ND-23-0403, ITAAC Closure Notification on Completion of ITAAC 2.2.04.05a.i (Index Number 226)
| ML23180A261 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/29/2023 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| ND-23-0403 | |
| Download: ML23180A261 (1) | |
Text
Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel June 29, 2023 Docket No.:
52-026 ND-23-0403 10 CFR 52.99(c)(1)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.2.04.05a.i [Index Number 226]
Ladies and Gentlemen:
In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP) Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.04.05a.i [Index Number 226] to demonstrate that the Steam Generator System (SGS) equipment identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 2.2.4-1 is designed and constructed in accordance with applicable requirements.
The closure process for this ITAAC is based on the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215.
This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.
If there are any questions, please contact Kelli Roberts at 706-848-6991.
Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.05a.i [Index Number 226]
JMC/JRB/sfr
U.S. Nuclear Regulatory Commission ND-23-0403 Page 2 of 2 cc:
Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)
Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4
U.S. Nuclear Regulatory Commission ND-23-0403 Page 1 of 13 Southern Nuclear Operating Company ND-23-0403 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.05a.i [Index Number 226]
U.S. Nuclear Regulatory Commission ND-23-0403 Page 2 of 13 ITAAC Statement Design Commitment:
5.a) The seismic Category I equipment identified in Table 2.2.4-1 can withstand seismic design basis loads without loss of safety function.
7.a) The Class 1E equipment identified in Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
Inspections, Tests, Analyses:
i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 2.2.4-1 is located on the Nuclear Island.
ii) Type tests, analyses, or a combination of type tests and analyses of seismic Category I equipment will be performed.
iii) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
i) Type tests, analyses, or a combination of type tests and analyses will be performed on Class 1E equipment located in a harsh environment.
ii) Inspection will be performed of the as-built Class 1E equipment and the associated wiring, cables, and terminations located in a harsh environment.
Acceptance Criteria:
i) The seismic Category I equipment identified in Table 2.2.4-1 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 1E equipment identified in Table 2.2.4-1 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 equipment and the associated wiring, cables, and terminations identified in Table 2.2.4-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.
U.S. Nuclear Regulatory Commission ND-23-0403 Page 3 of 13 ITAAC Determination Basis This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Steam Generator System (SGS) equipment identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 2.2.4-1 (the Table) is designed and constructed in accordance with applicable requirements.
i) The seismic Category I equipment identified in Table 2.2.4-1 is located on the Nuclear Island.
To assure that seismic Category I equipment can withstand seismic design basis loads without loss of safety function, all the equipment in the Table is designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EQ) ITAAC As-built Walkdown Guideline and EQ ITAAC As-built Installation Documentation Guideline (References 1 and 2), an inspection was conducted of the SGS to confirm the satisfactory installation of the seismically qualified equipment. The inspection includes 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 document the results of the inspection and conclude 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 loads without loss of safety function.
Seismic Category I equipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 4). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 5).
Safety-related (Class 1E) 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 1E) field sensors and the safety-related active valve accessories such as electric actuators, position switches, pilot solenoid valves and electrical connector assemblies. The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment in the Table is identified in Attachment A. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 7). The EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and conclude 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 equipment in the Table. The inspection verifies 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-23-0403 Page 4 of 13 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. This is done as part of seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment. EQ Reports (Reference 8) 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 3) 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 6), and NRC Regulatory Guide (RG) 1.100 (Reference 9).
i) A report exists and concludes that the Class 1E equipment identified in Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
The harsh environment Class 1E equipment in the Table was qualified by type testing and/or analyses. Class 1E electrical equipment 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 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 1E electrical equipment located in a harsh environment. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 7).
EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and 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 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.4-1 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 SGS to confirm the satisfactory installation of the Class 1E equipment in the Table. The inspection verifies 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 3) identified in Attachment A document this inspection, and conclude that the as-built harsh environment Class 1E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 10).
U.S. Nuclear Regulatory Commission ND-23-0403 Page 5 of 13 Together, these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met:
The seismic Category I equipment identified in Table 2.2.4-1 is located on the Nuclear Island; A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions; A report exists and concludes that the Class 1E equipment identified in Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function; and A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.4-1 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 4 ITAAC 2.2.04.05a.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 and associated corrective actions.
This review, which included now-consolidated ITAAC Indexes 227, 228, 231, and 232, found no relevant ITAAC findings associated with this ITAAC.
ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.04.05a.i was performed for VEGP Unit 4 and that the prescribed acceptance criteria are met.
Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with the approved plant programs and procedures.
References (available for NRC inspection)
- 3. EQ As-Built Reconciliation Reports as identified in Attachment A for Units 4
U.S. Nuclear Regulatory Commission ND-23-0403 Page 6 of 13
Code,Section III, 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 1E Equipment for Nuclear Power Generating Stations
- 7. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment
- 8. Equipment Qualification 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. 2.2.04.05a.i-U4-CP-Rev0, Completion Package for Unit 4 ITAAC 2.2.04.05a.i [Index Number 226]
U.S. Nuclear Regulatory Commission ND-23-0403 Page 7 of 13 Attachment A System: Steam Generator System Equipment Name +
Tag No. +
Seismic Cat. I +
Class 1E/
Qual. For Harsh Envir.+ 3 Envir.
Zone 1 Envir Qual Program 2 Type of Qual.
EQ Reports As-Built EQRR Main Steam Safety Valve SG01 SGS-PL-V030A Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG02 SGS-PL-V030B Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG01 SGS-PL-V031A Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG02 SGS-PL-V031B Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG01 SGS-PL-V032A Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG02 SGS-PL-V032B Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG01 SGS-PL-V033A Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG02 SGS-PL-V033B Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG01 SGS-PL-V034A Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002
U.S. Nuclear Regulatory Commission ND-23-0403 Page 8 of 13 Equipment Name +
Tag No. +
Seismic Cat. I +
Class 1E/
Qual. For Harsh Envir.+ 3 Envir.
Zone 1 Envir Qual Program 2 Type of Qual.
EQ Reports As-Built EQRR Main Steam Safety Valve SG02 SGS-PL-V034B Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG01 SGS-PL-V035A Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Safety Valve SG02 SGS-PL-V035B Yes
-/-
N/A N/A Type Testing &
Analysis SV4-PV65-VBR-012 /
SV4-PV65-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV01-VBR-016 /
SV4-PV01-VBR-015 2.2.04.05a.i-U4-EQRR-PCD002 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV01-VBR-016 /
SV4-PV01-VBR-015 2.2.04.05a.i-U4-EQRR-PCD002 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Steam Line Condensate Drain Isolation Valve SGS-PL-V036B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Line Isolation Valve SGS-PL-V040A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV64-VBR-012 /
SV4-PV64-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Line Isolation Valve SGS-PL-V040B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV64-VBR-012 /
SV4-PV64-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002
U.S. Nuclear Regulatory Commission ND-23-0403 Page 9 of 13 Equipment Name +
Tag No. +
Seismic Cat. I +
Class 1E/
Qual. For Harsh Envir.+ 3 Envir.
Zone 1 Envir Qual Program 2 Type of Qual.
EQ Reports As-Built EQRR Steam Line Condensate Drain Control Valve SGS-PL-V086B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Main Feedwater Isolation Valve SGS-PL-V057A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV67-VBR-012 /
SV4-PV67-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Main Feedwater Isolation Valve SGS-PL-V057B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV67-VBR-012 /
SV4-PV67-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.2.04.05a.i-U4-EQRR-PCD002 Steam Generator Blowdown Isolation Valve SGS-PL-V074A Yes Yes/Yes 10 M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Steam Generator Blowdown Isolation Valve SGS-PL-V074B Yes Yes/Yes 10 M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Steam Generator Blowdown Isolation Valve SGS-PL-V075A Yes Yes/Yes 10 M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Steam Generator Blowdown Isolation Valve SGS-PL-V075B Yes Yes/Yes 10 M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Power-operated Relief Valve SGS-PL-V233A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV66-VBR-002 /
SV4-PV66-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Power-operated Relief Valve SGS-PL-V233B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV66-VBR-002 /
SV4-PV66-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002
U.S. Nuclear Regulatory Commission ND-23-0403 Page 10 of 13 Equipment Name +
Tag No. +
Seismic Cat. I +
Class 1E/
Qual. For Harsh Envir.+ 3 Envir.
Zone 1 Envir Qual Program 2 Type of Qual.
EQ Reports As-Built EQRR Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Main Steam Isolation Valve Bypass Isolation SGS-PL-V240B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV14-VBR-002 /
SV4-PV14-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Main Feedwater Control Valve SGS-PL-V250A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV69-VBR-002 /
SV4-PV69-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Main Feedwater Control Valve SGS-PL-V250B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV69-VBR-002 /
SV4-PV69-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Startup Feedwater Control Valve SGS-PL-V255A Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV69-VBR-002 /
SV4-PV69-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Startup Feedwater Control Valve SGS-PL-V255B Yes Yes/Yes 5
M
- E S Type Testing &
Analysis SV4-PV69-VBR-002 /
SV4-PV69-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Main Feedwater Thermal Relief Valve SGSPLV257A Yes
/
N/A N/A Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Main Feedwater Thermal Relief Valve SGSPLV257B Yes
/
N/A N/A Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Startup Feedwater Thermal Relief Valve SGSPLV258A Yes
/
N/A N/A Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Startup Feedwater Thermal Relief Valve SGSPLV258B Yes
/
N/A N/A Type Testing &
Analysis SV4-PV16-VBR-002 /
SV4-PV16-VBR-001 2.2.04.05a.i-U4-EQRR-PCD002 Steam Generator 1 Narrow Range Level Sensor SGS-001 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001
U.S. Nuclear Regulatory Commission ND-23-0403 Page 11 of 13 Equipment Name +
Tag No. +
Seismic Cat. I +
Class 1E/
Qual. For Harsh Envir.+ 3 Envir.
Zone 1 Envir Qual Program 2 Type of Qual.
EQ Reports As-Built EQRR Steam Generator 1 Narrow Range Level Sensor SGS-002 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 1 Narrow Range Level Sensor SGS-003 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 1 Narrow Range Level Sensor SGS-004 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Narrow Range Level Sensor SGS-005 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Narrow Range Level Sensor SGS-006 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Narrow Range Level Sensor SGS-007 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Narrow Range Level Sensor SGS-008 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 1 Wide Range Level Sensor SGS-011 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 1 Wide Range Level Sensor SGS-012 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Wide Range Level Sensor SGS-013 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Wide Range Level Sensor SGS-014 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001
U.S. Nuclear Regulatory Commission ND-23-0403 Page 12 of 13 Equipment Name +
Tag No. +
Seismic Cat. I +
Class 1E/
Qual. For Harsh Envir.+ 3 Envir.
Zone 1 Envir Qual Program 2 Type of Qual.
EQ Reports As-Built EQRR Steam Generator 1 Wide Range Level Sensor SGS-015 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 1 Wide Range Level Sensor SGS-016 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Wide Range Level Sensor SGS-017 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Wide Range Level Sensor SGS-018 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Main Steam Line Steam Generator 1 Pressure Sensor SGS-030 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Main Steam Line Steam Generator 1 Pressure Sensor SGS-031 Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Main Steam Line Steam Generator 1 Pressure Sensor SGS-032 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Main Steam Line Steam Generator 1 Pressure Sensor SGS-033 Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Main Steam Line Steam Generator 2 Pressure Sensor SGS-034 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Main Steam Line Steam Generator 2 Pressure Sensor SGS-035 Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Main Steam Line Steam Generator 2 Pressure Sensor SGS-036 Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001
U.S. Nuclear Regulatory Commission ND-23-0403 Page 13 of 13 Equipment Name +
Tag No. +
Seismic Cat. I +
Class 1E/
Qual. For Harsh Envir.+ 3 Envir.
Zone 1 Envir Qual Program 2 Type of Qual.
EQ Reports As-Built EQRR Main Steam Line Steam Generator 2 Pressure Sensor SGS-037 Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 1 Startup Feedwater Flow Sensor SGS-55A Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 1 Startup Feedwater Flow Sensor SGS-55B Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Startup Feedwater Flow Sensor SGS-56A Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Steam Generator 2 Startup Feedwater Flow Sensor SGS-56B Yes Yes/No N/A N/A Type Testing SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.2.04.05a.i-U4-EQRR-PCD001 Notes:
+ Excerpt from COL Appendix C Table 2.2.4-1
- 1. See Table 3D.5-1 of UFSAR
- 2. E - Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)
M - Mechanical Equipment Program (valve)
S = Qualified for submergence or operation with spray
- - Harsh Environment
- 3. Dash (-) indicates not applicable