Text

ITAAC Closure Notification on Completion of ITAAC 2.2.01.05.i (Index Number 98)
	ML22168A168
Person / Time
Site:	Vogtle
Issue date:	06/17/2022
From:	Coleman J; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ITAAC 2.2.01.05.i, ND-21-1032
	Download: ML22168A168 (21)
	v • d • e

A Southern Nuclear Docket No.:

52-025 JUN 1'? 2022 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-21-1032 10 CFR 52.99(c)(1)

ITAAC Closure Notification on Completion of ITAAC 2.2.01.05.i (Index Number 98]

Ladies and Gentlemen:

In accordance with 1 O 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 2.2.01.05.i (Index Number 98].

This ITAAC confirms that the Containment System (CNS) equipment identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2.2.1 -1 are designed and constructed in accordance with applicable requirements. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "Industry Guideline for the ITAAC Closure Process Under 1 O CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new 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 1 O 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:

JMC/GCS/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.01.05.i (Index Number 98]

U.S. Nuclear Regulatory Commission ND-21-1032 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-21-1032 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-21-1032 Enclosure Page 1 of 18 Southern Nuclear Operating Company ND-21-1032 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.01.05.i [Index Number 98]

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 2 of 18 IT AAC Statement Design Commitment:

5. The seismic Category I equipment identified in Table 2.2.1-1 can withstand seismic design basis loads without loss of structural integrity and safety function.

6.a) The Class 1 E equipment identified in Table 2.2.1-1 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.

6.d) The non-Class 1 E electrical penetrations identified in Table 2.2.1-1 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 containment pressure boundary integrity.

Inspections, Tests, Analyses:

i) Inspection will be performed to verify that the seismic Category I equipment and valves identified in Table 2.2.1-1 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.

i) Type tests, analyses, or a combination of type tests and analyses will be performed on non-Class 1 E electrical penetrations located in a harsh environment.

ii) Inspection will be performed of the as-built non-Class 1 E electrical penetrations located in a harsh environment.

Acceptance Criteria:

i) The seismic Category I equipment identified in Table 2.2.1-1 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 structural integrity and safety function.

iii) The as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 3 of 18 i) A report exists and concludes that the Class 1 E equipment identified in Table 2.2.1-1 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 exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.2.1-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

i) A report exists and concludes that the non-Class 1 E electrical penetrations identified in Table 2.2.1-1 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 containment pressure boundary integrity.

ii) A report exists and concludes that the as-built non-Class 1 E electrical penetrations identified in Table 2.2.1-1 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 Containment System (CNS) equipment identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2.2.1-1 (the Table) are designed and constructed in accordance with applicable requirements.

i) The seismic Category I equipment identified in Table 2.2.1-1 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 are designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EQ) Walkdown ITAAC Guideline (Reference 1) and Equipment Qualification (EQ) Installation Documentation Guideline (Reference 13), an inspection was conducted of the CNS 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 2) 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 structural integrity and safety function.

Seismic Category I equipment in the Table require type tests and/or analyses to demonstrate structural integrity and operability. The structural integrity of the seismic Category I valves, as well as other passive seismic Category I mechanical equipment, was demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section Ill (Reference 3). The functionality of the subset of active safety-related valves under seismic loads was determined using the guidance of ASME OME-1-2007 (Reference 4).

Safety-related (Class 1 E) electrical equipment in the Table was seismically qualified by type testing combined with an analysis in accordance with Institute of Electrical and Electronics

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 4 of 18 Engineers (IEEE) Standard 344-1987 (Reference 5). 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 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 Analysis Report (UFSAR) Appendix 30 (Reference 6). The EQ Reports (Reference 7) 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 structural integrity and safety function.

iii) The as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

An inspection (References 1 and 13) 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 the 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 7) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification. Interface requirements are defined based on the test configuration and other design requirements.

Attachment A identifies the EQRR (Reference 2) completed to verify that the as-built seismic Category I equipment listed in the Table, including anchorage, is seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 5), and NRC Regulatory Guide (RG) 1.100 (Reference 8).

i) A report exists and concludes that the Class 1 E equipment identified in Table 2.2.1-1 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 1 E equipment in the Table are qualified by type testing and/or analyses. Class 1 E electrical equipment type testing was performed in accordance with IEEE Standard 323-197 4 (Reference 9) and RG 1.89 (Reference 10) to meet the requirements of 1 0 CFR 50.49. Type testing of safety-related equipment meets the requirements of 1 0 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 equipment located in a harsh environment. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the UFSAR Appendix 30 (Reference 6).

EQ Reports (Reference 7) identified in Attachment A contains applicable test reports and

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 5 of 18 associated documentation and conclude that the equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

ii) A report exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.2.1-1 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 13) was conducted of the CNS to confirm the satisfactory installation of the Class 1 E equipment in the Table. The inspection verified the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the equipment is mounted are bounded by the tested and/or analyzed conditions. It also documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 2) identified in Attachment A documents this inspection and concludes 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 9).

i) A report exists and concludes that the non-Class 1 E electrical penetrations identified in Table 2.2.1-1 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 containment pressure boundary integrity.

The harsh environment non-Class 1 E electrical penetrations in the Table are qualified by type testing and/or analyses. Non-Class 1 E electrical penetration type testing is performed in accordance with IEEE Standard 323-1974 (Reference 9), IEEE Standard 317-1983 (Reference 11 ), and RG 1.89 (Reference 10) to meet the requirements of 1 0 CFR 50.49. Attachment A identifies the EQ program and specific qualification method for each non-Class 1 E electrical penetration located in a harsh environment. Additional information about the methods used to qualify electrical penetrations supplied for the AP1000 is provided in the UFSAR Appendix 3D (Reference 6). EQ reports (Reference 7) identified in Attachment A contain applicable test reports and associated documentation and conclude that the electrical penetrations can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of containment pressure boundary integrity.

ii) A report exists and concludes that the as-built non-Class 1 E electrical penetrations identified in Table 2.2.1-1 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 13) was conducted of the CNS to confirm the satisfactory installation of the non-Class 1 E electrical penetrations in the Table. The inspection verified the penetration location, make/model/serial number, and as-designed penetration mounting, and confirms that the environmental conditions for the zone (Attachment A) in which the penetration is mounted are bounded by the tested and/or analyzed conditions. It also documented the installed configuration with photographs or sketches/drawings of penetration mounting. The EQRR (Reference 2) identified in Attachment A documented this inspection and concluded that the as-built harsh environment non-Class 1 E electrical penetrations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 9), and IEEE Standard 317-1983 (Reference 11 ).

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 6 of 18 Together, these reports (References 2 and 7) provided evidence that the ITAAC Acceptance Criteria requirements are met:

The seismic Category I equipment identified in Table 2.2.1-1 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 structural integrity and safety function; The as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions; A report exists and concludes that the Class 1 E equipment identified in Table 2.2.1-1 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; A report exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.2.1-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses; A report exists and concludes that the non-Class 1 E electrical penetrations identified in Table 2.2.1-1 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 containment pressure boundary integrity; and A report exists and concludes that the as-built non-Class 1 E electrical penetrations identified in Table 2.2.1-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

References 2 and 7 are available for NRC inspection as part of Unit 3 ITAAC 2.2.01.05.i Completion Package (Reference 12).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 99, 100, 101, 102, 105 and 106, found three closed Notices of Nonconformance (NON) and one closed violation associated with this ITAAC:

1) 99901412/2012-201-02 (closed) ML16357A725

2) 99901415/2012-201-01 (closed) ML15148A419

3) 99901415/2012-201-02 (closed) ML15148A419

4)05200025/2021005-05 (closed) ML22130A054

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 7 of 18 IT AAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.05.i was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

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 Walkdown ITAAC Guideline"

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

3. 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

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

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

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

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

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

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

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

11. IEEE Standard 317-1983, "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations"

12. 2.2.01.05.i-U3-CP-Rev 0, ITAAC Completion Package"

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

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 8 of 18 Equipment Name +

Tag No. +

Service Air Supply Outside CAS-PL-Containment Isolation Valve V204 Service Air Supply Inside CAS-PL-Containment Isolation Check V205 Valve Instrument Air Supply Outside Containment CAS-PL-Isolation Valve V014 Instrument Air Supply Inside CAS-PL-Containment Isolation Check V015 Valve Component Cooling Water System (CCS) Containment Isolation Motor-operated CCS-PL-Valve (MOV) - Inlet Line V200 Outside Reactor Containment (ORC)

CCS Containment Isolation Check Valve - Inlet Line CCS-PL-Inside Reactor Containment V201 (IRC)

Seismic Cat. I +

Yes Yes Yes Yes Yes Yes Attachment A System: Containment System Class Envir 1 E/Qual.

Envir.

Qual For Harsh Zone 1 Program 2 Envir. + 3

-/-

N/A N/A

-/-

N/A N/A Yes/No N/A N/A

-/-

N/A N/A Yes/No N/A N/A

-/-

N/A N/A Type of EQ Reports As-Built EQRR Qual.

(Reference 7)

(Reference 2)

Type Testing APP-PV1 0-VBR-008 /

2.2.01.05.i-U3-APP-PV1 0-VBR-007 EQRR-PCD001 Analysis APP-PV03-VBR-002 /

2.2.01.05.i-U3-Analysis APP-PV03-VBR-001 EQRR-PCD001 Type Testing APP-PV1 0-VBR-004 /

2.2.01.05.i-U3-APP-PV1 0-VBR-003 EQRR-PCD001 Analysis APP-PV02-VBR-016 /

2.2.01.05.i-U3-Analysis APP-PV02-VBR-015 EQRR-PCO001 Type Testing APP-PV11-VBR-006 /

2.2.01.05.i-U3-APP-PV11-VBR-005 EQRR-PCD001 Analysis Analysis APP-PV03-VBR-014 /

2.2.01.05.i-U3-APP-PV03-VBR-013 EQRR-PCO001

U.S. Nuclear Regulatory Commission N 0-21-1032 Enclosure Page 9 of 18 Equipment Name +

Tag No.+

CCS Containment Isolation CCS-PL-MOV - Outlet Line IRC V207 CCS Containment Isolation CCS-PL-MOV - Outlet Line ORC V208 CCS Containment Isolation CCS-PL-Relief Valve - Outlet Line V220 IRC Demineralized Water Supply DWS-PL-Containment Isolation Valve V244 ORC Demineralized Water Supply DWS-PL-Containment Isolation Check Valve IRC V245 FHS-FT-Fuel Transfer Tube 01 Fuel Transfer Tube Isolation FHS-PL-Valve V001 Fire Water Containment FPS-PL-Supply Isolation Valve -

voso Outside Class Seismic 1 E/Qual.

Cat. I +

For Harsh Envir. + 3 Yes Yes/Yes Yes Yes/No Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Envir Envir.

Qual Type of EQ Reports As-Built EQRR Zone 1 Program 2 Qual.

(Reference 7)

(Reference 2)

Type M

E Testing APP-PV11 -VBR-006 /

2.2.01.05.i-U3-1 APP-PV11-VBR-005 EQRR-PCO001 Analvsis Type N/A Testing APP-PV11-VBR-006 /

2.2.01.05.i-U3-N/A APP-PV11-VBR-005 EQRR-PCD001 Analvsis Type Testing APP-PV16-VBR-002 /

2.2.01.05.i-U3-N/A N/A APP-PV16-VBR-001 EQRR-PCO001 Analvsis Type Testing APP-PV11-VBR-002 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-001 EQRR-PCD001 Analvsis Analysis APP-PV02-VBR-016 /

2.2.01.05.i-U3-N/A N/A APP-PV02-VBR-015 EQRR-PCD001 N/A Analysis APP-FT01-S3R-001 2.2.01.05.i-U3-N/A EQRR-PCO002 Type N/A Testing APP-FH06-VBR-002 /

2.2.01.05.i-U3-N/A APP-FH06-VBR-001 EQRR-PCO001 Analysis Type Testing APP-PV11-VBR-002 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-001 EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 10 of 18 Equipment Name +

Tag No.+

Fire Water Containment FPS-PL-Isolation Supply Check Valve V052 Inside Spent Fuel Pool Cooling System (SFS) Discharge Line SFS-PL-Containment Isolation Check V037 Valve IRC SFS Discharge Line SFS-PL-Containment Isolation MOV -

V038 ORC SFS Suction Line SFS-PL-Containment Isolation MOV -

V034 IRC SFS Suction Line SFS-PL-Containment Isolation MOV -

V035 ORC SFS Suction Line SFS-PL-Containment Isolation Relief V067 Valve - IRC Containment Purge Inlet VFS-PL-Containment Isolation Valve V003

- ORC Containment Purge Inlet VFS-PL-Containment Isolation Valve V004

-IRC Class Seismic 1 E/Qual.

Cat. I +

For Harsh Envir. + 3 Yes

-/-

Yes

-/-

Yes Yes/No Yes Yes/Yes Yes Yes/No Yes

-/-

Yes Yes/No Yes Yes/Yes Envir Envir.

Type of EQ Reports As-Built EQRR Zone 1 Qual Qual.

(Reference 7)

(Reference 2)

Program 2 Analysis APP-PV03-VBR-014 /

2.2.01.05.i-U3-N/A N/A APP-PV03-VBR-013 EQRR-PCD001 APP-PV03-VBR-002 /

2.2.01.05.i-U3-Analysis N/A N/A APP-PV03-VBR-00 1 EQRR-PCD001 Type Testing APP-PV11-VBR-006 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-005 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-006 /

2.2.01.05.i-U3-1 M

E APP-PV11-VBR-005 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-006 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-005 EQRR-PCD001 Analysis Type Testing APP-PV16-VBR-002 /

2.2.01.05.i-U3-N/A N/A APP-PV16-VBR-001 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-004 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-003 EQRR-PCD001 Analysis Type Testing APP-PV11 -VBR-004 /

2.2.01.05.i-U3-1 M

E APP-PV11-VBR-003 EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 11 of 18 Equipment Name+

Tag No.+

Integrated Leak Rate Testing VFS-PL-Vent Discharge Containment V008 Isolation Valve - ORC Containment Purge VFS-PL-Discharge Containment V009 Isolation Valve - IRC Containment Purge VFS-PL-Discharge Containment V010 Isolation Valve - ORC Vacuum Relief Containment VFS-PL-Isolation A MOV-ORC VS00A Vacuum Relief Containment VFS-PL-Isolation B MOV-ORC V800B Vacuum Relief Containment VFS-PL-Isolation Check Valve A -

V803A IRC Vacuum Relief Containment VFS-PL-Isolation Check Valve B -

V803B IRC Class Seismic 1 E/Qual.

Cat. I+

For Harsh Envir. + 3 Yes

-/-

Yes Yes/Yes Yes Yes/No Yes Yes/No Yes Yes/No Yes

-/-

Yes

-/-

I Envir Envir.

Qual Type of EQ Reports As-Built EQRR Zone 1 Program 2 Qual.

(Reference 7)

(Reference 2)

Type Testing APP-PV02-VBR-010 /

2.2.01.05.i-U3-N/A N/A APP-PV02-VBR-009 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-004 /

2.2.01.05.i-U3-1 M

ES APP-PV11-VBR-003 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-004 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-003 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-006 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-005 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-006 /

2.2.01.05.i-U3-N/A N/A APP-PV11-VBR-005 EQRR-PCD001 Analysis Type Testing APP-PV18-VBR-002 /

2.2.01.05.i-U3-N/A N/A APP-PV18-VBR-001 EQRR-PCD001 Analysis Type Testing APP-PV18-VBR-002 /

2.2.01.05.i-U3-N/A N/A APP-PV18-VBR-001 EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission N D-21-1032 Enclosure Page 12 of 18 Equipment Name +

Tag No.+

Fan Coolers Return VWS-PL-Containment Isolation Valve V082

-IRC Fan Coolers Return VWS-PL-Containment Isolation Valve V086

-ORC Fan Coolers Return VWS-PL-Containment Isolation Relief V080 Valve - IRC Fan Coolers Supply VWS-PL-Containment Isolation Valve V0S8

-ORC Fan Coolers Supply VWS-PL-Containment Isolation Check V062 Valve IRC Reactor Coolant Drain Tank (RCDT) Gas Outlet WLS-PL-Containment Isolation Valve V067 IRC RCDT Gas Outlet WLS-PL-Containment Isolation Valve V068

-ORC Sump Discharge WLS-PL-Containment Isolation Valve VOSS

-IRC Class Seismic 1 E/Qual.

Cat. I+

For Harsh Envir. + 3 Yes Yes/Yes Yes Yes/No Yes

-/-

Yes Yes/No Yes

-/-

Yes Yes/Yes Yes Yes/No Yes Yes/Yes Envir Envir.

Type of EQ Reports As-Built EQRR Zone 1 Qual Qual.

(Reference 7)

(Reference 2)

Program 2 Type Testing APP-PV11-VBR-004 /

2.2.01.0S.i-U3-1 M

ES APP-PV11 -VBR-003 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-004 /

2.2.01.0S.i-U3-N/A N/A APP-PV11-VBR-003 EQRR-PCD001 Analysis Type Testing APP-PV16-VBR-002 /

2.2.01.0S.i-U3-N/A N/A APP-PV16-VBR-001 EQRR-PCD001 Analysis Type Testing APP-PV11-VBR-004 /

2.2.01.0S.i-U3-N/A N/A APP-PV11-VBR-003 EQRR-PCD001 Analysis Analysis APP-PV03-VBR-002 /

2.2.01.0S.i-U3-N/A N/A APP-PV03-VBR-001 EQRR-PCD001 Type Testing APP-PV14-VBR-002 /

2.2.01.0S.i-U3-1 M

ES APP-PV14-VBR-001 EQRR-PCD001 Analysis Type Testing APP-PV14-VBR-002 /

2.2.01.0S.i-U3-N/A N/A APP-PV14-VBR-001 EQRR-PCD001 Analysis Type Testing APP-PV1 0-VBR-006 /

2.2.01.0S.i-U3-1 M

ES APP-PV10-VBR-00S EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 13 of 18 Equipment Name +

Tag No. +

Sump Discharge WLS-PL-Containment Isolation Valve V057

-ORC Sump Discharge WLS-PL-Containment Isolation Relief V058 Valve - IRC CNS-PY-Spare Penetration C01 CNS-PY-Spare Penetration CO2 CNS-PY-Spare Penetration C03 CNS-MY-Main Equipment Hatch Y01 CNS-MY-Maintenance Hatch Y02 CNS-MY-Upper Personnel Hatch Y03 CNS-MY-Lower Personnel Hatch Y04 Class Seismic 1 E/Qual.

Cat. I +

For Harsh Envir. + 3 Yes Yes/No Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Yes

-/-

Envir Envir.

Qual Type of EQ Reports As-Built EQRR Zone 1 Program 2 Qual.

(Reference 7)

(Reference 2)

Type Testing APP-PV1 0-VBR-006 /

2.2.01.05.i-U3-NIA NIA APP-PV1 0-VBR-005 EORR-PCD001 Analysis Type Testing APP-PV16-VBR-002 /

2.2.01.05.i-U3-NIA NIA APP-PV16-VBR-001 EQRR-PCD001 Analysis NIA Analysis SV3-MV50-S3R-100 2.2.01.05.i-U3-NIA SV3-CNS-S3R-001 EQRR-PCD002 Analysis SV3-MV50-S3R-100 2.2.01.05.i-U3-NIA NIA SV3-CNS-S3R-001 EQRR-PCD002 Analysis SV3-MV50-S3R-100 2.2.01.05.i-U3-NIA NIA SV3-CNS-S3R-001 EQRR-PCD002 Type APP-MVS0-VBR-002 /

Testing APP-MV50-VBR-001 /

2.2.01.05.i-U3-NIA NIA EQRR-PCD002 Analvsis Type APP-MV50-VBR-002 /

Testing APP-MVS0-VBR-001 /

2.2.01.05.i-U3-NIA NIA EQRR-PCD002 Analysis Type APP-MVS0-VBR-002 /

Testing APP-MV50-VBR-001 /

2.2.01.05.i-U3-NIA NIA EQRR-PCD002 Analysis Type APP-MV50-VBR-002 /

Testing APP-MV50-VBR-001 /

2.2.01.05.i-U3-NIA NIA EQRR-PCD002 Analysis

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 14 of 18 Equipment Name +

Tag No.+

CNS-MV-Containment Vessel 01 DAS-EY-Electrical Penetration P03 P03Z ECS-EY-Electrical Penetration P01 P01X ECS-EY-Electrical Penetration P02 P02X ECS-EY-Electrical Penetration P06 P06Y ECS-PY-Electrical Penetration PO?

PO?X ECS-EY-Electrical Penetration P09 P09W ECS-EY-Electrical Penetration P 1 O P10W Class Seismic 1 E/Qual.

Envir.

Cat. I+

For Harsh Zone 1 Envir. + 3 Yes

-/-

N/A Yes No/Yes 7

Yes No/Yes 4

Envir Qual Type of EQ Reports As-Built EQRR Program 2 Qual.

(Reference 7)

(Reference 2)

N/A Analysis SV3-MV50-S3R-100 2.2.01.05.i-U3-EQRR-PCD002 Type E

S Testing APP-EY01 -VBR-004 /

2.2.01.05.i-U3-APP-EY01-VBR-003 EQRR-PCD003 Analysis Type E

S Testing APP-EY01 -VBR-004 /

2.2.01.05.i-U3-APP-EY01-VBR-003 EQRR-PCD003 Analysis Type E

S Testing APP-EY01 -VBR-004 /

2.2.01.05.i-U3-APP-EY01-VBR-003 EQRR-PCD003 Analysis Type E

S Testing APP-EYO 1-VBR-004 /

2.2.01.05.i-U3-APP-EY01 -VBR-003 EQRR-PCD003 Analysis Type E

S Testing APP-EY01 -VBR-004 /

2.2.01.05.i-U3-APP-EY01-VBR-003 EQRR-PCD003 Analvsis Type E

S Testing APP-EY01-VBR-002 /

2.2.01.05.i-U3-APP-EY01-VBR-001 EQRR-PCD003 Analvsis Type E

S Testing APP-EY01-VBR-002 /

2.2.01.05.i-U3-APP-EY01-VBR-001 EQRR-PCD003 Analysis

U.S. Nuclear Regulatory Commission ND-21-1032 Enclosure Page 15 of 18 Equipment Name+

Tag No. +

IDSA-EY-Electrical Penetration P11 P11Z IDSA-EY-Electrical Penetration P12 P12Y IDSA-EY-Electrical Penetration P 13 P13Y IDSD-EY-Electrical Penetration P 14 P14Z IDSD-EY-Electrical Penetration P15 P15Y IDSD-EY-Electrical Penetration P 16 P16Y ECS-EY-Electrical Penetration P 17 P17X Class Seismic 1 E/Qual.

Envir.

Cat. I+

For Harsh Zone 1 Envir. + 3 Yes Yes/Yes 2

Yes Yes/Yes 2

Yes No/Yes 4

Envir Qual Type of EQ Reports As-Built EQRR Program 2 Qual.

(Reference 7)

(Reference 2)

Type E

S Testing APP-EY01-VBR-004 /