ML22125A268

ITAAC Closure Notification on Completion of ITAAC 2.1.02.05a.i (Index Number 19)

ML22125A268
Person / Time
Site:	Vogtle
Issue date:	05/05/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21 -1029
Download: ML22125A268 (21)

Text

Jamie M Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830

.>-,. Southern Nuclear Vogtle 3 & 4 706-848-6926 tel

MAY O 5 2022

Docket Nos.: 52-025

ND-21 - 1029 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 2.1.02.05a.i (Index Number 191

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 (ITAAC) Item 2. 1.02.05a. i [Index Number 191 to demonstrate that the Reactor Coolant System (RCS) components identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2. 1.2-1 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 3 Completion of ITAAC 2.1.02.05a.i [Index Number 191

JMC/LBP/sfr U.S. Nuclear Regulatory Commission ND-21-1029 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. 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 Regulato ry 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-21-1029 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-21-1029 Enclosure Page 1 of 18

Southern Nuclear Operating Company ND-21-1029 Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.1.02.0Sa.i [Index Number 19]

U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 2 of 18

ITAAC Statement

Design Commitment

5.a) The seismic Category I equipment identified in Table 2.1.2-1 can withstand seismic design basis loads without loss of safety function.

7.a) The Class 1 E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time requ ired 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. 1.2-1 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 1 E equipment located in a harsh environment.

ii) Inspection will be performed of the as-built Class 1 E 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. 1.2-1 is located on the Nuclear Island.

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

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

i) A report exists and concludes that the Class 1 E equipment identified in Table 2. 1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

ii) A report ex ists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.1.2-1 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 - 1029 Enclosure Page 3 of 18

ITAAC Determination Basis

This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Reactor Coolant System (RCS) components identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2. 1.2-1 (the Table) are designed and constructed in accordance with applicable requirements.

i) The seismic Category I equipment identified in Table 2.1.2 - 1 is located on the Nuclear Island

To assure that seismic Category I components can withstand seismic design basis loads without loss of safety function, all the components in the Table are designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (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 RCS to confirm the satisfactory installation of the seismically qualified components. 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 components are located on the Nuclear Island.

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

Seismic Category I components in the Table require 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 is determined using the guidance of ASME QME-1-2007 (Reference 5).

Safety-related (Class 1 E) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 6). This equipment includes safety-related (Class 1 E) 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 component 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 Analysis Report (UFSAR) Appendix 3D (Reference 7). The EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and concluded that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

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

An inspection (References 1 and 2) was conducted to confirm the satisfactory installation of the seismically qualified components 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 U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 4 of 18

seismically qualified components includes photographs and/or sketches/drawings of equipment/mounting/interfaces._

As part of the seismic qualification program, consideration is given to the definition of the clearances needed around the equipment mounted in the plant to permit the equipment to move during a postulated seismic event without causing impact between adjacent pieces of safety related equipment. When required, seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports (Reference 8) 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 requ irements.

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 6) and NRC Regulatory Guide (RG) 1.100 (Reference 9).

i) A report exists and concludes that the Class 1 E equipment identified in Table 2. 1.2-1 as being qualified for a harsh environment can withstand the environmental condit ions 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 1 E components in the Table are qualified by type testing and/or analyses. Class 1 E electrical component type testing was performed in accordance with IEEE Standard 323-1974 (Reference 10) and RG 1.89 (Reference 11) 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 safety-related mechanical or Class 1 E electrical component 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 7).

EQ Reports (Reference 8) 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 1 E equipment and the associated wiring, cables, and terminations identified in Table 2. 1.2-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses

An inspection (References 1 and 2) was conducted of the RCS to confirm the satisfactory installation of the Class 1 E components 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 component 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 3) identified in Attachment A documented this inspection and concluded that the as-built harsh environment Class 1 E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-197 4 (Reference 10).

U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 5 of 18

Together, these reports (References 3 and 8) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 2. 1.2-1 is located on the Nuclear Island ;

• A report exists and concluded that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function ;

• A report exists and concluded that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions ;

• A report exists and concluded that the Class 1 E equipment identified in Table 2.1. 2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety func tion for the time required to perform the safety function ; and

• A report ex ists and concluded that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.1.2-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

References 3 and 8 are available for NRC inspection as part of the Unit 3 ITAAC 2. 1.02.05a.i Completion Package (Reference 12).

ITAAC Finding Review

In accordance with plant procedures for ITAAC completion, Southern Nuclear Ope rating Company (SNC) performed a review of all lTAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 20, 21, 24, and 25, found three closed notices of non-conformance (NON) and one closed non-cited violation (NCV) associated with this IT AAC :

1) NON 9990143 1/2013 - 201-01 - closed - ML14073A652

2) NON 99901441/2014-201-03 - closed - ML14307A578

3) NON 99900728/2017-201-01 - closed - ML20216A590

4) NCV 05200025/2021005-03 - closed - ML22045A005

ITAAC Completion Statement

Based on the above information, SNC hereby notifies the NRC that ITAAC 2. 1.02.05a.i was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 6 of 18

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with 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 Ill, " Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda

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

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

7. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 30, "Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment "

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

9. Regulatory Guide 1. 100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

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

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

12. 2.1.02.05a.i-U3-CP-Rev0, "Completion Package for Unit 3 ITAAC 2. 1.02.0Sa.i [Index Number 19]"

U.S. Nuclear Regulatory Commission N D 1029 Enclosure Page 7 of 18

Attachment A

System: Reactor Coolant Syst e m (RCS)

Seismic Class 1 E/ Qua I "Envir. Envir Qual T ype o f Equipmen t Name + T ag No.+ C a t. 1+ For Harsh E Q Reports As-Built EQR R erence 8) (Reference 3)

E nvir. + 3 Zone 1 P rogram 2 Qua l. (Re f

Steam Generato r 1 RCS-MB-01 Yes -/- N/ A N/A Analysis SV3-MB01-Z0R-101 2. 1.02.05a.i-U3-EQRR-PCD003 Ste am Generator 2 RCS-MB-02 Yes -/ - N/ A N/ A Analysis SV3-MB01-Z0R-101 2.1.02.05a.i - U3-EQRR-PCD003

RCP1A RCS - MP-01A Yes No/No N/ A N/ A Analysis SV3-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCD003

RCP1B RCS-MP-01 B Yes No / No N/ A N/ A Analysis SV3-MP0 1-S2R-011 2. 1.02.05a.i-U3-EQRR-PCD003

RCP2A RCS-MP-02A Yes No/No N/A N/ A Analysis SV3-MP01-S2R-011 2. 1.02.05a.i-U3-EQRR-PCD003

RCP 2B RCS-MP-02B Yes No / No N/ A N/ A Analysis SV3-MP01-S2R-011 2. 1.02.05a.i - U3-EQRR-PCD003

Pressurizer RCS - MV-02 Yes No / No (heaters) N/ A N/ A Analysis SV3-MV20 -Z0R-102 2. 1.02.05a.i-U3-EQRR-PCD003

Automatic Depressurization System PXS-MW-01A Yes -/ - N/ A N/ A Analysis SV3-MW01-S3R-001 2.1.02.05a.i-U3-EQRR-PCD003 (ADS) Sparger A ADS Sparger B PXS - MW-01 B Yes -/- N/ A N/ A Analysis SV3-MW01 - S3R-001 2.1.02.05a.i-U3-EQRR-PCD003

Pressurizer Safety Valve RCS-PL - V005A Yes -/- N/A N/ A Analysis SV3 - PV62-VBR-002 / 2.1.02.05a.i - U3-EQRR-SV3-PV62-VBR-001 PCD00 4

Pressurizer Safety Valve RCS-PL-V005B Yes -/ - N/A N/A Analysis SV3 - PV62-VBR-002 / 2. 1.02.05a.i - U3-EQRR-SV3-PV62-VBR-001 PCD004

First-stage ADS Motor-RCS - PL-V001 A Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-operated Valve (MOV) Yes Yes/Yes 1 ME

• S Testing &

Analvsis SV3-PV01-VBR-013 PCD004 U.S. Nuclear Regulatory Commission N D-21-1029 Enclosure Page 8 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Envir.+ 3 Type SV3-PV01-VBR-014 / 2. 1.02.05a.i-U3 - EQRR-First-stage ADS MOV RCS-PL-V001 B Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2. 1.02.05a.i-U3-EQRR-Second-stage ADS MOV RCS-PL-V002A Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR - 013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2. 1.02.05a.i-U3-EQRR-Second -stage ADS MOV RCS-PL-V002B Yes Yes/Yes 1 ME

• S Testing & SV3-PV01 -VBR-013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-Third-stage ADS MOV RCS-PL-V003A Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-Third-stage ADS MOV RCS-PL-V003B Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-013 PCD004 Analysis Fourth-stage ADS Squib RCS-PL-V004A Type SV3-PV70-VBR-005 / 2.1.02.05a.i-U3-EQRR-Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV70-VBR-004 PCD004 Analysis Fourth-stage ADS Squib RCS-PL-V004B Type SV3-PV70-VBR-005 / 2. 1.02.05a.i-U3-EORR-Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV70-VBR-004 PCD004 Analysis Fourth-stage ADS Squib RCS-PL-V004C Type SV3-PV70-VBR-005 / 2.1.02.05a.i - U3-EQRR-Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV70-VBR-004 PCD004 Analvsis Fourth-stage ADS Squib RCS-PL-V00 4 D Type SV3 - PV70-VBR-005 / 2.1.02.05a. i-U3-EQRR-Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV70 - VBR - 004 PCD004 Analvsis ADS Discharge Header A RCS-PL-V01 0A Type SV3-PV18-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Vacuum Relief Valve Yes Yes/Yes 1 M

• S Testing & SV3-PV18-VBR-001 PCD004 Analvsis U.S. Nuclear Regulatory Commission ND 1029 Enclosure Page 9 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Bui lt EQRR Equipment Name + T ag No. + Cat. 1+ For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Envir.+ 3 ADS Discharge Header B RCS-PL - V01 OB Type SV3-PV18 -VBR - 002 / 2.1.02.05a.i-U3-EQRR-Vacuum Relief Valve Yes Yes/Yes 1 M

• S Testing & SV3-PV18-VBR-001 PCD004 Analysis First-stage ADS Isolation RCS-PL - V011 A Type SV3-PV01-VBR-012 / 2. 1.02.05a.i-U3-EQRR-MOV Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-011 PCD004 Analysis First-stage ADS Isolation RCS-PL-V011 B Type SV3-PV01-VBR-012 / 2. 1.02.05a. i-U3-EQRR-MOV Y e s Yes/Y e s 1 ME

• S Testing & SV3 - PV01-VBR-011 PCD004 Analysis Second-stage ADS RCS-PL-V012A Type SV3-PV01-VBR -012 / 2. 1.02.05a.i-U3-EQRR-Isolation MOV Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-011 PCD004 Analysis Second-stage ADS RCS-PL-V012B Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-Isolation MOV Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-011 PCD004 Analysis Third-stage ADS Isolation RCS-PL-V013A Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-MOV Yes Yes/Yes 1 ME

• S Testing & SV3 - PV01-VBR-011 PCD004 Analysis Third-stage ADS Isolation RCS-PL-V013B Type SV3-PV01-VBR - 012 / 2. 1.02.05a.i-U3-EQRR-MOV Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-Fourth-stage ADS MOV RCS-PL-V01 4 A Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3 - EQRR -

Fourth-stage ADS MOV RCS-PL-V014B Yes Yes/Yes 1 ME

• S Testing & SV3 - PV01-VBR-011 PCD004 Analysis Type SV3 - PV01 -VBR - 012 / 2.1.02.05a.i-U3-EQRR-Fourth-stage ADS MOV RCS-PL - V014C Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR - 011 PCD004 Analysis U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 10 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Envir.+ 3 Type SV3 - PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-Fourth-stage ADS MOV RCS-PL-V01 4 D Yes Yes/Yes 1 ME

• S Testing & SV3-PV01-VBR-011 PCD004 Analysis Reactor Vessel Head RCS - PL-V150A Type SV3-PV13 - VBR-012 / 2.1.02.05a.i - U3-EQRR-Vent Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV13-VBR-011 PCD004 Analysis Reactor Vessel Head RCS-PL-V150B Type SV3-PV13-VBR-012 / 2. 1.02.05a.i-U3-EQRR-Vent Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV13-VBR-011 PCD004 Analysis Reactor Vessel Head RCS-PL-V150C Type SV3-PV13-VBR-012 / 2.1.02.05a.i-U3-EQRR-Vent Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV13-VBR-011 PCD004 Analysis Reactor Vessel Head RCS-PL-V150D Type SV3-PV13-VBR-012 / 2.1.02.05a.i-U3-EQRR-Vent Valve Yes Yes/Yes 1 ME

• S Testing & SV3-PV13-VBR-011 PCD004 Analysis RCS Hot Leg 1 Flow RCS-101A Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Hot Leg 1 Flow RCS-101B Type SV3-JE52-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52 -VBR-001 PCD006 Analysis RCS Hot Leg 1 Flow RCS - 101C Type SV3-JE52-VBR - 002 / 2. 1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Hot Leg 1 Flow RCS-101 D Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Hot Leg 2 Flow RCS-102A Type SV3-JE52-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52-VBR-001 PCD006 Analysis U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 11 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Envir.+ 3 RCS Hot Leg 2 Flow RCS-102B Type SV3-JE52-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Hot Leg 2 Flow RCS-102C Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Hot Leg 2 Flow RCS-102D Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Cold Leg 1 A Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-121A Yes Yes/Yes 1 E

• S Testing & SV3-J E53-VBR-00 1 PCD005 Sensor Analysis RCS Cold Leg 1 B Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-121B Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Cold Leg 1 B Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-121C Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Cold Leg 1 A Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-121 D Yes Yes/Yes 1 E*S Testing & APP-JE53-VBR-001 PCD005 Sensor Analysis RCS Cold Leg 2B Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-122A Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Cold Leg 2A Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-122B Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Cold Leg 2A Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS - 122C Yes Yes/Yes 1 E*S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 12 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Envir.+ 3 RCS Cold Leg 2B Narrow Type SV3 -JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-122D Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD00S Sensor Ana!_ysis RCS Cold Leg 1 A Dual Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-125A Yes Yes/Yes 1 E

• S Testing & SV3-J E53 - VBR-00 1 PCD00S Sensor Ana!Y_sis RCS Cold Leg 2A Dual Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-125B Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD00S Sensor Analysis RCS Cold Leg 1 B Dual Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-125C Yes Yes/Yes 1 E

• S Testing & SV3-JE53 - VBR-001 PCD00S Sensor Analysis RCS Cold Leg 2B Dual Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-125D Yes Yes/Yes 1 E

• S Testing & APP-JE53-VBR-001 PCD00S Sensor Ana!_ysis RCS Hot Leg 1 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-131A Yes Yes/Yes 1 E

• S Testing & SV3-J E53-VBR-00 1 PCD00S Sensor Ana!Y_sis RCS Hot Leg 2 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS - 131 B Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD00S Sensor Ana!_ysis RCS Hot Leg 1 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-131 C Yes Yes/Yes 1 E

• S Testing & SV3 -JE53-VBR-001 PCD00S Sensor Ana!Y_sis RCS Hot Leg 2 Narrow Type SV3-JE53-VBR - 002 / 2. 1.02.05a.i-U3-EQRR-Range Temperature RCS-131 D Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD00S Sensor Ana!_ysis RCS Hot Leg 1 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-132A Yes Yes/Yes 1 E

• S Testing & SV3-J E53-VBR-00 1 PCD00S Sensor Ana!Y_sis U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 13 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Envir.+ 3 RCS Hot Leg 2 Narrow Type SV3-JE53-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Range Temperature RCS-132B Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Hot Leg 1 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-132C Yes Yes/Yes 1 E*S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Hot Leg 2 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-132O Yes Yes/Yes 1 E*S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Hot Leg 1 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-133A Yes Yes/Yes 1 E*S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Hot Leg 2 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-133B Yes Yes/Yes 1 E*S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Hot Leg 1 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-133C Yes Yes/Yes 1 E*S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Hot Leg 2 Narrow Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-133O Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Hot Leg 1 Wide Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-135A Yes Yes/Yes 1 E*S Testing & SV3-J E53-VB R-001 PCD005 Sensor Analysis RCS Hot Leg 2 Wide Type SV3-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Range Temperature RCS-135B Yes Yes/Yes 1 E

• S Testing & SV3-JE53-VBR-001 PCD005 Sensor Analysis RCS Wide Range RCS-140A Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Pressure Sensor Yes Yes/Yes 1 E*S Testing & SV3-JE52-VBR-001 PCD006 Analysis U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 14 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Envir.+ 3 RCS Wide Range RCS-140B Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Pressure Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Wide Range RCS-140C Type SV3 -JE52 - VBR-004 / 2.1.02.05a.i-U3-EQRR-Pressure Sensor Yes Yes/Yes 1 E

• S Testing & SV3-J E52-VBR-003 PCD006 Analysis RCS Wide Range RCS-140O Type SV3-JE52-VBR-004 / 2.1.02.05a.i-U3 - EQRR-Pressure Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-003 PCD006 Analy_sis RCS Hot Leg 1 Level RCS-160A Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-001 PCD006 Analysis RCS Hot Leg 2 Level RCS-160B Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-001 PCD006 Analysis Passive Residual Heat Type APP-JE53-VBR - 002 2.1.02.05a.i-U3-EQRR-Removal (PRHR) Return RCS-161 Yes Yes/Yes 1 E

• S Testing & APP-J E53-VBR-00 1 PCD005-Rev 0 Line Temperature Sensor Analysis Pressurizer Pressure RCS-191A Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-001 PCD006 Analysis Pressurizer Pressure RCS-191B Type SV3 -JE52-VBR - 002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-001 PCD006 Analysis Pressurizer Pressure RCS-191C Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-001 PCD006 Analysis Pressurizer Pressure RCS-191O Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• S Testing & SV3-JE52-VBR-001 PCD006 Analysis U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 15 of 18

Seismic Class 1 E/ Qual "Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ Envir.+ 3 For Harsh Zone 1 Program 2 Qual. (Reference 8) (Reference 3)

Pressurizer Level Type Reference Leg RCS-193A Yes Yes/Yes 1 E

• S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EORR-Temperature Sensor Analysis APP-JE53-VBR-001 PCD005-Rev 0 Pressurizer Level Type Reference Leg RCS-193B Yes Yes/Yes 1 E

• S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor Analysis APP-JE53-VBR-001 PCD005-Rev 0 Pressurizer Level Type Reference Leg RCS-193C Yes Yes/Yes 1 E

• S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor Analvsis APP-JE53-VBR-001 PCD005-Rev O Pressurizer Level Type Reference Leg RCS-193D Yes Yes/Yes 1 E

• S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor Analvsis APP-JE53-VBR-001 PCD005-Rev O Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EORR-Pressurizer Level Sensor RCS-195A Yes Yes/Yes 1 E

• S Testing &

Analysis SV3-JE52-VBR-001 PCD006 Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Pressurizer Level Sensor RCS-195B Yes Yes/Yes 1 E

• S Testing &

Analvsis SV3-JE52-VBR-001 PCD006 Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EQRR-Pressurizer Level Sensor RCS-195C Yes Yes/Yes 1 E

• S Testing &

Analvsis SV3-JE52-VBR-001 PCD006 Type SV3-JE52-VBR-002 / 2.1.02.05a.i-U3-EORR-Pressurizer Level Sensor RCS-195D Yes Yes/Yes 1 E

• S Testing &

Analvsis SV3-JE52-VBR-001 PCD006 RCP 1 A Bearing Water RCS-211A Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-MP01-VBR-001 PCD005 RCP 1 A Bearing Water RCS-211 B Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-MP01-VBR-001 PCD005 U.S. Nuclear Regulatory Commission N D-21-1029 Enclosure Page 16 of 18

Seismic Class 1 E/ Qua l. Envir. Envir Qual Type of E Q Reports As-Built EQRR Equipment Name+ T ag No.+ Cat. 1+ For Harsh Qual. (Reference 8) (Re fe rence 3)

Envir. + 3 Zone 1 Program 2 RCP 1 A Bearing Water Type SV3-MP01-VBR - 002 / 2. 1.02.05a.i-U3-EQRR -

Temperature Sensor RCS -211 C Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 1 A Bearing Water Type SV3-MP01-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Temperature Sensor RCS -211 D Yes Yes/Yes 1 E

• Testing & SV3 - MP01-VBR-001 PCD005 Analysis RCP 1 B Bearing Water Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor RCS-212A Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 1 B Bearing Water Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor RCS-212B Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 1 B Bearing Water Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EORR-Temperature Sensor RCS-212C Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 1 B Bearing Water Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor RCS-212D Yes Yes/Yes 1 E

• Testing & SV3-MP01 -VBR-001 PCD005 Analysis RCP 2A Bearing Water Type SV3-MP01-VBR-002 / 2.1.02.05a. i-U3-EQRR-Temperatur e Senso r RCS -213A Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 2A Bearing Water Type SV3-MP01-VBR-002 / 2. 1.02.05a.i-U3-EQRR -

Temperature Sensor RCS-213B Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 2A Bearing Wate r Type SV3-MP01-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Temperature Sensor RCS-213C Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 2A Bearing Water Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor RCS-213D Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 17 of 18

Seismic Class 1 E/ Qual. Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name+ Tag No.+ Cat. 1+ Envir.+ 3 Zone 1 Program 2 For Harsh Qual. (Reference 8) (Reference 3)

RCP 2B Bearing Water Type SV3-MP01 - VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor RCS-214A Yes Yes/Yes 1 E

• Testing & SV3-MP01-VBR-001 PCD005 Analysis RCP 2B Bearing Water RCS-214B Type SV3-MP01-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Temperature Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-MP01 - VBR-001 PCD005 RCP 2B Bearing Water RCS-214C Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-MP01-VBR-001 PCD005 RCP 2B Bearing Water RCS-214D Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Temperature Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-MP01-VBR-001 PCD005 RCP 1 A Pump Speed RCS-281 Type SV3-JE62-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-JE62-VBR-001 PCD006 RCP 1 B Pump Speed RCS-282 Type SV3-JE62-VBR-002 / 2. 1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-JE62-VBR-001 PCD006 RCP 2A Pump Speed Type SV3-JE62-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor RCS-283 Yes Yes/Yes 1 E

• Testing & SV3-JE62-VBR-001 PCD006 Analysis RCP 2B Pump Speed RCS-284 Type SV3-JE62-VBR-002 / 2.1.02.05a.i-U3-EQRR-Sensor Yes Yes/Yes 1 E

• Testing &

Analysis SV3-JE62-VBR-001 PCD006 U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 18 of 18

Notes :

+ Excerpt from COL Appendix C Table 2. 1.2 -1

1. See Table 30.5-1 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