ND-22-0816, ITAAC Closure Notification of Completion of ITAAC 2.1.02.05a (Index Number 19)
| ML23196A009 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/15/2023 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| ND-22-0816 | |
| Download: ML23196A009 (1) | |
Text
Jamie M Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel July 15, 2023 Docket Nos.: 52-026 ND-22-0816 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 2.1.02.05a.i [Index Number 19]
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 2.1.02.05a.i [Index Number 19] to demonstrate that the Reactor Coolant System (RCS) components identified as seismic Category I or Class 1E 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 4 Completion of ITAAC 2.1.02.05a.i [Index Number 19]
JMC/AD/sfr
U.S. Nuclear Regulatory Commission ND-22-0816 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-22-0816 Enclosure Page 1 of 18 Southern Nuclear Operating Company ND-22-0816 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.05a.i [Index Number 19]
U.S. Nuclear Regulatory Commission ND-22-0816 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 1E 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.
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 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 2.1.2-1 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 1E 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 exists and concludes that the as-built Class 1E 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-22-0816 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 1E 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 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 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-22-0816 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 requirements.
Attachment A identifies the EQRR (Reference 3) completed to verify that the as-built seismic Category I equipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 6) and NRC Regulatory Guide (RG) 1.100 (Reference 9).
i) A report exists and concludes that the Class 1E equipment identified in Table 2.1.2-1 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.
The harsh environment Class 1E components in the Table are qualified by type testing and/or analyses. Class 1E 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 1E 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 1E 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 1E 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 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-22-0816 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 1E 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; and A report exists and concluded that the as-built Class 1E 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 4 ITAAC 2.1.02.05a.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 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) associated with this ITAAC:
NON 99901431/2013-201 closed - ML14073A652 NON 99901441/2014-201 closed - ML14307A578 NON 99900728/2017-201 closed - ML20216A590 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 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 approved plant programs and procedures.
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 6 of 18 References (available for NRC inspection)
- 3. EQ As-Built Reconciliation Reports (EQRR) as identified in Attachment A
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 (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. 2.1.02.05a.i-U4-CP-Rev0, Completion Package for Unit 4 ITAAC 2.1.02.05a.i [Index Number 19]
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 7 of 18 Attachment A System: Reactor Coolant System (RCS)
Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
Steam Generator 1 RCS-MB-01 Yes
-/-
N/A N/A Analysis SV4-MB01-Z0R-101 2.1.02.05a.i-U4-EQRR-PCD001 Steam Generator 2 RCS-MB-02 Yes
-/-
N/A N/A Analysis SV4-MB01-Z0R-101 2.1.02.05a.i-U4-EQRR-PCD001 RCP 1A RCS-MP-01A Yes No/No N/A N/A Analysis SV4-MP01-S2R-011 2.1.02.05a.i-U4-EQRR-PCD001 RCP 1B RCS-MP-01B Yes No/No N/A N/A Analysis SV4-MP01-S2R-011 2.1.02.05a.i-U4-EQRR-PCD001 RCP 2A RCS-MP-02A Yes No/No N/A N/A Analysis SV4-MP01-S2R-011 2.1.02.05a.i-U4-EQRR-PCD001 RCP 2B RCS-MP-02B Yes No/No N/A N/A Analysis SV4-MP01-S2R-011 2.1.02.05a.i-U4-EQRR-PCD001 Pressurizer RCS-MV-02 Yes No/No (heaters) N/A N/A Analysis SV4-MV20-Z0R-102 2.1.02.05a.i-U4-EQRR-PCD001 Automatic Depressurization System (ADS) Sparger A PXS-MW-01A Yes
-/-
N/A N/A Analysis SV4-MW01-S3R-001 2.1.02.05a.i-U4-EQRR-PCD001 ADS Sparger B PXS-MW-01B Yes
-/-
N/A N/A Analysis SV4-MW01-S3R-001 2.1.02.05a.i-U4-EQRR-PCD001 Pressurizer Safety Valve RCS-PL-V005A Yes
-/-
N/A N/A Analysis SV4-PV62-VBR-002 /
SV4-PV62-VBR-001 2.1.02.05a.i-U4-EQRR-PCD002 Pressurizer Safety Valve RCS-PL-V005B Yes
-/-
N/A N/A Analysis SV4-PV62-VBR-002 /
SV4-PV62-VBR-001 2.1.02.05a.i-U4-EQRR-PCD002 First-stage ADS Motor-operated Valve (MOV) RCS-PL-V001A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-014 /
SV4-PV01-VBR-013 2.1.02.05a.i-U4-EQRR-PCD002
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 8 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
First-stage ADS MOV RCS-PL-V001B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-014 /
SV4-PV01-VBR-013 2.1.02.05a.i-U4-EQRR-PCD002 Second-stage ADS MOV RCS-PL-V002A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-014 /
SV4-PV01-VBR-013 2.1.02.05a.i-U4-EQRR-PCD002 Second-stage ADS MOV RCS-PL-V002B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-014 /
SV4-PV01-VBR-013 2.1.02.05a.i-U4-EQRR-PCD002 Third-stage ADS MOV RCS-PL-V003A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-014 /
SV4-PV01-VBR-013 2.1.02.05a.i-U4-EQRR-PCD002 Third-stage ADS MOV RCS-PL-V003B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-014 /
SV4-PV01-VBR-013 2.1.02.05a.i-U4-EQRR-PCD002 Fourth-stage ADS Squib Valve RCS-PL-V004A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV70-VBR-005 /
SV4-PV70-VBR-004 2.1.02.05a.i-U4-EQRR-PCD002 Fourth-stage ADS Squib Valve RCS-PL-V004B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV70-VBR-005 /
SV4-PV70-VBR-004 2.1.02.05a.i-U4-EQRR-PCD002 Fourth-stage ADS Squib Valve RCS-PL-V004C Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV70-VBR-005 /
SV4-PV70-VBR-004 2.1.02.05a.i-U4-EQRR-PCD002 Fourth-stage ADS Squib Valve RCS-PL-V004D Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV70-VBR-005 /
SV4-PV70-VBR-004 2.1.02.05a.i-U4-EQRR-PCD002 ADS Discharge Header A Vacuum Relief Valve RCS-PL-V010A Yes Yes/Yes 1
M
- S Type Testing &
Analysis SV4-PV18-VBR-002 /
SV4-PV18-VBR-001 2.1.02.05a.i-U4-EQRR-PCD002
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 9 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
ADS Discharge Header B Vacuum Relief Valve RCS-PL-V010B Yes Yes/Yes 1
M
- S Type Testing &
Analysis SV4-PV18-VBR-002 /
SV4-PV18-VBR-001 2.1.02.05a.i-U4-EQRR-PCD002 First-stage ADS Isolation MOV RCS-PL-V011A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 First-stage ADS Isolation MOV RCS-PL-V011B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Second-stage ADS Isolation MOV RCS-PL-V012A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Second-stage ADS Isolation MOV RCS-PL-V012B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Third-stage ADS Isolation MOV RCS-PL-V013A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Third-stage ADS Isolation MOV RCS-PL-V013B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Fourth-stage ADS MOV RCS-PL-V014A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Fourth-stage ADS MOV RCS-PL-V014B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Fourth-stage ADS MOV RCS-PL-V014C Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 10 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
Fourth-stage ADS MOV RCS-PL-V014D Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV01-VBR-012 /
SV4-PV01-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Reactor Vessel Head Vent Valve RCS-PL-V150A Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV13-VBR-012 /
SV4-PV13-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Reactor Vessel Head Vent Valve RCS-PL-V150B Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV13-VBR-012 /
SV4-PV13-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Reactor Vessel Head Vent Valve RCS-PL-V150C Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV13-VBR-012 /
SV4-PV13-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 Reactor Vessel Head Vent Valve RCS-PL-V150D Yes Yes/Yes 1
M E
- S Type Testing &
Analysis SV4-PV13-VBR-012 /
SV4-PV13-VBR-011 2.1.02.05a.i-U4-EQRR-PCD002 RCS Hot Leg 1 Flow Sensor RCS-101A Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 1 Flow Sensor RCS-101B Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 1 Flow Sensor RCS-101C Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 1 Flow Sensor RCS-101D Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 2 Flow Sensor RCS-102A Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 11 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
RCS Hot Leg 2 Flow Sensor RCS-102B Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 2 Flow Sensor RCS-102C Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 2 Flow Sensor RCS-102D Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Cold Leg 1A Narrow Range Temperature Sensor RCS-121A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 1B Narrow Range Temperature Sensor RCS-121B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 1B Narrow Range Temperature Sensor RCS-121C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 1A Narrow Range Temperature Sensor RCS-121D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 2B Narrow Range Temperature Sensor RCS-122A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 2A Narrow Range Temperature Sensor RCS-122B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 2A Narrow Range Temperature Sensor RCS-122C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 12 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
RCS Cold Leg 2B Narrow Range Temperature Sensor RCS-122D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 1A Dual Range Temperature Sensor RCS-125A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 2A Dual Range Temperature Sensor RCS-125B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 1B Dual Range Temperature Sensor RCS-125C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Cold Leg 2B Dual Range Temperature Sensor RCS-125D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-131A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-131B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-131C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-131D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-132A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 13 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-132B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-132C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-132D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-133A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-133B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-133C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-133D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 1 Wide Range Temperature Sensor RCS-135A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Hot Leg 2 Wide Range Temperature Sensor RCS-135B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE53-VBR-002 /
SV4-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCS Wide Range Pressure Sensor RCS-140A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 14 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
RCS Wide Range Pressure Sensor RCS-140B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Wide Range Pressure Sensor RCS-140C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-004 /
SV4-JE52-VBR-003 2.1.02.05a.i-U4-EQRR-PCD004 RCS Wide Range Pressure Sensor RCS-140D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-004 /
SV4-JE52-VBR-003 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 1 Level Sensor RCS-160A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCS Hot Leg 2 Level Sensor RCS-160B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 Passive Residual Heat Removal (PRHR) Return Line Temperature Sensor RCS-161 Yes Yes/Yes 1
E
- S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003-Rev 0 Pressurizer Pressure Sensor RCS-191A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 Pressurizer Pressure Sensor RCS-191B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 Pressurizer Pressure Sensor RCS-191C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 Pressurizer Pressure Sensor RCS-191D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 15 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
Pressurizer Level Reference Leg Temperature Sensor RCS-193A Yes Yes/Yes 1
E
- S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003-Rev 0 Pressurizer Level Reference Leg Temperature Sensor RCS-193B Yes Yes/Yes 1
E
- S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003-Rev 0 Pressurizer Level Reference Leg Temperature Sensor RCS-193C Yes Yes/Yes 1
E
- S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003-Rev 0 Pressurizer Level Reference Leg Temperature Sensor RCS-193D Yes Yes/Yes 1
E
- S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003-Rev 0 Pressurizer Level Sensor RCS-195A Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 Pressurizer Level Sensor RCS-195B Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 Pressurizer Level Sensor RCS-195C Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 Pressurizer Level Sensor RCS-195D Yes Yes/Yes 1
E
- S Type Testing &
Analysis SV4-JE52-VBR-002 /
SV4-JE52-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCP 1A Bearing Water Temperature Sensor RCS-211A Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 1A Bearing Water Temperature Sensor RCS-211B Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 16 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
RCP 1A Bearing Water Temperature Sensor RCS-211C Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 1A Bearing Water Temperature Sensor RCS-211D Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 1B Bearing Water Temperature Sensor RCS-212A Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 1B Bearing Water Temperature Sensor RCS-212B Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 1B Bearing Water Temperature Sensor RCS-212C Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 1B Bearing Water Temperature Sensor RCS-212D Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 2A Bearing Water Temperature Sensor RCS-213A Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 2A Bearing Water Temperature Sensor RCS-213B Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 2A Bearing Water Temperature Sensor RCS-213C Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 2A Bearing Water Temperature Sensor RCS-213D Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 17 of 18 Equipment Name+
Tag No.+
Seismic Cat. I+
Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone1 Envir Qual Program2 Type of Qual.
EQ Reports (Reference 8)
As-Built EQRR (Reference 3)
RCP 2B Bearing Water Temperature Sensor RCS-214A Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 2B Bearing Water Temperature Sensor RCS-214B Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 2B Bearing Water Temperature Sensor RCS-214C Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 2B Bearing Water Temperature Sensor RCS-214D Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-MP01-VBR-002 /
SV4-MP01-VBR-001 2.1.02.05a.i-U4-EQRR-PCD003 RCP 1A Pump Speed Sensor RCS-281 Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE62-VBR-002 /
SV4-JE62-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCP 1B Pump Speed Sensor RCS-282 Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE62-VBR-002 /
SV4-JE62-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCP 2A Pump Speed Sensor RCS-283 Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE62-VBR-002 /
SV4-JE62-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004 RCP 2B Pump Speed Sensor RCS-284 Yes Yes/Yes 1
E
- Type Testing &
Analysis SV4-JE62-VBR-002 /
SV4-JE62-VBR-001 2.1.02.05a.i-U4-EQRR-PCD004
U.S. Nuclear Regulatory Commission ND-22-0816 Enclosure Page 18 of 18 Notes:
+ Excerpt from COL Appendix C Table 2.1.2-1
- 1. See Table 3D.5-1 of UFSAR
- 2. E = Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)
M = Mechanical Equipment Program (valve)
S = Qualified for submergence or operation with spray
- = Harsh Environment
- 3. Dash (-) indicates not applicable