ND-21-1034, 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)

ML22151A332
Person / Time
Site:	Vogtle
Issue date:	05/31/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-1034
Download: ML22151A332 (19)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director

.,, Southern Nuclear Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6926 tel MAY 3 1 2022 Docket No.: 52-025 ND-21-1034 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 3 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 3 Inspections, Tests, Analyses, and Acceptance Criteria (IT AAC) 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,

~em~~

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.05a.i [Index Number 165)

JMC/LBP/sfr

U.S. Nuclear Regulatory Commission ND-21-1034 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. D. Pitts Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01 .02.06 Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-21-1034 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S.L. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph .D. , GOS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton , Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 1 of 16 Southern Nuclear Operating Company ND-21-1034 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.0Sa.i [Index Number 165]

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 2 of 16 IT AAC 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-21-1034 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 EO 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 EO As-Built Reconciliation Reports (EORR) (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 Ill (Reference 4). Functionality of the subset of active safety-related valves under seismic loads was determined using the guidance of ASME OME-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 N D-21-1034 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 se ismic 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 323-197 4 (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-21-1034 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-21-1034 Enclosure Page 6 of 16 References 3 and 10 are available for NRC inspection as part of the Unit 3 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.

IT AAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.05a.i was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part of this ITAAC are being maintained in thei r 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-Bu ilt Reconciliation Reports (EQRR) as identified in Attachment A

4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

Code , Section Ill , "Rules for Construction of Nuclear Power Plant Components ," 1998 Edition with 2000 Addenda

U.S. Nuclear Regulatory Comm ission ND-21-1034 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 Powe r Generating Stations"

9. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 30, "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 Powe r Plants"

12. IEEE Standard 323-197 4, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations"

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

14. 2.2.03.05a.i-U3-CP-Rev0 , "Completion Package for Unit 3 ITAAC 2.2.03.05a.i [Index Number 165]"

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 8 of 16 Attachment A System: Passive Core Cooling System Class 1 E/

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

Envir. +3 Passive Residual Heat Removal Heat Exchanger PXS-ME-01 Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis SV3-ME02-Z0R-001 PRHR HX) PCD003 Accumulator Tank A PXS-MT-01A Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis SV3-MT02-Z0R-102 PCO003

~ccumulator Tank B PXS-MT-01 B Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis SV3-MT02-Z0R-102 PCD003 Core Makeup Tank (CMT) 2.2.03.05a.i-U3-EQRR-PXS-MT-02A Yes -I - N/A N/A Analysis SV3-MT01-Z0R-101 A PCD003 CMTB PXS-MT-02B Yes -I - N/A N/A 2.2.03.05a.i-U3-EORR-Analysis SV3-MT01-Z0R-101 PCD003 IRWST PXS-MT-03 Yes -I - N/A N/A 2.2.03.05a.i-U3-EORR-Analysis SV3-11 00-GCR-001 PCD003 IRWST Screen A PXS-MY-Y01A Yes -I - N/A N/A Analysis 2.2.03.05a.i-U3-EQRR-SV3-MY03-VDR-00 1 PCD002 IRWST Screen B PXS-MY-Y01 B Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis SV3-MY03-VDR-001 PCD002 IRWST Screen C PXS-MY-Y0 1C Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis SV3-MY03-VDR-001 PCD002 Containment Recirculation 2.2.03.05a.i-U3-EQRR-PXS-MY-Y02A Yes -I - N/A N/A Analysis SV3-MY03-VDR-00 1 Screen A PCD002 Containment Recirculation 2.2.03.05a.i-U3-EQRR-PXS-MY-Y02B Yes -I - N/A N/A Analysis SV3-MY03-VDR-001 Screen B PCD002 pH Adjustment Basket 3A PXS-MY-Y03A Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis APP-MY0?-Z0C-002 PCD002 pH Adjustment Basket 3B PXS-MY-Y03B Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis APP-MY0?-Z0C-002 PCD002 pH Adjustment Basket 4A PXS-MY-Y04A Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis APP-MY0?-Z0C-002 PCD002

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 9 of 16 Attachment A System: Passive Core Cooling System Class 1E/

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

Envir. + 3 pH Adjustment Basket 4B PXS-MY-Y04B Yes -I - 2.2.03.05a.i-U3-EQRR-N/A N/A Analysis APP-MY0?-Z0C-002 PCD002 Downspout Screen 1A PXS-MY-Y81 Yes -I - N/A 2.2.03.05a.i-U3-EQRR-N/A Analysis APP-MY02-Z0C-001 PCD002 Downspout Screen 1B PXS-MY-Y82 Yes -I - 2.2.03.05a.i-U3-EQRR-N/A N/A Analysis APP-MY02-Z0C-001 PCD002 Downspout Screen 1C PXS-MY-Y83 Yes -I - 2.2.03.05a.i-U3-EQRR-N/A N/A Analysis APP-MY02-Z0C-001 PCD002 Downspout Screen 1D PXS-MY-Y84 Yes -I - N/A N/A 2.2.03.05a.i-U3-EQRR-Analysis APP-MY02-Z0C-001 PCD002 Downspout Screen 2A PXS-MY-Y85 Yes -I - 2.2.03.05a.i-U3-EQRR-N/A N/A Analysis APP-MY02-Z0C-001 PCD002 Downspout Screen 2B PXS-MY-Y86 Yes -I - 2.2.03.05a.i-U3-EQRR-N/A N/A Analysis APP-MY02-Z0C-001 PCD002 Downspout Screen 2C PXS-MY-Y87 Yes -I - 2.2.03.05a.i-U3-EQRR-N/A N/A Analysis APP-MY02-Z0C-001 PCD002 Downspout Screen 2D PXS-MY-Y88 Yes -I - 2.2.03.05a.i-U3-EQRR-N/A N/A Analysis APP-MY02-Z0C-001 PCD002 CMT A Inlet Isolation Type SV3-PV01-VBR-012 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V002A Yes Yes/Yes 1 M

• ES Testing &

Motor-operated Valve SV3-PV01-VBR-011 PCD001 Analysis CMT B Inlet Isolation Type PXS-PL-V002B SV3-PV01-VBR-012 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Motor-operated Valve SV3-PV01-VBR-011 PCD001 Analysis CMT A Discharge Type PXS-PL-V014A SV3-PV14-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Isolation Valve SV3-PV14-VBR-001 PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 10 of 16 Attachment A System: Passive Core Cooling System Class 1E/

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

Envir. +3 CMT B Discharge Type PXS-PL-V014B SV3-PV14-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Isolation Valve SV3-PV14-VBR-001 PCD001 Analysis CMT A Discharge Type PXS-PL-V015A SV3-PV14-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Isolation Valve SV3-PV14-VBR-001 PCD001 Analysis CMT B Discharge Type PXS-PL-V015B SV3-PV14-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Isolation Valve SV3-PV14-VBR-001 PCD001 Analysis CMT A Discharge Check SV3-PV03-VBR-004 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V016A Yes -I - N/A N/A Analysis Valve SV3-PV03-VBR-003 PCD001 CMT B Discharge Check SV3-PV03-VBR-004 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V016B Yes -I - N/A N/A Analysis Valve SV3-PV03-VBR-003 PCD001 CMT A Discharge Check SV3-PV03-VBR-004 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V017A Yes -I - N/A N/A Analysis Valve SV3-PV03-VBR-003 PCD001 CMT B Discharge Check SV3-PV03-VBR-004 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V017B Yes -I - N/A N/A Analysis Valve SV3-PV03-VBR-003 PCD001 Accumulator A Pressure Type SV3-PV16-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V022A Yes -I - N/A N/A Testing &

Relief Valve SV3-PV16-VBR-001 PCD001 Analysis

!Accumulator B Pressure Type SV3-PV16-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V022B Yes -I - N/A N/A Testing &

Relief Valve SV3-PV16-VBR-001 PCD001 Analysis Accumulator A Discharge Type SV3-PV01-VBR-012 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V027A Yes -I - N/A N/A Testing &

Isolation Valve SV3-PV01-VBR-011 PCD001 Analysis

!Accumulator B Discharge Type SV3-PV01-VBR-012 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V027B Yes -I - N/A N/A Testing &

Isolation Valve SV3-PV01-VBR-011 PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 11 of 16 Attachment A System: Passive Core Cooling System Class 1 E/

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

Envir. +3 lAccumulator A Discharge SV3-PV03-VBR-014 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V028A Yes -I - N/A N/A Analysis Check Valve SV3-PV03-VBR-013 PCD001 lAccumulator B Discharge SV3-PV03-VBR-014 / 2.2.03.05a .i-U3-EQRR-PXS-PL-V028B Yes -I - N/A N/A Analysis Check Valve SV3-PV03-VBR-013 PCD001 Accumul ator A Discharge SV3-PV03-VBR-014 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V029A Yes -I - N/A N/A Analysis Check Valve SV3-PV03-VBR-013 PCD001 Accumulator B Discharge SV3-PV03-VBR-014 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V029B Yes -I - N/A N/A Analysis Check Valve SV3-PV03-VBR-013 PCD001 Nitrogen Supply Type SV3-PV14-VBR-002 / 2.2.03.05a.i-U3-EQRR-Containment Isolation PXS-PL-V042 Yes Yes/No N/A N/A Testing &

SV3-PV14-VBR-001 PCD001 Valve Analysis Nitrogen Supply SV3-PV02-VBR-016 / 2.2.03.05a.i-U3-EQRR-Containment Isolation PXS-PL-V043 Yes -I - N/A N/A Analysis SV3-PV02-VBR-015 PCD001 Check Valve Type PRHR HX Inlet Isolation SV3-PV01-VBR-012 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V101 Yes Yes/Yes 1 M

• ES Testing &

Motor-operated Valve SV3-PV01-VBR-011 PCD001 Analysis Type SV3-PV20-VBR-002 / 2.2.03.05a.i-U3-EQRR-PRHR HX Control Valve PXS-PL-V1 OBA Yes Yes/Yes 1 M

• ES Testing &

SV3-PV20-VBR-001 PCD001 Analysis Type SV3-PV20-VBR-002 / 2.2.03.05a.i-U3-EQRR-PRHR HX Control Valve PXS-PL-V1088 Yes Yes/Yes 1 M

• ES Testing &

SV3-PV20-VBR-00 1 PCD001 Analysis Containment Recirculation Type SV3-PV01-VBR-012 / 2.2.03.05a.i-U3-EQRR-A Isolation Motor-operated PXS-PL-V117A Yes Yes/Yes 1 M

• ES Testing &

SV3-PV01-VBR-011 PCD001 Valve Analysis Containm ent Recirculation Type SV3-PV01-VBR-012 / 2.2.03.05a.i-U3-EQRR-B Isolation Motor-operated PXS-PL-V117B Yes Yes/Yes 1 M

• ES Testing &

SV3-PV01-VBR-011 PCD001 Valve Analysis

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 12 of 16 Attachment A System: Passive Core Cooling System Class 1 E/

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

Envir. + 3 Containment Recircul ation Type SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V118A Yes Yes/Yes 1 M

• ES Testing &

A Squib Valve SV3-PV70-VBR-002 PCD001 Analysis Containment Recirculation Type PXS-PL-V118B Yes SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-Yes/Yes 1 M

• ES Testing &

B Squib Valve SV3-PV70-VBR-002 PCD001 Analysis Containment Recirculation SV3-PV03-VBR-014 / 2.2.03.05a.i-U3-EQRR-A Check Valve PXS-PL-V119A Yes -I - N/A N/A Analysis SV3-PV03-VBR-013 PCD001 Containment Recirculation SV3-PV03-VBR-01 4 / 2.2.03.05a.i-U3-EQRR-B Check Valve PXS-PL-V119B Yes -I - N/A N/A Analysis SV3-PV03-VBR-013 PCD001 Containment Recirculation Type SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V120A Yes Yes/Yes 1 M

• ES Testing &

IA Squib Valve SV3-PV70-VBR-002 PCD001 Analysis Containment Recirculation Type PXS-PL-V120B SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

B Squib Valve SV3-PV70-VBR-002 PCD001 Analysis IRWST Injection A Check SV3-PV03-VBR-01 4 / 2.2.03.05a.i-U3-EQRR-Valve PXS-PL-V122A Yes -I - N/A N/A Analysis SV3-PV03-VBR-013 PCD001 IRWST Injection B Ch eck SV3-PV03-VBR-014 / 2.2.03.05a .i-U3-EQRR-Valve PXS-PL-V122B Yes -I - N/A N/A Analysis SV3-PV03-VBR-013 PCD001 Type IRWST Injection A Squib SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V123A Yes Yes/Yes 1 M

• ES Testing &

Valve SV3-PV70-VBR-002 PCD001 Analysis Type IRWST Injection B Squib SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V123B Yes Yes/Yes 1 M

• ES Testing &

Valve SV3-PV70-VBR-002 PCD001 Analysis IRWST Injection A Check SV3-PV03-VBR-014 / 2.2.03.05a.i-U3-EQRR-Valve PXS-PL-V124A Yes -I - N/A N/A Analysis SV3-PV03-VBR-013 PCD001

U.S. Nuclear Regulatory Commission N 0-21-1 034 Enclosure Page 13 of 16 Attachment A System: Passive Core Cooling System Class 1 E/

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

Envir. +3 IRWST Injection B Check SV3-PV03-VBR-014 / 2.2.03.05a.i-U3-EORR-PXS-PL-V124B Yes -I - N/A N/A Analysis Valve SV3-PV03-VBR-013 PCD001 IRWST Injection A Squib Type PXS-PL-V125A SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Valve SV3-PV70-VBR-002 PCD001 Analysis IRWST Injection B Squib Type PXS-PL-V125B SV3-PV70-VBR-003 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Valve SV3-PV70-VBR-002 PCD001 Analysis IRWST Gutter Isolation Type PXS-PL-V130A SV3-PV1 0-VBR-003 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Valve SV3-PV1 0-VBR-004 PCD001 Analysis IRWST Gutter Isolation Type PXS-PL-V130B SV3-PV1 0-VBR-003 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 M

• ES Testing &

Valve SV3-PV1 0-VBR-004 PCD001 Analysis Type CMT A Level Sensor PXS-011A SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type CMT A Level Sensor PXS-011 B SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EORR-Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type CMT A Level Sensor PXS-011 C SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type CMT A Level Sensor PXS-011 D SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type CMT B Level Sensor SV3-JE61-VBR-002 / 2.2 .03.05a.i-U3-EORR-PXS-012A Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 14 of 16 Attachment A System: Passive Core Cooling System Class 1 E/

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 SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT B Level Sensor PXS-012B Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCO004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT B Level Sensor PXS-012C Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT B Level Sensor PXS-012O Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT A Level Sensor PXS-013A Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCO004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT A Level Sensor PXS-013B Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT A Level Sensor PXS-013C Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EORR-GMT A Level Sensor PXS-013O Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT B Level Sensor PXS-014A Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-GMT B Level Sensor PXS-014B Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 15 of 16 Attachment A System: Passive Core Cooling System Class 1 E/

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

Envir. + 3 Type CMT B Level Sensor PXS-014C SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis Type CMT B Level Sensor PXS-014D SV3-JE61-VBR-002 / 2.2 .03.05a.i-U3-EQRR-Yes Yes/Yes 1 E*S Testing &

SV3-JE61-VBR-001 PCD004 Analysis IRWST Wide Range Level Type SV3-JE52-VBR-002 / 2.2.03.05a.i -U3-EQRR-PXS-046 Yes Yes/Yes 1 E*S Testing &

Sensor SV3-JE52-VBR-001 PCD004 Analysis IRWST Wide Range Level Type SV3-JE52-VBR-002 / 2 .2.03.05a.i-U3-EQRR-PXS-047 Yes Yes/Yes 1 E*S Testing &

Sensor SV3-JE52-VBR-001 PCD004 Analysis IRWST Wide Range Level Type PXS-048 SV3-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-Yes Yes/Yes 1 E*S Testing &

Sensor SV3-JE52-VBR-001 PCD004 Analysis Type SV3-JE52-VBR-004 / 2.2.03.05a.i-U3-EQRR-PRHR HX Flow Sensor PXS-049A Yes Yes/Yes 1 E*S Testing &

SV3-J E52-VBR-003 PCD004 Analysis Type PRHR HX Flow Sensor SV3-JE52-VBR-004 / 2.2.03.05a.i-U3-EQRR-PXS-049B Yes Yes/Yes 1 E*S Testing &

SV3-J E52-VB R-003 PCD004 Analysis Containment Flood-up Type SV3-JE61-VBR-002 /

PXS-050 Yes E*S 2.2.03.05a.i-U3-EQRR-Yes/Yes 1 Testing & SV3-JE61-VBR-001 Level Sensor PCD004 Analysis Containment Flood-up Type SV3-JE61-VBR-002 /

PXS-051 Yes E*S 2.2.03.05a.i-U3-EQRR-Yes/Yes 1 Testing & SV3-JE61-VBR-001 Level Sensor PCD004 Analysis

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 16 of 16 Attachment A System : Passive Core Coolin g System Class 1E/

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

Envir. + 3 Type Containment Flood-up SV3-JE61-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-052 Yes Yes/Yes 1 E*S Testing &

Level Sensor SV3-JE61-VBR-001 PCD004 Analysis Type I RWST Lower Narrow SV3-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-066 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV3-JE52-VBR-001 PCD004 Analysis Type IRWST Lower Narrow SV3-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-067 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV3-JE52-VBR-001 PCD004 Analysis Type IRWST Lower Narrow SV3-JE52-VBR-002 / 2 .2.03.05a.i-U3-EQRR-PXS-068 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV3-JE52-VBR-001 PCD004 Analysis Type I RWST Lower Narrow SV3-JE52-VBR-002 / 2.2.03.05a.i-U3-EQRR-PXS-069 Yes Yes/Yes 1 E*S Testing &

Range Level Sensor SV3-JE52-VBR-001 PCD004 Analysis RNS Suction Leak Test SV3-PV17-VBR-004 / 2.2.03.05a.i-U3-EQRR-PXS-PL-V208A Yes -I - N/A N/A Analysis Valve SV3-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 th e 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