ML22125A268
| ML22125A268 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/05/2022 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ND-21 -1029 | |
| Download: ML22125A268 (21) | |
Text
.>-,. Southern Nuclear MAY O 5 2022 Docket Nos.: 52-025 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 -1029 10 CFR 52.99(c)(1)
ITAAC Closure Notification on Completion of ITAAC 2.1.02.05a.i (Index Number 191 In accordance with 10 CFR 52.99(c)(1 ), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)
Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.05a.i [Index Number 191 to demonstrate that the Reactor Coolant System (RCS) components identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2.1.2-1 are designed and constructed in accordance with applicable requirements.
The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.
This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.
If there are any questions, please contact Kelli Roberts at 706-848-6991.
Respectfully submitted,
~~
Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
JMC/LBP/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.1.02.05a.i [Index Number 191
U.S. Nuclear Regulatory Commission ND-21-1029 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear 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-21-1029 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S.L. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GOS Associates, Inc.
Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 1 of 18 Southern Nuclear Operating Company ND-21-1029 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.1.02.0Sa.i [Index Number 19]
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 2 of 18 ITAAC Statement Design Commitment 5.a) The seismic Category I equipment identified in Table 2.1.2-1 can withstand seismic design basis loads without loss of safety function.
7.a) The Class 1 E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time 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 1 E equipment located in a harsh environment.
ii) Inspection will be performed of the as-built Class 1 E equipment and the associated wiring,
cables, and terminations located in a harsh environment.
Acceptance Criteria i) The seismic Category I equipment identified in Table 2.1.2-1 is located on the Nuclear Island.
ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.
iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
i) A report exists and concludes that the Class 1 E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
ii) A report exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.1.2-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.
U.S. Nuclear Regulatory Commission ND-21 -1029 Enclosure Page 3 of 18 ITAAC Determination Basis This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Reactor Coolant System (RCS) components identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2.1.2-1 (the Table) are designed and constructed in accordance with applicable requirements.
i) The seismic Category I equipment identified in Table 2.1.2-1 is located on the Nuclear Island To assure that seismic Category I components can withstand seismic design basis loads without loss of safety function, all the components in the Table are designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EQ) ITAAC As-built Walkdown Guideline and the EQ ITAAC As-built Installation Documentation Guideline (References 1 and 2), an inspection was conducted of the RCS to confirm the satisfactory installation of the seismically qualified components. The inspection included verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). The EQ As-Built Reconciliation Reports (EQRR) (Reference 3) identified in Attachment A documented the results of the inspection and concluded that the seismic Category I components are located on the Nuclear Island.
ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.
Seismic Category I components in the Table require type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves, as well as other passive seismic Category I mechanical equipment, is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section Ill (Reference 4). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 5).
Safety-related (Class 1 E) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 6). This equipment includes safety-related (Class 1 E) field sensors and the safety-related active valve accessories such as electric actuators, position switches, pilot solenoid valves and electrical connector assemblies. The specific qualification method (i.e., type testing, analysis, or combination) used for each component in the Table is identified in Attachment A Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 7). The EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and concluded that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.
iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
An inspection (References 1 and 2) was conducted to confirm the satisfactory installation of the seismically qualified components in the Table. The inspection verified the equipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other interfaces. The documentation of installed configuration of
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 4 of 18 seismically qualified components includes photographs and/or sketches/drawings of equipment/mounting/interfaces._
As part of the seismic qualification program, consideration is given to the definition of the clearances needed around the equipment mounted in the plant to permit the equipment to move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. When required, seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports (Reference 8) identified the equipment mounting employed for qualification and established interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification. Interface requirements are defined based on the test configuration and other design 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 1 E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
The harsh environment Class 1 E components in the Table are qualified by type testing and/or analyses. Class 1 E electrical component type testing was performed in accordance with IEEE Standard 323-1974 (Reference 10) and RG 1.89 (Reference 11) to meet the requirements of 10 CFR 50.49. Type testing of safety-related equipment meets the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment A identifies the EQ program and specific qualification method for each safety-related mechanical or Class 1 E electrical component located in a harsh environment. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 7).
EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and concluded that the equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
ii) A report exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.1.2-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses An inspection (References 1 and 2) was conducted of the RCS to confirm the satisfactory installation of the Class 1 E components in the Table. The inspection verified the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirmed that the environmental conditions for the zone (Attachment A) in which the component is mounted are bounded by the tested and/or analyzed conditions. It also documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 3) identified in Attachment A documented this inspection and concluded that the as-built harsh environment Class 1 E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-197 4 (Reference 10).
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 5 of 18 Together, these reports (References 3 and 8) provide evidence that the ITAAC Acceptance Criteria requirements are met:
The seismic Category I equipment identified in Table 2.1.2-1 is located on the Nuclear Island; A report exists and concluded that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; A report exists and concluded that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions; A report exists and concluded that the Class 1 E equipment identified in Table 2.1. 2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function; and A report exists and concluded that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.1.2-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.
References 3 and 8 are available for NRC inspection as part of the Unit 3 ITAAC 2.1.02.05a.i Completion Package (Reference 12).
ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all lTAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 20, 21, 24, and 25, found three closed notices of non-conformance (NON) and one closed non-cited violation (NCV) associated with this IT AAC:
- 1) NON 99901431/2013-201 closed - ML14073A652
- 2) NON 99901441/2014-201 closed - ML14307A578
- 3) NON 99900728/2017-201 closed - ML20216A590
- 4) NCV 05200025/2021005 closed - ML22045A005 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.05a.i was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 6 of 18 Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.
References (available for NRC inspection)
- 3. EQ As-Built Reconciliation Reports (EQRR) as identified in Attachment A
Code, Section Ill, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda
- 5. ASME QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007
- 6. IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1 E Equipment for Nuclear Power Generating Stations"
- 7. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 30, "Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment"
- 8. Equipment Qualification (EQ) Reports as identified in Attachment A
- 9. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"
- 10. IEEE Standard 323-197 4, "IEEE Standard for Qualifying Class 1 E Equipment for Nuclear Power Generating Stations" 11. Regulatory Guide 1.89, Rev 1, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants"
- 12. 2.1.02.05a.i-U3-CP-Rev0, "Completion Package for Unit 3 ITAAC 2.1.02.0Sa.i [Index Number 19]"
U.S. Nuclear Regulatory Commission N D-21-1029 Enclosure Page 7 of 18 Equipment Name+
Tag No.+
Steam Generator 1 RCS-MB-01 Steam Generator 2 RCS-MB-02 RCP1A RCS-MP-01A RCP1B RCS-MP-01 B RCP2A RCS-MP-02A RCP 2B RCS-MP-02B Pressurizer RCS-MV-02 Automatic Depressurization System PXS-MW-01A (ADS) Sparger A ADS Sparger B PXS-MW-01 B Pressurizer Safety Valve RCS-PL-V005A Pressurizer Safety Valve RCS-PL-V005B First-stage ADS Motor-RCS-PL-V001 A operated Valve (MOV)
Seismic Cat. 1+
Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Attachment A System: Reactor Coolant System (RCS)
Class 1 E/ Qua I "Envir. Envir Qual Type of For Harsh EQ Reports As-Built EQRR Envir.+ 3 Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
-/-
N/A N/A Analysis SV3-MB01-Z0R-101 2.1.02.05a.i-U3-EQRR-PCD003
-/-
N/A N/A Analysis SV3-MB01-Z0R-101 2.1.02.05a.i-U3-EQRR-PCD003 No/No N/A N/A Analysis SV3-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCD003 No/No N/A N/A Analysis SV3-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCD003 No/No N/A N/A Analysis SV3-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCD003 No/No N/A N/A Analysis SV3-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCD003 No/No (heaters) N/A N/A Analysis SV3-MV20-Z0R-102 2.1.02.05a.i-U3-EQRR-PCD003
-/-
N/A N/A Analysis SV3-MW01-S3R-001 2.1.02.05a.i-U3-EQRR-PCD003
-/-
N/A N/A Analysis SV3-MW01 -S3R-001 2.1.02.05a.i-U3-EQRR-PCD003
-/-
N/A N/A Analysis SV3-PV62-VBR-002 / 2.1.02.05a.i-U3-EQRR-SV3-PV62-VBR-001 PCD004
-/-
N/A N/A Analysis SV3-PV62-VBR-002 / 2.1.02.05a.i-U3-EQRR-SV3-PV62-VBR-001 PCD004 Type SV3-PV01-VBR-014 /
2.1.02.05a.i-U3-EQRR-Yes/Yes 1
ME
- S Testing &
Analvsis SV3-PV01-VBR-013 PCD004
U.S. Nuclear Regulatory Commission N D-21-1029 Enclosure Page 8 of 18 Equipment Name+
Tag No.+
First-stage ADS MOV RCS-PL-V001 B Second-stage ADS MOV RCS-PL-V002A Second-stage ADS MOV RCS-PL-V002B Third-stage ADS MOV RCS-PL-V003A Third-stage ADS MOV RCS-PL-V003B Fourth-stage ADS Squib RCS-PL-V004A Valve Fourth-stage ADS Squib RCS-PL-V004B Valve Fourth-stage ADS Squib RCS-PL-V004C Valve Fourth-stage ADS Squib RCS-PL-V004D Valve ADS Discharge Header A RCS-PL-V01 0A Vacuum Relief Valve Seismic Class 1 E/ Qual. Envir.
Cat. 1+
For Harsh Zone1 Envir.+ 3 Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Yes Yes/Yes 1
Envir Qual Type of EQ Reports As-Built EQRR Program2 Qual.
(Reference 8)
(Reference 3)
Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV01-VBR-013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV01-VBR-013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV01 -VBR-013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV01-VBR-013 PCD004 Analysis Type SV3-PV01-VBR-014 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV01-VBR-013 PCD004 Analysis Type SV3-PV70-VBR-005 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV70-VBR-004 PCD004 Analysis Type SV3-PV70-VBR-005 / 2.1.02.05a.i-U3-EORR-ME
- S Testing & SV3-PV70-VBR-004 PCD004 Analysis Type SV3-PV70-VBR-005 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV70-VBR-004 PCD004 Analvsis Type SV3-PV70-VBR-005 / 2.1.02.05a.i-U3-EQRR-ME
- S Testing & SV3-PV70-VBR-004 PCD004 Analvsis Type SV3-PV18-VBR-002 / 2.1.02.05a.i-U3-EQRR-M
- S Testing & SV3-PV18-VBR-001 PCD004 Analvsis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 9 of 18 Equipment Name+
Tag No.+
ADS Discharge Header B RCS-PL-V01 OB Vacuum Relief Valve First-stage ADS Isolation RCS-PL-V011 A MOV First-stage ADS Isolation RCS-PL-V011 B MOV Second-stage ADS RCS-PL-V012A Isolation MOV Second-stage ADS RCS-PL-V012B Isolation MOV Third-stage ADS Isolation RCS-PL-V013A MOV Third-stage ADS Isolation RCS-PL-V013B MOV Fourth-stage ADS MOV RCS-PL-V01 4A Fourth-stage ADS MOV RCS-PL-V014B Fourth-stage ADS MOV RCS-PL-V014C Seismic Class 1 E/ Qual.
Cat. 1+
For Harsh Envir.+ 3 Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Envir. Envir Qual Type of EQ Reports As-Built EQRR Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
Type SV3-PV18-VBR-002 / 2.1.02.05a.i-U3-EQRR-1 M
- S Testing & SV3-PV18-VBR-001 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV01 -VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 10 of 18 Equipment Name+
Tag No.+
Fourth-stage ADS MOV RCS-PL-V01 4D Reactor Vessel Head RCS-PL-V150A Vent Valve Reactor Vessel Head RCS-PL-V150B Vent Valve Reactor Vessel Head RCS-PL-V150C Vent Valve Reactor Vessel Head RCS-PL-V150D Vent Valve RCS Hot Leg 1 Flow RCS-101A Sensor RCS Hot Leg 1 Flow RCS-101B Sensor RCS Hot Leg 1 Flow RCS-101C Sensor RCS Hot Leg 1 Flow RCS-101 D Sensor RCS Hot Leg 2 Flow RCS-102A Sensor Seismic Class 1 E/ Qual.
Cat. 1+
For Harsh Envir.+ 3 Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Envir. Envir Qual Type of EQ Reports As-Built EQRR Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
Type SV3-PV01-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV01-VBR-011 PCD004 Analysis Type SV3-PV13-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV13-VBR-011 PCD004 Analysis Type SV3-PV13-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV13-VBR-011 PCD004 Analysis Type SV3-PV13-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV13-VBR-011 PCD004 Analysis Type SV3-PV13-VBR-012 / 2.1.02.05a.i-U3-EQRR-1 ME
- S Testing & SV3-PV13-VBR-011 PCD004 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing & SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing & SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing & SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing & SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing & SV3-JE52-VBR-001 PCD006 Analysis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 11 of 18 Equipment Name+
Tag No.+
RCS Hot Leg 2 Flow RCS-102B Sensor RCS Hot Leg 2 Flow RCS-102C Sensor RCS Hot Leg 2 Flow RCS-102D Sensor RCS Cold Leg 1 A Narrow Range Temperature RCS-121A Sensor RCS Cold Leg 1 B Narrow Range Temperature RCS-121B Sensor RCS Cold Leg 1 B Narrow Range Temperature RCS-121C Sensor RCS Cold Leg 1 A Narrow Range Temperature RCS-121 D Sensor RCS Cold Leg 2B Narrow Range Temperature RCS-122A Sensor RCS Cold Leg 2A Narrow Range Temperature RCS-122B Sensor RCS Cold Leg 2A Narrow Range Temperature RCS-122C Sensor Seismic Class 1 E/ Qual.
Cat. 1+
For Harsh Envir.+ 3 Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Envir. Envir Qual Type of EQ Reports As-Built EQRR Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-J E53-VBR-00 1 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing & APP-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-JE53-VBR-001 PCD005 Analysis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 12 of 18 Equipment Name+
Tag No.+
RCS Cold Leg 2B Narrow Range Temperature RCS-122D Sensor RCS Cold Leg 1 A Dual Range Temperature RCS-125A Sensor RCS Cold Leg 2A Dual Range Temperature RCS-125B Sensor RCS Cold Leg 1 B Dual Range Temperature RCS-125C Sensor RCS Cold Leg 2B Dual Range Temperature RCS-125D Sensor RCS Hot Leg 1 Narrow Range Temperature RCS-131A Sensor RCS Hot Leg 2 Narrow Range Temperature RCS-131 B Sensor RCS Hot Leg 1 Narrow Range Temperature RCS-131 C Sensor RCS Hot Leg 2 Narrow Range Temperature RCS-131 D Sensor RCS Hot Leg 1 Narrow Range Temperature RCS-132A Sensor Seismic Class 1 E/ Qual.
Cat. 1+
For Harsh Envir.+ 3 Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Envir. Envir Qual Type of EQ Reports As-Built EQRR Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD00S Ana!_ysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-J E53-VBR-00 1 PCD00S Ana!Y_sis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD00S Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD00S Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing & APP-JE53-VBR-001 PCD00S Ana!_ysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-J E53-VBR-00 1 PCD00S Ana!Y_sis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD00S Ana!_ysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD00S Ana!Y_sis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD00S Ana!_ysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-J E53-VBR-00 1 PCD00S Ana!Y_sis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 13 of 18 Equipment Name+
Tag No.+
RCS Hot Leg 2 Narrow Range Temperature RCS-132B Sensor RCS Hot Leg 1 Narrow Range Temperature RCS-132C Sensor RCS Hot Leg 2 Narrow Range Temperature RCS-132O Sensor RCS Hot Leg 1 Narrow Range Temperature RCS-133A Sensor RCS Hot Leg 2 Narrow Range Temperature RCS-133B Sensor RCS Hot Leg 1 Narrow Range Temperature RCS-133C Sensor RCS Hot Leg 2 Narrow Range Temperature RCS-133O Sensor RCS Hot Leg 1 Wide Range Temperature RCS-135A Sensor RCS Hot Leg 2 Wide Range Temperature RCS-135B Sensor RCS Wide Range RCS-140A Pressure Sensor Seismic Class 1 E/ Qual.
Cat. 1+
For Harsh Envir.+ 3 Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Envir. Envir Qual Type of EQ Reports As-Built EQRR Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-J E53-VB R-001 PCD005 Analysis Type SV3-JE53-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE53-VBR-001 PCD005 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E*S Testing &
SV3-JE52-VBR-001 PCD006 Analysis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 14 of 18 Equipment Name+
Tag No.+
RCS Wide Range RCS-140B Pressure Sensor RCS Wide Range RCS-140C Pressure Sensor RCS Wide Range RCS-140O Pressure Sensor RCS Hot Leg 1 Level RCS-160A Sensor RCS Hot Leg 2 Level RCS-160B Sensor Passive Residual Heat Removal (PRHR) Return RCS-161 Line Temperature Sensor Pressurizer Pressure RCS-191A Sensor Pressurizer Pressure RCS-191B Sensor Pressurizer Pressure RCS-191C Sensor Pressurizer Pressure RCS-191O Sensor Seismic Class 1 E/ Qual.
Cat. 1+
For Harsh Envir.+ 3 Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Envir. Envir Qual Type of EQ Reports As-Built EQRR Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-004 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-J E52-VBR-003 PCD006 Analysis Type SV3-JE52-VBR-004 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-003 PCD006 Analy_sis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type APP-JE53-VBR-002 2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
APP-J E53-VBR-00 1 PCD005-Rev 0 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-001 PCD006 Analysis Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
SV3-JE52-VBR-001 PCD006 Analysis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 15 of 18 Equipment Name+
Tag No.+
Pressurizer Level Reference Leg RCS-193A Temperature Sensor Pressurizer Level Reference Leg RCS-193B Temperature Sensor Pressurizer Level Reference Leg RCS-193C Temperature Sensor Pressurizer Level Reference Leg RCS-193D Temperature Sensor Pressurizer Level Sensor RCS-195A Pressurizer Level Sensor RCS-195B Pressurizer Level Sensor RCS-195C Pressurizer Level Sensor RCS-195D RCP 1 A Bearing Water RCS-211A Temperature Sensor RCP 1 A Bearing Water RCS-211 B Temperature Sensor Seismic Class 1 E/ Qual For Harsh Cat. 1+
Envir.+ 3 Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes Yes Yes/Yes "Envir. Envir Qual Type of EQ Reports As-Built EQRR Zone1 Program2 Qual.
(Reference 8)
(Reference 3)
Type 1
E
- S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EORR-Analysis APP-JE53-VBR-001 PCD005-Rev 0 Type 1
E
- S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Analysis APP-JE53-VBR-001 PCD005-Rev 0 Type 1
E
- S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Analvsis APP-JE53-VBR-001 PCD005-Rev O Type 1
E
- S Testing & APP-JE53-VBR-002 / 2.1.02.05a.i-U3-EQRR-Analvsis APP-JE53-VBR-001 PCD005-Rev O Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EORR-1 E
- S Testing &
Analysis SV3-JE52-VBR-001 PCD006 Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
Analvsis SV3-JE52-VBR-001 PCD006 Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EQRR-1 E
- S Testing &
Analvsis SV3-JE52-VBR-001 PCD006 Type SV3-JE52-VBR-002 /
2.1.02.05a.i-U3-EORR-1 E
- S Testing &
Analvsis SV3-JE52-VBR-001 PCD006 Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-1 E
- Testing &
Analysis SV3-MP01-VBR-001 PCD005 Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-1 E
- Testing &
Analysis SV3-MP01-VBR-001 PCD005
U.S. Nuclear Regulatory Commission N D-21-1029 Enclosure Page 16 of 18 Equipment Name+
Tag No.+
RCP 1 A Bearing Water Temperature Sensor RCS-211 C RCP 1 A Bearing Water Temperature Sensor RCS-211 D RCP 1 B Bearing Water Temperature Sensor RCS-212A RCP 1 B Bearing Water Temperature Sensor RCS-212B RCP 1 B Bearing Water Temperature Sensor RCS-212C RCP 1 B Bearing Water Temperature Sensor RCS-212D RCP 2A Bearing Water Temperature Sensor RCS-213A RCP 2A Bearing Water Temperature Sensor RCS-213B RCP 2A Bearing Water Temperature Sensor RCS-213C RCP 2A Bearing Water Temperature Sensor RCS-213D Seismic Cat. 1+
Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Class 1 E/ Qual. Envir. Envir Qual For Harsh Envir.+ 3 Zone1 Program2 Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Yes/Yes 1
E
- Type of EQ Reports As-Built EQRR Qual.
(Reference 8)
(Reference 3)
Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EORR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01 -VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 17 of 18 Equipment Name+
Tag No.+
RCP 2B Bearing Water Temperature Sensor RCS-214A RCP 2B Bearing Water RCS-214B Temperature Sensor RCP 2B Bearing Water RCS-214C Temperature Sensor RCP 2B Bearing Water RCS-214D Temperature Sensor RCP 1 A Pump Speed RCS-281 Sensor RCP 1 B Pump Speed RCS-282 Sensor RCP 2A Pump Speed Sensor RCS-283 RCP 2B Pump Speed RCS-284 Sensor Seismic Class 1 E/ Qual. Envir. Envir Qual For Harsh Cat. 1+
Envir.+ 3 Zone1 Program2 Yes Yes/Yes 1
E
- Yes Yes/Yes 1
E
- Yes Yes/Yes 1
E
- Yes Yes/Yes 1
E
- Yes Yes/Yes 1
E
- Yes Yes/Yes 1
E
- Yes Yes/Yes 1
E
- Yes Yes/Yes 1
E
- Type of EQ Reports As-Built EQRR Qual.
(Reference 8)
(Reference 3)
Type SV3-MP01 -VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing & SV3-MP01-VBR-001 PCD005 Analysis Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing &
Analysis SV3-MP01 -VBR-001 PCD005 Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing &
Analysis SV3-MP01-VBR-001 PCD005 Type SV3-MP01-VBR-002 / 2.1.02.05a.i-U3-EQRR-Testing &
Analysis SV3-MP01-VBR-001 PCD005 Type SV3-JE62-VBR-002 /
2.1.02.05a.i-U3-EQRR-Testing &
Analysis SV3-JE62-VBR-001 PCD006 Type SV3-JE62-VBR-002 /
2.1.02.05a.i-U3-EQRR-Testing &
Analysis SV3-JE62-VBR-001 PCD006 Type SV3-JE62-VBR-002 /
2.1.02.05a.i-U3-EQRR-Testing &
SV3-JE62-VBR-001 PCD006 Analysis Type SV3-JE62-VBR-002 /
2.1.02.05a.i-U3-EQRR-Testing &
Analysis SV3-JE62-VBR-001 PCD006
U.S. Nuclear Regulatory Commission ND-21-1029 Enclosure Page 18 of 18 Notes:
+ Excerpt from COL Appendix C Table 2.1.2-1
- 1. See Table 30.5-1 of UFSAR
- 2. E = Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)
M = Mechanical Equipment Program (valve)
S = Qualified for submergence or operation with spray
- = Harsh Environment
- 3. Dash (-) indicates not applicable