ND-23-0162, ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165)

ML23200A036
Person / Time
Site:	Vogtle
Issue date:	07/19/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0162
Download: ML23200A036 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel July 19, 2023 Docket No.: 52-026 ND-23-0162 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i [Index Number 165]

Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)

Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.05a.i [Index Number 165] to demonstrate that the Passive Core Cooling System (PXS) components identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 2.2.3-1 are designed and constructed in accordance with applicable requirements.

The closure process for this ITAAC is based on 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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.03.05a.i [Index Number 165]

JMC/AD/sfr

U.S. Nuclear Regulatory Commission ND-23-0162 Page 2 of 2 cc: Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 1 of 16 Southern Nuclear Operating Company ND-23-0162 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.03.05a.i [Index Number 165]

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 2 of 16 ITAAC Statement Design 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, Analyses:

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 performed for 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 of type 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 I equipment identified in Table 2.2.3-1 is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of 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.

iii) A report 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.

i) 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, 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-23-0162 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 Determination Basis 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 1E in the Combined License (COL) Appendix C, Table 2.2.3-1 (the Table) is designed and constructed in accordance with applicable requirements.

i) The seismic Category I equipment 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 (EQ) ITAAC As-Built Walkdown Guideline and the EQ ITAAC As-built Installation Documentation Guideline (References 1 and 2), an inspection was conducted of the PXS to confirm the satisfactory installation of the seismically qualified equipment. The inspection included verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). The EQ As-Built Reconciliation Reports (EQRR) (Reference 3) identified in Attachment A documented the results of the inspection and concluded that the seismic Category I equipment is located on 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. 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.

Seismic Category I equipment in the Table requires 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 4). Functionality of the subset of active safety-related valves under seismic loads was determined using the guidance of ASME QME-1-2007 (Reference 5). Structural integrity of the in-containment refueling water storage tank (IRWST) was demonstrated by analysis in accordance with American Concrete Institute (ACI) Standard 349-01 (Reference 6) and American Institute of Steel Construction (AISC) Specification N690 (Reference 7). Structural integrity of the pH adjustment baskets was demonstrated by analysis in accordance with AISC Specification N690 (Reference 7).

Safety-related (Class 1E) electrical equipment in the Table was seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 8). 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 AP1000 safety-related equipment is provided in the Updated Final Safety

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 4 of 16 Analysis Report (UFSAR) Appendix 3D (Reference 9). The EQ Reports (Reference 10) identified 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 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.

An inspection (References 1 and 2) was conducted to confirm the satisfactory installation of the seismically qualified equipment in the Table. The inspection verified 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. When required, seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports (Reference

10) identified the equipment mounting employed for qualification and established 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 3) completed to verify that the as-built seismic Category I equipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 8), and NRC Regulatory Guide (RG) 1.100 (Reference 11). For the 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.

i) 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, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

The harsh environment Class 1E equipment in the Table is qualified by type testing and/or analyses. Class 1E electrical equipment type testing was performed in accordance with IEEE Standard 323-1974 (Reference 12) and RG 1.89 (Reference 13) 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 of safety-related mechanical or Class 1E electrical equipment located in a harsh environment. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 9).

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 5 of 16 EQ Reports (Reference 10) identified in Attachment A contain applicable test reports and associated documentation and concluded 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 by type tests, analyses, or a combination of type tests and analyses.

An inspection (Reference 1 and 2) was conducted of the PXS to confirm the satisfactory installation of the Class 1E equipment in the Table. The inspection verified the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirmed 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 documented the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 3) identified in Attachment A documents this inspection and concluded 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 12).

Together, these reports (References 3 and 10) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 2.2.3-1 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. 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;

• A report 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;

• 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, 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 2.2.3-1 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-23-0162 Enclosure Page 6 of 16 References 3 and 10 are available for NRC inspection as part of the Unit 4 ITAAC 2.2.03.05a.i Completion Package (References 14).

ITAAC Finding Review 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 closed notice of non-conformance (NON) associated with this ITAAC:

1) NON 99901441/2014-201-03 (Closed - ML14307A578)

2) NON 99901431/2013-201-01 (Closed - ML14091A361)

3) NON 99901377/2012-201-02 (Closed - ML16357A724)

4) NON 99901377/2012-201-03 (Closed - ML16357A724)

5) NON 99900404/2012-201-01 (Closed - ML16307A159)

6) NON 99900404/2012-201-02 (Closed - ML12313A461)

7) NON 99900404/2012-201-03 (Closed - ML12313A461)

The corrective actions for these findings have been completed and the findings are closed. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.03.05a.i (Reference 14) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.05a.i was performed for VEGP Unit 4 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with the approved plant programs and procedures.

References (available for NRC inspection)

1. ND-RA-001-014, EQ ITAAC As-Built Walkdown Guideline, Version 3.1

2. ND-RA-001-016, EQ ITAAC As-built Installation Documentation Guideline, Version 1.0

3. EQ As-Built Reconciliation Reports (EQRR) as identified in Attachment A

4. 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

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 7 of 16

5. ASME QME-1-2007, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, The American Society of Mechanical Engineers, June 2007

6. American Concrete Institute (ACI) Standard 349-01, "Code Requirements for Nuclear Safety Related Concrete Structures," 2001.

7. 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"

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

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

10. Equipment Qualification (EQ) Reports as identified in Attachment A

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

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

13. Regulatory Guide 1.89, Rev 1, Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants

14. 2.2.03.05a.i-U4-CP-Rev0, Completion Package for Unit 4 ITAAC 2.2.03.05a.i [Index Number 165]

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 8 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 Passive Residual Heat 2.2.03.05a.i-U4-EQRR-Removal Heat Exchanger PXS-ME-01 Yes -/- N/A N/A Analysis SV4-ME02-Z0R-001 PCD003 (PRHR HX) 2.2.03.05a.i-U4-EQRR-Accumulator Tank A PXS-MT-01A Yes -/- N/A N/A Analysis SV4-MT02-Z0R-102 PCD003 2.2.03.05a.i-U4-EQRR-Accumulator Tank B PXS-MT-01B Yes -/- N/A N/A Analysis SV4-MT02-Z0R-102 PCD003 Core Makeup Tank (CMT) 2.2.03.05a.i-U4-EQRR-PXS-MT-02A Yes -/- N/A N/A Analysis SV4-MT01-Z0R-101 A PCD003 2.2.03.05a.i-U4-EQRR-CMT B PXS-MT-02B Yes -/- N/A N/A Analysis SV4-MT01-Z0R-101 PCD003 2.2.03.05a.i-U4-EQRR-IRWST PXS-MT-03 Yes -/- N/A N/A Analysis SV4-1100-GCR-001 PCD003 2.2.03.05a.i-U4-EQRR-IRWST Screen A PXS-MY-Y01A Yes -/- N/A N/A Analysis SV4-MY03-VDR-001 PCD002 2.2.03.05a.i-U4-EQRR-IRWST Screen B PXS-MY-Y01B Yes -/- N/A N/A Analysis SV4-MY03-VDR-001 PCD002 2.2.03.05a.i-U4-EQRR-IRWST Screen C PXS-MY-Y01C Yes -/- N/A N/A Analysis SV4-MY03-VDR-001 PCD002 Containment Recirculation 2.2.03.05a.i-U4-EQRR-PXS-MY-Y02A Yes -/- N/A N/A Analysis SV4-MY03-VDR-001 Screen A PCD002 Containment Recirculation 2.2.03.05a.i-U4-EQRR-PXS-MY-Y02B Yes -/- N/A N/A Analysis SV4-MY03-VDR-001 Screen B PCD002 2.2.03.05a.i-U4-EQRR-pH Adjustment Basket 3A PXS-MY-Y03A Yes -/- N/A N/A Analysis APP-MY07-Z0C-002 PCD002 2.2.03.05a.i-U4-EQRR-pH Adjustment Basket 3B PXS-MY-Y03B Yes -/- N/A N/A Analysis APP-MY07-Z0C-002 PCD002 2.2.03.05a.i-U4-EQRR-pH Adjustment Basket 4A PXS-MY-Y04A Yes -/- N/A N/A Analysis APP-MY07-Z0C-002 PCD002

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 9 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 2.2.03.05a.i-U4-EQRR-pH Adjustment Basket 4B PXS-MY-Y04B Yes -/- N/A N/A Analysis APP-MY07-Z0C-002 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 1A PXS-MY-Y81 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 1B PXS-MY-Y82 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 1C PXS-MY-Y83 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 1D PXS-MY-Y84 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 2A PXS-MY-Y85 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 2B PXS-MY-Y86 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 2C PXS-MY-Y87 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 2.2.03.05a.i-U4-EQRR-Downspout Screen 2D PXS-MY-Y88 Yes -/- N/A N/A Analysis APP-MY02-Z0C-001 PCD002 Type CMT A Inlet Isolation SV4-PV01-VBR-012 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V002A Yes Yes/Yes 1 M*ES Testing &

Motor-operated Valve SV4-PV01-VBR-011 PCD001 Analysis Type CMT B Inlet Isolation SV4-PV01-VBR-012 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V002B Yes Yes/Yes 1 M*ES Testing &

Motor-operated Valve SV4-PV01-VBR-011 PCD001 Analysis Type CMT A Discharge SV4-PV14-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V014A Yes Yes/Yes 1 M*ES Testing &

Isolation Valve SV4-PV14-VBR-001 PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 10 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 Type CMT B Discharge SV4-PV14-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V014B Yes Yes/Yes 1 M*ES Testing &

Isolation Valve SV4-PV14-VBR-001 PCD001 Analysis Type CMT A Discharge SV4-PV14-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V015A Yes Yes/Yes 1 M*ES Testing &

Isolation Valve SV4-PV14-VBR-001 PCD001 Analysis Type CMT B Discharge SV4-PV14-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V015B Yes Yes/Yes 1 M*ES Testing &

Isolation Valve SV4-PV14-VBR-001 PCD001 Analysis CMT A Discharge Check SV4-PV03-VBR-004 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V016A Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-003 PCD001 CMT B Discharge Check SV4-PV03-VBR-004 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V016B Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-003 PCD001 CMT A Discharge Check SV4-PV03-VBR-004 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V017A Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-003 PCD001 CMT B Discharge Check SV4-PV03-VBR-004 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V017B Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-003 PCD001 Type Accumulator A Pressure SV4-PV16-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V022A Yes -/- N/A N/A Testing &

Relief Valve SV4-PV16-VBR-001 PCD001 Analysis Type Accumulator B Pressure SV4-PV16-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V022B Yes -/- N/A N/A Testing &

Relief Valve SV4-PV16-VBR-001 PCD001 Analysis Type Accumulator A Discharge SV4-PV01-VBR-012 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V027A Yes -/- N/A N/A Testing &

Isolation Valve SV4-PV01-VBR-011 PCD001 Analysis Type Accumulator B Discharge SV4-PV01-VBR-012 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V027B Yes -/- N/A N/A Testing &

Isolation Valve SV4-PV01-VBR-011 PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 11 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 Accumulator A Discharge SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V028A Yes -/- N/A N/A Analysis Check Valve SV4-PV03-VBR-013 PCD001 Accumulator B Discharge SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V028B Yes -/- N/A N/A Analysis Check Valve SV4-PV03-VBR-013 PCD001 Accumulator A Discharge SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V029A Yes -/- N/A N/A Analysis Check Valve SV4-PV03-VBR-013 PCD001 Accumulator B Discharge SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V029B Yes -/- N/A N/A Analysis Check Valve SV4-PV03-VBR-013 PCD001 Nitrogen Supply Type SV4-PV14-VBR-002 / 2.2.03.05a.i-U4-EQRR-Containment Isolation PXS-PL-V042 Yes Yes/No N/A N/A Testing &

SV4-PV14-VBR-001 PCD001 Valve Analysis Nitrogen Supply SV4-PV02-VBR-016 / 2.2.03.05a.i-U4-EQRR-Containment Isolation PXS-PL-V043 Yes -/- N/A N/A Analysis SV4-PV02-VBR-015 PCD001 Check Valve Type PRHR HX Inlet Isolation SV4-PV01-VBR-012 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V101 Yes Yes/Yes 1 M*ES Testing &

Motor-operated Valve SV4-PV01-VBR-011 PCD001 Analysis Type SV4-PV20-VBR-002 / 2.2.03.05a.i-U4-EQRR-PRHR HX Control Valve PXS-PL-V108A Yes Yes/Yes 1 M*ES Testing &

SV4-PV20-VBR-001 PCD001 Analysis Type SV4-PV20-VBR-002 / 2.2.03.05a.i-U4-EQRR-PRHR HX Control Valve PXS-PL-V108B Yes Yes/Yes 1 M*ES Testing &

SV4-PV20-VBR-001 PCD001 Analysis Containment Recirculation Type SV4-PV01-VBR-012 / 2.2.03.05a.i-U4-EQRR-A Isolation Motor-operated PXS-PL-V117A Yes Yes/Yes 1 M*ES Testing &

SV4-PV01-VBR-011 PCD001 Valve Analysis Containment Recirculation Type SV4-PV01-VBR-012 / 2.2.03.05a.i-U4-EQRR-B Isolation Motor-operated PXS-PL-V117B Yes Yes/Yes 1 M*ES Testing &

SV4-PV01-VBR-011 PCD001 Valve Analysis

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 12 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 Type Containment Recirculation SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V118A Yes Yes/Yes 1 M*ES Testing &

A Squib Valve SV4-PV70-VBR-002 PCD001 Analysis Type Containment Recirculation SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V118B Yes Yes/Yes 1 M*ES Testing &

B Squib Valve SV4-PV70-VBR-002 PCD001 Analysis Containment Recirculation SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V119A Yes -/- N/A N/A Analysis A Check Valve SV4-PV03-VBR-013 PCD001 Containment Recirculation SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V119B Yes -/- N/A N/A Analysis B Check Valve SV4-PV03-VBR-013 PCD001 Type Containment Recirculation SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V120A Yes Yes/Yes 1 M*ES Testing &

A Squib Valve SV4-PV70-VBR-002 PCD001 Analysis Type Containment Recirculation SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V120B Yes Yes/Yes 1 M*ES Testing &

B Squib Valve SV4-PV70-VBR-002 PCD001 Analysis IRWST Injection A Check SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V122A Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-013 PCD001 IRWST Injection B Check SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V122B Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-013 PCD001 Type IRWST Injection A Squib SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V123A Yes Yes/Yes 1 M*ES Testing &

Valve SV4-PV70-VBR-002 PCD001 Analysis Type IRWST Injection B Squib SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V123B Yes Yes/Yes 1 M*ES Testing &

Valve SV4-PV70-VBR-002 PCD001 Analysis IRWST Injection A Check SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V124A Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-013 PCD001

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 13 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 IRWST Injection B Check SV4-PV03-VBR-014 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V124B Yes -/- N/A N/A Analysis Valve SV4-PV03-VBR-013 PCD001 Type IRWST Injection A Squib SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V125A Yes Yes/Yes 1 M*ES Testing &

Valve SV4-PV70-VBR-002 PCD001 Analysis Type IRWST Injection B Squib SV4-PV70-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V125B Yes Yes/Yes 1 M*ES Testing &

Valve SV4-PV70-VBR-002 PCD001 Analysis Type IRWST Gutter Isolation SV4-PV10-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V130A Yes Yes/Yes 1 M*ES Testing &

Valve SV4-PV10-VBR-004 PCD001 Analysis Type IRWST Gutter Isolation SV4-PV10-VBR-003 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V130B Yes Yes/Yes 1 M*ES Testing &

Valve SV4-PV10-VBR-004 PCD001 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-011A Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-011B Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-011C Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-011D Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-012A Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 14 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-012B Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-012C Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-012D Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-013A Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-013B Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-013C Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT A Level Sensor PXS-013D Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-014A Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-014B Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 15 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-014C Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-CMT B Level Sensor PXS-014D Yes Yes/Yes 1 E*S Testing &

SV4-JE61-VBR-001 PCD004 Analysis Type IRWST Wide Range Level SV4-JE52-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-046 Yes Yes/Yes 1 E*S Testing &

Sensor SV4-JE52-VBR-001 PCD004 Analysis Type IRWST Wide Range Level SV4-JE52-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-047 Yes Yes/Yes 1 E*S Testing &

Sensor SV4-JE52-VBR-001 PCD004 Analysis Type IRWST Wide Range Level SV4-JE52-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-048 Yes Yes/Yes 1 E*S Testing &

Sensor SV4-JE52-VBR-001 PCD004 Analysis Type SV4-JE52-VBR-004 / 2.2.03.05a.i-U4-EQRR-PRHR HX Flow Sensor PXS-049A Yes Yes/Yes 1 E*S Testing &

SV4-JE52-VBR-003 PCD004 Analysis Type SV4-JE52-VBR-004 / 2.2.03.05a.i-U4-EQRR-PRHR HX Flow Sensor PXS-049B Yes Yes/Yes 1 E*S Testing &

SV4-JE52-VBR-003 PCD004 Analysis Type SV4-JE61-VBR-002 /

Containment Flood-up 2.2.03.05a.i-U4-EQRR-PXS-050 Yes Yes/Yes 1 E*S Testing & SV4-JE61-VBR-001 Level Sensor PCD004 Analysis Type SV4-JE61-VBR-002 /

Containment Flood-up 2.2.03.05a.i-U4-EQRR-PXS-051 Yes Yes/Yes 1 E*S Testing & SV4-JE61-VBR-001 Level Sensor PCD004 Analysis

U.S. Nuclear Regulatory Commission ND-23-0162 Enclosure Page 16 of 16 Attachment A System: Passive Core Cooling System Class 1E/

Seismic Envir. Envir Qual Type of Equipment Name + Tag No. + Qual. Harsh EQ Reports As-Built EQRR Cat. I + 3 Zone 1 Program 2 Qual.

Envir. + 3 Type Containment Flood-up SV4-JE61-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-052 Yes Yes/Yes 1 E*S Testing &

Level Sensor SV4-JE61-VBR-001 PCD004 Analysis Type IRWST Lower Narrow SV4-JE52-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-066 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV4-JE52-VBR-001 PCD004 Analysis Type IRWST Lower Narrow SV4-JE52-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-067 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV4-JE52-VBR-001 PCD004 Analysis Type IRWST Lower Narrow SV4-JE52-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-068 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV4-JE52-VBR-001 PCD004 Analysis Type IRWST Lower Narrow SV4-JE52-VBR-002 / 2.2.03.05a.i-U4-EQRR-PXS-069 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV4-JE52-VBR-001 PCD004 Analysis RNS Suction Leak Test SV4-PV17-VBR-004 / 2.2.03.05a.i-U4-EQRR-PXS-PL-V208A Yes -/- N/A N/A Analysis Valve SV4-PV17-VBR-003 PCD001 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