ND-18-0175, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.02.05a.i (Index Number 126)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.02.05a.i (Index Number 126)

ML18054A655
Person / Time
Site:	Vogtle
Issue date:	02/22/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.02.05a.i, ND-18-0175
Download: ML18054A655 (14)

Text

Michael J. Vox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830

^ Southern Nuclear Vogtie 3 & 4 708-848-6459 tei 410-474-8587 ceii FEB 2 2 2018 myox@souttiernco.com Docket Nos.: 52-025 52-026 ND-18-0175 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.02.05a.i findex Number 1261 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 15, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.02.05a.i

[Index Number 126] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.

All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtie 3 & 4

U.S. Nuclear Regulatory Commission ND-18-0175 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.02.05a.i [Index Number 126]

MJY/PGLVamw

U.S. Nuclear Regulatory Commission ND-18-0175 Page 3 of 4 To:

Southern Nuclear Operating Company / Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0175 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. CorlettI Ms. L. G. Iller Mr. D. Hawkins Ms. J. 8. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-18-0175 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.02.05a.l [Index Number 126]

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 2 of 10 ITAAC Statement Design Commitment:

5.a) The seismic Category I components identified in Table 2.2.2-1 can withstand seismic design basis loads without loss of safety function.

6.a) The Class 1E components identified in Table 2.2.2-1 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.

Inspections. Tests. Analvses:

i) Inspection will be performed to verify that the seismic Category I components and valves identified in Table 2.2.2-1 are located on the Nuclear Island.

ii) Type tests, analyses, or a combination of type tests and analyses of seismic Category I components will be performed.

ill) Inspection will be performed for the existence of a report verifying that the as-built components including anchorage are seismically bounded by the tested or analyzed conditions.

i) Type tests or a combination of type tests and analyses will be performed on Class 1E components located in a harsh environment.

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

Acceptance Criteria:

i) The seismic Category I components identified in Table 2.2.2-1 are located on the Nuclear Island.

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

iii) The report exists and concludes that the as-built components including anchorage are seismically bounded by the tested or analyzed conditions.

i) A report exists and concludes that the Class 1E components identified in Table 2.2.2-1 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 exists and concludes that the as-built Class 1E components and the associated wiring, cables, and terminations identified inTable 2.2.2-1 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-18-0175 Enclosure Page 3 of 10 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Passive Containment Cooling System (PCS) components identified as seismic Category Ior Class 1E in the Combined License (COL) Appendix C, Table 2.2.2-1 (the Table) are designed and constructed in accordance with applicable requirements.

i) The seismic Category I components identified in Table 2.2.2-1 are located on the Nuclear Island.

To assure that seismic Category I components can withstand seismic design basis loads without loss of safetyfunction, all of the components in the Table are designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EG)

Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the PCS to confirm the satisfactory installation of the seismically qualified components. The inspection includes verification of component make/model/serial number and verification of component location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category Icomponents are located on the Nuclear Island.

ih A report exists and concludes that the seismic Cateoorv I components can withstand seismic design basis loads without loss of safety function.

Seismic Category Icomponents inthe Table require type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category Ivalves, as well as other passive seismic Category I mechanical components, is demonstrated byanalysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of the subsetof active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4). Structural integrity of the passive containment cooling water storage tank (PCCWST) is demonstrated by analysis.

Structural integrity of the water distribution bucket and water distribution weirs is demonstrated byanalysis in accordance with ANSI/AISC N690-1994 (Reference 5).

Safety-related (Class 1E) electrical components in the Table are seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 6). These components include 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 component in the Table is identified in Attachment A. Additional information about the methods used to qualify API 000 safety-related components is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 7). The EG Reports (Reference 8) identified in Attachment Acontain applicable test reports and associated documentation and conclude that the seismic Category Icomponents can withstand seismic design basis loadswithout loss of safety function.

iiil The report exists and concludes that the as-built comoonents including anchorage are seismicallv bounded bv the tested or analvzed conditions.

An inspection (Reference 1) is conducted to confirm the satisfactory installation of the

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 4 of 10 selsmlcally qualified components in the Table. The inspection verifies the component make/model/serial number, as-designed component mounting orientation, anchorage and clearances, and electrical and other interfaces. The documentation of installed configuration of selsmlcally qualified components includes photographs and/or sketches/drawings of component/mounting/interfaces.

As part of the seismic qualification program, consideration is given to the definition of the clearances needed around the component mounted in the plant, to permit the component to move during a postulated seismic event without causing impact between adjacent pieces of safety-related components. This is done as part of seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the components. EQ Reports (Reference 8) identify the component 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 components listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 6), and NRG Regulatory Guide (RG) 1.100 (Reference 9).

i) A report exists and concludes that the Class 1E components identified in Table 2.2.2-1 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 safetv function for the time required to perform the safetv function.

The harsh environment Class IE components in the Table are qualified by type testing and/or analyses. Class IE electrical component type testing is 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 components 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 1E electrical component located in a harsh environment. Additional information about the methods used to qualify API 000 safety-related components 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 conclude that the components 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 components and the associated wiring, cables, and terminations identified in Table 2.2.2-1 as being qualified for a harsh environment are bounded bv tvoe tests, analvses. or a combination of tvpe tests and analyses.

An inspection (Reference 1) is conducted of the PCS to confirm the satisfactory installation of the Class IE components in the Table. The inspection verifies the component location, make/model/serial number, as-designed component mounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the component is mounted are bounded by the tested or analyzed conditions. It also documents the installed configuration with photographs and/or sketches/drawings of component mounting and connections. The EQRR (Reference 2) identified in Attachment A document this

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 5 of 10 Inspection, and conclude that the as-built harsh environment Class 1E component and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 10).

Together, these reports (References 2 and 8) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I components identified in Table 2.2.2-1 are located on the Nuclear Island;

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

• The report exists and concludes that the as-built components including anchorage are seismically bounded by the tested or analyzed conditions;

• A report exists and concludes that the Class 1E components identified in Table 2.2.2-1 as being qualified for a harsh environmentcan 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 components and the associated wiring, cables, and terminations identified in Table 2.2.2-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

References 2 and 8 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.02.05a.i Completion Packages (References 12 and 13, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.

This review, which included now consolidated ITAAC Indexes 127,128,131 and 132, found the following relevant ITAAC findings associated with this ITAAC:

1) Notice of Nonconformance 99900404/2012-201 -04 (Closed)

2) Notice of Nonconformance 99901412/2012-201 -02 (Closed)

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

References (available for NRC Inspection)

1. ND-xx-xx-001, "EQ Walkdown ITAAC Guideline"

2. EQ As-Built Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 6 of 10

3. American Society of Mecfianical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition, 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. ANSI/AISC N690-1994, "American National Standard Specification for the Design, Fabrication, and Erection of Steel Safety-Related Structures for Nuclear Facilities"

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

7. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodologyfor Qualifying API 000 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 323-1974, "IEEE Standard for Qualifying Class 1E 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" 12.2.2.02.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.2.02.05a.i [Index Number 126]"

13.2.2.02.05a.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.2.02.05a.i [Index Number 126]"

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

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 7 of 10 Attachment A System: Passive Containment Cooling System (PCS)

Class 1E/

Envir Seismic Quai. Envir. Type of EQ Reports As-Buiit EQRR Component Name ^ Tag No, ^ Quai Quai. (Reference 8) (Reference 2)"

Cat. i ^ for Harsh Zone ^

Program ^

Envir.^3 2.2.02.05a.i-U3-PCCWST PCS-MT-01 Yes - N/A N/A Analysis APP-XXX-XXX-XXX EORR-PCDXXX Water Distribution 2.2.02.05a.i-U3-PCS-MT-03 Yes - N/A N/A Analysis APP-MT05-S3C-002 Bucket EORR-PCDXXX Water Distribution 2.2.02.05a.i-U3-PCS-MT-04 Yes - N/A N/A Analysis APP-MT05-S3C-002 Wiers (sic) EORR-PCDXXX Type PCCWST Isoiation APP-PV11-VBR-004/ 2.2.02.05a.i-U3-PCS-PL-V001A Yes Yes/No N/A N/A Testing &

Valve APP-PV11-VBR-003 EQRR-PCDXXX Analysis Type PCCWST Isolation APP-PV11-VBR-004/ 2.2.02.05a.i-U3-PCS-PL-V001B Yes Yes/No N/A N/A Testing &

Valve APP-PV11-VBR-003 EORR-PCDXXX Analysis Type PCCWST Isolation APP-PV01-VBR-012/ 2.2.02.05a.i-U3-PCS-PL-V001C Yes Yes/No N/A N/A Testing &

Valve MOV APP-PV01-VBR-011 EORR-PCDXXX Analysis Type PCCWST Isolation APP-PV01-VBR-012/ 2.2.02.05a.i-U3-PCS-PL-V002A Yes Yes/No N/A N/A Testing &

Block MOV APP-PV01-VBR-011 EORR-PCDXXX Analysis Type PCCWST Isolation APP-PV01-VBR-012/ 2.2.02.05a.i-U3-PCS-PL-V002B Yes Yes/No N/A N/A Testing &

Block MOV APP-PV01-VBR-011 EORR-PCDXXX Analysis Type PCCWST Isolation APP-PV01-VBR-012/ 2.2.02.05a.i-U3-PCS-PL-V002C Yes Yes/No N/A N/A Testing &

Block MOV APP-PV01-VBR-011 EQRR-PCDXXX Analysis PCS Recirculatlon Type APP-PV03-VBR-010/ 2.2.02.05a.i-U3-Return Isolation PCS-PL-V023 Yes -/No N/A N/A Testing &

APP-PV03-VBR-009 EORR-PCDXXX Valve Analysis

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 8 of 10 Class 1E/

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

• Zone ^

Quai Quai. (Reference 8) (Reference 2) ^

Cat. i + for Harsh Program ^

Envir.^

POCWST Supply to Type Fire Protection APP-PV03-VBR-010/ 2.2.02.05a.i-U3-PCS-PL-V005 Yes -/No N/A N/A Testing &

System Isolation APP-PV03-VBR-009 EQRR-PCDXXX Analysis Valve Type PCS Makeup to SFS APP-PV03-VBR-010/ 2.2.02.05a.i-U3-PCS-PL-V009 Yes -/No N/A N/A Testing &

Isolation Valve APP-PV03-VBR-009 EQRR-PCDXXX Analysis Type Water Makeup APP-PV03-VBR-010/ 2.2.02.05a.i-U3-PCS-PL-V044 Yes -/No N/A N/A Testing &

Isolation Valve APP-PV03-VBR-009 EQRR-PCDXXX Analysis Water Bucket Type APP-PV02-VBR-010/ 2.2.02.05a.i-U3-Makeup Line Drain PCS-PL-V015 Yes -/No N/A N/A Testing &

APP-PV02-VBR-009 EQRR-PCDXXX Valve Analysis Water Bucket Type APP-PV03-VBR-010/ 2.2.02.05a.i-U3-Makeup Line PCS-PL-V020 Yes -/No N/A N/A Testing &

APP-PV03-VBR-009 EQRR-PCDXXX Isolation Valve Analysis PCCWST Long-Term APP-PV03-VBR-014 / 2.2.02.05a.i-U3-Makeup Line Check PCS-PL-V039 Yes -/No N/A N/A Analysis APP-PV03-VBR-013 EQRR-PCDXXX Valve PCCWST Long-Term Type APP-PV02-VBR-010/ 2.2.02.05a.i-U3-Makeup Drain PCS-PL-V042 Yes -/No N/A N/A Testing &

APP-PV02-VBR-009 EQRR-PCDXXX isolation Analysis PCS Discharge to Type APP-PV02-VBR-010/ 2.2.02.05a.i-U3-SFS Pool Isolation PCS-PL-V045 Yes -/No N/A N/A Testing &

APP-PV02-VBR-009 EQRR-PCDXXX Valve Analysis Recirc Header Type Discharge to APP-PV03-VBR-010/ 2.2.02.05a.i-U3-PCS-PL-V046 Yes -/No N/A N/A Testing &

PCCWST Isolation APP-PV03-VBR-009 EQRR-PCDXXX Analysis Valve Type PCCWST Drain APP-PV02-VBR-010/ 2.2.02.05a.i-U3-PCS-PL-V049 Yes -/No N/A N/A Testing &

Isolation Valve APP-PV02-VBR-009 EQRR-PCDXXX Analysis

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 9 of 10 Class 1E/

Envir Seismic Quai. Envir. Type of EG Reports As-Built EQRR Component Name ^ Tag No.

• Quai (Reference 8) (Reference 2)

• Cat. 1 + for Harsh Zone ^ Quai.

Envir.+ 3 Program ^

Recirc Header Type APP-PV02-VBR-010/ 2.2.02.05a.i-U3-Discharge to SFS PCS-PL-V050 Yes -/No N/A N/A Testing &

APP-PV02-VBR-009 EQRR-PCDXXX Pool Isolation Valve Analysis PCCWST Discharge Type APP-PV02-VBR-010/ 2.2.02.05a.i-U3-to SFS Pool Isolation PCS-PL-V051 Yes -/No N/A N/A Testing &

APP-PV02-VBR-009 EQRR-PCDXXX Valve Analysis Type PCS Water Delivery APP-JE52-VBR-006 / 2.2.02.05a.i-U3-PCS-001 Yes Yes/No N/A N/A Testing &

Flow Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type PCS Water Delivery APP-JE52-VBR-006/ 2.2.02.05a.i-U3-PCS-002 Yes Yes/No N/A N/A Testing &

Flow Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type PCS Water Delivery N/A Testing &

APP-JE52-VBR-006 / 2.2.02.05a.i-U3-PCS-003 Yes Yes/No N/A Flow Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type PCS Water Delivery APP-JE52-VBR-006/ 2.2.02.05a.i-U3-PCS-004 Yes Yes/No N/A N/A Testing &

Flow Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type Containment APP-JE52-VBR-006 / 2.2.02.05a.i-U3-PCS-005 Yes Yes/Yes 7 E* Testing &

Pressure Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type Containment APP-JE52-VBR-006 / 2.2.02.05a.i-U3-PCS-006 Yes Yes/Yes 7 E* Testing &

Pressure Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type Containment APP-JE52-VBR-006/ 2.2.02.05a.i-U3-PCS-007 Yes Yes/Yes 7 E* Testing &

Pressure Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis Type Containment APP-JE52-VBR-006 / 2.2.02.05a.i-U3-PCS-008 Yes Yes/Yes 7 E* Testing &

Pressure Sensor APP-JE52-VBR-005 EQRR-PCDXXX Analysis PCCWST Water Type APP-JE52-VBR-002 / 2.2.02.05a.i-U3-PCS-010 Yes Yes/No N/A N/A Level Sensor Testing APP-JE52-VBR-001 EQRR-PCDXXX

U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 10 of 10 Class IE/

Envir Seismic Qual. Envir. Type of EG Reports As-Built EQRR Component Name ^ Tag No. ^ Qual Cat. i for Harsh Zone ^ Quai. (Reference 8) (Reference 2) ^

Program Envir.^

PCCWST Water Type APP-JE52-VBR-002 / 2.2.02.05a.i-U3-PCS-011 Yes Yes/No N/A N/A Level Sensor Testing APP-JE52-VBR-001 EQRR-PCDXXX High-range Type APP-JE52-VBR-006 / 2.2.02.05a.i-U3-Containment PCS-012 Yes Yes/Yes 7 E* Testing &

APP-JE52-VBR-005 EQRR-PCDXXX Pressure Sensor Analysis High-range Type APP-JE52-VBR-006 / 2.2.02.05a.i-U3-Containment PCS-013 Yes Yes/Yes 7 E* Testing &

APP-JE52-VBR-005 EQRR-PCDXXX Pressure Sensor Analysis High-range Type APP-JE52-VBR-006/ 2.2.02.05a.i-U3-Containment PCS-014 Yes Yes/Yes 7 E* Testing &

APP-JE52-VBR-005 EQRR-PCDXXX Pressure Sensor Analysis Notes:

+ Excerpt from COL Appendix C Table 2.2.2-1

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

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

• = Harsh Environment

3. Dash (-) indicates not applicable

4. The Unit 4 As-Built EQRR are numbered "2.2.02.05a.i-U4-EQRR-PCDXXX"