E*S Testing &

Sensor APP-JE52-VBR-001 PCDXXX Analysis Type IRWST Wide Range Level APP-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-048 Yes Yes/Yes 1 E*S Testing &

Sensor APP-JE52-VBR-001 PCDXXX Analysis Type APP-JE52-VBR-002/ 2.2.03.05a.i-U3-EQRR-PRHR HX Flow Sensor PXS-049A Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 PCDXXX Analysis Type APP-JE52-VBR-002 / 2.2.03.05a. i-U3-EQRR-PRHR HX Flow Sensor PXS-049B Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 PCDXXX Analysis Type Containment Flood-up APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-PXS-050 Yes Yes/Yes 1 E*S Testing &

Level Sensor APP-JE61-VBR-001 PCDXXX Analysis Type Containment Flood-up APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-PXS-051 Yes Yes/Yes 1 E*S Testing &

Level Sensor APP-JE61-VBR-001 PCDXXX Analysis

U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 16 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Quai Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No. ^ Quai. Harsh Cat. i Zone ^ Program ^ Quai. (Reference 9) (Reference 2) ^

Envir.

Type Containment Flood-up APP-JE61-VBR-002/ 2.2.03.05a.i-U3-EQRR-PXS-052 Yes YesA'es 1 E* S Testing &

Level Sensor APP-JE61-VBR-001 PCDXXX Analysis Type IRWST Lower Narrow APP-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-066 Yes YesA'es 1 E*S Testing &

Range Level Sensor APP-JE52-VBR-001 PCDXXX Analysis Type IRWST Lower Narrow APP-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-067 Yes YesA'es 1 E* S Testing &

Range Level Sensor APP-JE52-VBR-001 PCDXXX Anaiysis Type IRWST Lower Narrow APP-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-068 Yes YesA'es 1 E*S Testing &

Range Level Sensor APP-JE52-VBR-001 PCDXXX Analysis Type IRWST Lower Narrow APP-JE52-VBR-002 / 2.2.03.05a. i-U3-EQRR-PXS-069 Yes YesA'es 1 E*S Testing &

Range Level Sensor APP-JE52-VBR-001 PCDXXX Analysis RNS Suction Leak Test APP-PV17-VBR-004/ 2.2.03.05a. i-U3-EQRR-PXS-PL-V208A Yes -/- N/A N/A Analysis Valve APP-PV17-VBR-003 PCDXXX Notes:

+ Excerpt from COL Appendix C Table 2.2.3-1

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

2. E - Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)

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 "2.2.03.05a.i-U4-EQRR-PCDXXX"