ND-18-0327, Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.05a.i (Index Number 19)
| ML18106A741 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 04/09/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.1.02.05a.i, ND-18-0327 | |
| Download: ML18106A741 (21) | |
Text
Southern Nuclear APR 0 9 2018 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@souttiernco.com ND-18-0327 10CFR 52.99(c)(3)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Resubmittal of Notice of Uncompleted ITAAC225-davs Prior to Initial Fuel Load Item 2.1.02.05a.i [Index Number 191 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 27, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.05a.i
[Index Number 19] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describesthe plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC thathave not been completed 225-days prior to initial fuel load.
Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.1.02.05a.i [Index Number 19] ND-18-0041
[ML18037B023] dated January 25, 2018. This resubmittal supersedes ND-18-0041 in its entirety.
This notification is informed bythe guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, oranalyses have not been performed orhave been only partially completed.
All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plantoperation, as required by 10 CFR 52.103(g).
This letter contains no new NRC regulatory commitments.
If there are any questions, please contact Tom Petrak at 706-848-1575.
Respectfully submitted.
Michael J. Yox Regulatory Affairs Director Vogtle 3 &4
U.S. Nuclear Regulatory Commission ND-18-0327 Page 2 of 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit4 Completion Plan for Uncompleted ITAAC 2.1.02.05a.i [Index Number 19]
MJY/LBP/amw
U.S. Nuclear Regulatory Commission ND-18-0327 Page 3 of 4 To:
Southern Nuclear Operating Companv/ Georgia Power Company M
M M
M M
M M
M M
M D. A. Bost (w/o enclosures)
M. D. Rauckhorst (w/o enclosures)
M. D. Meier
. D. H. Jones (w/o enclosures)
D. L. McKinney M. J. Vox D. L. Fulton J. B. Klecha G. Chick F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Reaulatorv Commission Mr.W. Jones (w/o enclosures)
Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oalethorpe Power Corporation Mr. R. B. Brinkman
U.S. Nuclear Regulatory Commission ND-18-0327 Page 4 of 4 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Mr. M. M. CorlettI Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.
Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 1 of17 Southern Nuclear Operating Company ND-18-0327 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Completion Plan for Uncompleted ITAAC 2.1.02.05a.i [Index Number 19]
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 2 of 17 ITAAC Statement Desion Commitment 5.a) Theseismic Category Iequipment identified in Table 2.1.2-1 can withstand seismic design basis loads without loss of safety function.
7.a) The Class 1E equipmentidentified inTable 2.1.2-1 as beingqualified fora harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without lossofsafetyfunction for the time required to perform the safety function.
Inspections. Tests. Analvses i) Inspection will be performed to verify thatthe seismicCategoryIequipment 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 analysesofseismic Category I equipment will be performed.
ill) Inspection will be performed for the existence of a report verifying thatthe as-built equipment including anchorageisseismically bounded bythe tested or analyzed conditions.
i) Type tests, analyses, ora combination of type testsandanalyses will be performed on Class 1E equipment located in a harsh environment.
ii) Inspection will be performed of theas-built Class 1E equipment and theassociated wiring, cables, and terminations located in a harsh environment.
Acceptance Criteria i) The seismic Category Iequipment identified in Table 2.1.2-1 is located on the Nuclear Island.
ii) Areport exists and concludes that theseismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function.
iii) Areport exists and concludes that the as-built equipment including anchorage isseismically bounded bythe tested or analyzed conditions.
i) Areport exists and concludes that the Class 1E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment canwithstand theenvironmental conditions that would exist before, during, andfollowing a design basis accident without loss of safety function for thetime required to performthe safety function.
ii) Areport exists and concludes that theas-built Class 1E equipment andtheassociated wiring, cables, and terminations identified in Table 2.1.2-1 as being qualified for a harsh environment are bounded bytype tests, analyses,ora combination oftype tests and analyses.
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 3 of 17 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performedand documented to ensure the Reactor Coolant System (RCS) components identified as seismic Category Ior Class 1E inthe Combined License (COL) Appendix C, Table 2.1.2-1 (the Table) are designed and constructed in accordance with applicable requirements.
i^ The seismic Cateoorv I eouioment identified in Table 2.1.2-1 is located on the Nuclear Island To assure that seismic Category Icomponents can withstand seismic design basis loads without lossof safetyfunction, all the components in the Table are designed to be located on the seismic Category INuclear Island. In accordance with Equipment Qualification (EQ)
Walkdown ITAAC Guideline (Reference 1),an inspection is conducted ofthe RCSto confirm the satisfactory installation ofthe seismically qualified components. The inspection includes verification ofequipment make/model/serial number and verification ofequipment location (Building, Elevation, Room). The EQ As-Built Reconciliation Reports (EQRR) (Reference 2) identified inAttachment A document the results of the inspection and conclude that the seismic CategoryIcomponentsare located on the Nuclear Island.
W) A report exists and concludes that the seismic Cateoorv Ieouioment can withstand seismic desion basis loads without loss of safetv function.
Seismic Category Icomponents in theTable require type tests and/or analyses todemonstrate structural integrity and operability. Structural integrity of theseismic Category Ivalves, as well as other passive seismic Category Imechanical equipment, isdemonstrated by analysis in accordancewith American Society of Mechanical Engineers (ASME) CodeSection III (Reference 3). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1 -2007 (Reference 4).
Safety-related (Class 1E) electrical equipment in the Table isseismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). 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 API 000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6). The EQ Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation andconclude that the seismic Category Iequipment can withstand seismic design basis loads without loss of safety function.
iiil Areportexists and concludesthat the as-built equipmentincluding anchorage is seismicallv bounded bv the tested or analvzed conditions.
An inspection (Reference 1) isconducted to confirm the satisfactory installation of the seismically qualified components in theTable. The inspection verifies theequipment 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-18-0327 Enclosure Page 4 of 17 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. 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 7) identifythe equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plantinstallation does not degrade the established qualification.
Interface requirements are defined based on the test configuration and other design requirements.
Attachment A identifies the EQRR (Reference 2) completed to verifythat the as-built seismic Category Iequipment listed inthe Table, including anchorage, are seismicallybounded by the tested or analyzed conditions, IEEEStandard 344-1987 (Reference 5) and NRG Regulatory Guide (RG) 1.100 (Reference 8).
\\) A reoort exists and concludes that the Class 1E eouioment identified in Table 2.1.2-1 as beina qualified for a harsh environment can withstand the environmental conditions that would exist before, durino. and followino a desion basis accident without loss of safetv function for the time required to perform the safetv function.
The harsh environmentClass 1E components inthe Table are qualified bytype testing and/or analyses. Class 1Eelectrical component type testing is performed in accordance with IEEE Standard 323-1974 (Reference9) and RG 1.89 (Reference 10)to meet the requirements of 10 CFR 50.49. Typetesting ofsafety-related equipment meets the requirements of10CFR Part50,Appendix A, General Design Criterion 4. Attachment Aidentifies the EQ program and specific qualification method for each safety-related mechanical orClass 1Eelectrical component located in a harshenvironment. Additional information about the methods usedto qualify API000 safety-related equipment isprovided in the UFSAR Appendix 3D (Reference 6).
EQ Reports (Reference 7) identified in Attachment Acontain 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 forthe time required to perform the safety function.
iil A reoort exists and concludes that the as-built Class 1E equipment and the associated wirino. cables, and terminations identified in Table 2.1.2-1 as beino qualified for a harsh environment are bounded bv tvoe tests, analvses. or a combination of tvpe tests and analvses An inspection (Reference 1)isconducted of the RCS to confirm the satisfactory installation of the Class 1Ecomponents in the Table. The inspection verifies the equipmentlocation, make/model/serial number, as-designed equipmentmounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the component is mounted are bounded bythe tested and/oranalyzed conditions. It also documents the installedconfiguration with photographs or sketches/drawings of equipment mounting andconnections. The EQRR (Reference 2) identified in Attachment Adocument this inspection and conclude thatthe as-built harshenvironment Class 1Eequipment and the associatedwiring, cables, andterminations are bounded bythe qualified configuration and IEEE Standard 323-1974 (Reference 9).
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 5 of 17 Together,these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met:
The seismic Category Iequipment identified inTable 2.1.2-1 is located on the Nuclear Island; Areport existsand concludesthat the seismicCategoryIequipment can withstand seismic design basis loads withoutloss of safety function; Areport existsand concludesthat the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions; Areport existsand concludes thatthe Class 1Eequipment identified in Table2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would existbefore, during, and following a designbasis accident without loss ofsafety function forthe time required to perform the safety function; and Areport exists andconcludes that theas-built Class 1Eequipment andtheassociated wiring, cables, andterminations identified in Table 2.1.2-1 as being qualified for a harsh environment are bounded bytypetests, analyses, ora combination oftypetests and analyses.
References 2 and 7 are available for NRC inspection as partofthe Unit 3 and Unit 4 ITAAC 2.1.02.05a.i Completion Packages(References 11 and 12,respectively).
List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining tothe subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 20, 21, 24, and 25, found thefollowing Notices of Nonconformance (NGN) associated with this ITAAC;
- 1) 99901441/2014-201-03 (open)
- 2) 99900728/1-2017-201-01 (open)
- 3) 99901431/2013-201-01 (closed)
Before submission ofthe \\TAAC Closure Notification (ICN), corrective actions will be completed for relevant IT/\\AC findings.
References (available for NRC inspection) 1.
ND-xx-xx-001, "EG Walkdown ITAAC Guideline"
- 2. EG As-Built Reconciliation Reports (EQRR) as identified in Attachment Afor Units 3 and4
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 6 of 17
Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda 4.
ASME QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007 5.
IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"
- 6. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment"
- 7. Equipment Qualification (EQ) Reports as identified in Attachment A
- 8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"
- 9. IEEE Standard 323-1974, "IEEE Standard for Qualifying Class 1E Equipmentfor Nuclear Power Generating Stations"
- 10. Regulatory Guide 1.89, Rev 1,"Environmental Qualification of Certain Electric Equipment Important to Safetyfor Nuclear Power Plants" 11.2.1.02.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.1.02.05a.i [Index Number 19]"
12.2.1.02.05a.i-U4-CP-Rev X, "Completion Packagefor Unit 4 ITAAC 2.1.02.05a.i [Index Number 19]"
- 13. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 7 of 17 Attachment A System; Reactor Coolant System (RCS)
Equipment Name^
Tag No/
Seismic Cat. \\*
Ciass 1E/Quai.
For Harsh Envir.^3 Envir.
Zone^
Envir Qua!
Program^
Type of Quai.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)*
Steam Generator 1 RCS-MB-01 Yes
-/-
N/A N/A Analysis APP-MB01-Z0R-100 2.1.02.05a.i-U3-EQRR-PCDXXX Steam Generator 2 RCS-MB-02 Yes
-/-
N/A N/A Analysis APP-MB01-Z0R-100 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 1A RCS-MP-01A Yes No/No N/A N/A Analysis APP-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCDXXX RCP IB RCS-MP-01B Yes No/No N/A N/A Analysis APP-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2A RCS-MP-02A Yes No/No N/A N/A Anaiysis APP-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 28 RCS-MP-02B Yes No/No N/A N/A Analysis APP-MP01-S2R-011 2.1.02.05a.i-U3-EQRR-PCDXXX Pressurizer RCS-MV-02 Yes No/No (heaters)
N/A N/A Analysis APP-MV20-Z0R-101 2.1.02.05a.i-U3-EQRR-PCDXXX Automatic Depressurization System (ADS) Sparger A PXS-MW-01A Yes
-/-
N/A N/A Analysis APP-MW01-Z0C-001 2.1.02.05a.i-U3-EQRR-PCDXXX ADS Sparger B PXS-MW-01B Yes
-/-
N/A N/A Analysis APP-MW01-Z0C-001 2.1.02.05a.i-U3-EQRR-PCDXXX Pressurizer Safety Valve RCS-PL-V005A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV62-VBR-002 /
APP-PV62-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX Pressurizer Safety Valve RCS-PL-V005B Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV62-VBR-002 /
APP-PV62-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 8 of 17 Equipment Name^
Tag No.^
Seismic Cat. r Class 1E/ Qual.
For Harsh Envlr.^
Envir.
Zone^
Envir Quai Program^
Type of Quai.
EG Reports (Reference 7)
As-Buiit EQRR (Reference 2)^
First-stage ADS Motor-operated Valve (MOV)
RCS-PL-V001A Yes YesA^es 1
M E*S Type Testing &
Analysis APP-PV01-VBR-014/
APP-PV01-VBR-013 2.1.02.05a.i-U3-EQRR-PCDXXX First-stage ADS MOV RCS-PL-V001B Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV01-VBR-014/
APP-PV01-VBR-013 2.1.02.05a.i-U3-EQRR-PCDXXX Second-stage ADS MOV RCS-PL-V002A Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV01-VBR-014/
APP-PV01-VBR-013 2.1.02.05a.i-U3-EQRR-PCDXXX Second-stage ADS MOV RCS-PL-V002B Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV01-VBR-014/
APP-PV01-VBR-013 2.1.02.05a.i-U3-EQRR-PCDXXX Third-stage ADS MOV RCS-PL-V003A Yes YesA'es 1
ME*S Type Testing &
Analysis APP-PV01-VBR-014/
APP-PV01-VBR-013 2.1.02.05a.i-U3-EQRR-PCDXXX Third-stage ADS MOV RCS-PL-V003B Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV01-VBR-014/
APP-PV01-VBR-013 2.1.02.05a.i-U3-EQRR-PCDXXX Fourth-stage ADS Squib Valve RCS-PL-V004A Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV70-VBR-005 /
APP-PV70-VBR-004 2.1.02.05a.i-U3-EQRR-PCDXXX Fourth-stage ADS Squib Valve RCS-PL-V004B Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV70-VBR-005 /
APP-PV70-VBR-004 2.1.02.05a.i-U3-EQRR-PCDXXX Fourth-stage ADS Squib Valve RCS-PL-V004C Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV70-VBR-005 /
APP-PV70-VBR-004 2.1.02.05a.i-U3-EQRR-PCDXXX Fourth-stage ADS Squib Valve RCS-PL-V004D Yes YesA'es 1
ME*S Type Testing &
Analysis APP-PV70-VBR-005 /
APP-PV70-VBR-004 2.1.02.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 9 of 17 Equipment Name^
Tag No.*
Seismic Cat. 1*
Class IE/Qua!.
For Harsh Envir.*3 Envir.
Zone^
Envir Qual Program^
Type of Quai.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)^
ADS Discharge Header A Vacuum Relief Valve RCS-PL-V010A Yes Yes/Yes 1
M*S Type Testing &
Analysis APP-PV18-VBR-002/
APP-PV18-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX ADS Discharge Header B Vacuum Relief Valve RCS-PL-V010B Yes Yes/Yes 1
M*S Type Testing &
Analysis APP-PV18-VBR-002/
APP-PV18-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX First-stage ADS Isolation MOV RCS-PL-V011A Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX First-stage ADS Isolation MOV RCS-PL-V011B Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX Second-stage ADS Isolation MOV RCS-PL-V012A Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX Second-stage ADS Isolation MOV RCS-PL-V012B Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX Third-stage ADS Isolation MOV RCS-PL-V013A Yes Yes/Yes 1
M E*S Type Testing &
Anaiysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX Third-stage ADS Isoiation MOV RCS-PL-V013B Yes Yes/Yes 1
ME*S Type Testing &
Anaiysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX Fourth-stage ADS MOV RCS-PL-V014A Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX Fourth-stage ADS MOV RCS-PL-V014B Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 10 of 17 Equipment Name^
Tag No/
Seismic Cat. \\*
Class 1E/ Quai.
For Harsh Envir.+ 3 Envir.
Zone^
Envir Quai Program^
Type of Quai.
EQ Reports (Reference 7)
As-Buiit EQRR (Reference 2)^
Fourth-stage ADS MOV RGS-PL-V014G Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PGDXXX Fourth-stage ADS MOV RGS-PL-V014D Yes Yes/Yes 1
M E*S Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.1.02.05a.i-U3-EQRR-PGDXXX Reactor Vessel Head Vent Valve RGS-PL-V150A Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV13-VBR-XXX/
APP-PV13-VBR-YYY 2.1.02.05a.i-U3-EQRR-PGDXXX Reactor Vessel Head Vent Valve RGS-PL-V150B Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV13-VBR-XXX/
APP-PV13-VBR-YYY 2.1.02.05a.i-U3-EQRR-PGDXXX Reactor Vessel Head Vent Valve RGS-PL-V150G Yes YesA'es 1
ME*S Type Testing &
Analysis APP-PV13-VBR-XXX/
APP-PV13-VBR-YYY 2.1.02.05a.i-U3-EQRR-PGDXXX Reactor Vessel Head Vent Valve RGS-PL-V150D Yes YesA'es 1
M E*S Type Testing &
Analysis APP-PV13-VBR-XXX/
APP-PV13-VBR-YYY 2.1.02.05a.i-U3-EQRR-PGDXXX RGS Hot Leg 1 Flow Sensor RGS-101A Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGS Hot Leg 1 Flow Sensor RGS-101B Yes YesA'es 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGS Hot Leg 1 Flow Sensor RGS-101G Yes YesA'es 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGS Hot Leg 1 Flow Sensor RGS-101D Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 11 of 17 Equipment Name^
Tag No.^
Seismic Cat. r Class IE/Qua!.
For Harsh Envlr.+ 3 Envlr.
Zone^
Envlr Qual Program^
Type of Qual.
EG Reports (Reference 7)
As-Bullt EQRR (Reference 2)^
RGB Hot Leg 2 Flow Sensor RGS-102A Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Flow Sensor RGS-102B Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Flow Sensor RGS-102G Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Flow Sensor RGS-102D Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Gold Leg 1A Narrow Range Temperature Sensor RGS-121A Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Gold Leg 1B Narrow Range Temperature Sensor RGS-121B Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Gold Leg 1B Narrow Range Temperature Sensor RGS-121G Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Gold Leg 1A Narrow Range Temperature Sensor RGS-121D Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Gold Leg 2B Narrow Range Temperature Sensor RGS-122A Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Gold Leg 2A Narrow Range Temperature Sensor f
RGS-122B Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 12 of 17 Equipment Name^
Tag No/
Seismic Cat. r Class 1E/ Qual.
For Harsh Envir.+
Envir.
Zone^
Envir Quai Program^
Type of Qual.
EG Reports (Reference 7)
As-Built EQRR (Reference 2)^
RGB Cold Leg 2A Narrow Range Temperature Sensor RCS-122C Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Cold Leg 2B Narrow Range Temperature Sensor RCS-122D Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Cold Leg 1A Dual Range Temperature Sensor RCS-125A Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Cold Leg 2A Dual Range Temperature Sensor RCS-125B Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Cold Leg 1B Dual Range Temperature Sensor RCS-125C Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Cold Leg 2B Dual Range Temperature Sensor RCS-125D Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-131A Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-131B Yes YesA'es 1
E* S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Hot Leg 1 Narrow Range Temperature Sensor RCS-131C Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCS Hot Leg 2 Narrow Range Temperature Sensor RCS-131D Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 13 of 17 Equipment Name"^
Tag No/
Seismic Cat. r Class 1E/ Qual.
For Harsh Envir.+ 3 Envir.
Zone^
Envir Qual Program^
Type of Qual.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)^
RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-132A Yes Yes/Yes 1
E*S Type Testing &
Anaiysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-132B Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-132G Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-132D Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-133A Yes Yes/Yes 1
E* S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-133B Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 1 Narrow Range Temperature Sensor RGS-133G Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Narrow Range Temperature Sensor RGS-133D Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 1 Wide Range Temperature Sensor RGS-135A Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Wide Range Temperature Sensor RGS-135B Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enciosure Page 14 of 17 Equipment Name^
Tag No.^
Seismic Cat. \\*
Class 1E/Qual.
For Harsh Envir.+
Envir.
Zone^
Envir Qual Program^
Type of Qual.
EG Reports (Reference 7)
As-Built EORR (Reference 2)^
RGB Wide Range Pressure Sensor RGS-140A Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Wide Range Pressure Sensor RGS-140B Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Wide Range Pressure Sensor RGS-140G Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Wide Range Pressure Sensor RGS-140D Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 1 Level Sensor RGS-160A Yes Yes/Yes 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX RGB Hot Leg 2 Level Sensor RGS-160B Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX Passive Residual Heat Removal (PRHR) Return Line Temperature Sensor RGS-161 Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 APP-JE53-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX Pressurizer Pressure Sensor RGS-191A Yes YesA'es 1
E* S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX Pressurizer Pressure Sensor RGS-191B Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX Pressurizer Pressure Sensor RGS-191G Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.i-U3-EQRR-PGDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 15 of 17 Equipment Name"^
Tag No.+
Seismic Cat. i^
Oiass 1E/ Quai.
For Harsh Envir.+ 3 Envir.
Zone^
Envir Qual Program^
Type of Quai.
EG Reports (Reference 7)
As-Buiit EORR (Reference 2)^
Pressurizer Pressure Sensor RCS-191D Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX Pressurizer Level Reference Leg Temperature Sensor RCS-193A Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX Pressurizer Level Reference Leg Temperature Sensor RCS-193B Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX Pressurizer Level Reference Leg Temperature Sensor RCS-193C Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE53-VBR-002 /
APP-JE53-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX 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.l-U3-EQRR-PCDXXX Pressurizer Level Sensor RCS-195A Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX Pressurizer Level Sensor RCS-195B Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX Pressurizer Level Sensor RCS-195C Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX Pressurizer Level Sensor RCS-195D Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX RCP 1A Bearing Water Temperature Sensor RCS-211A Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX RCP 1A Bearing Water Temperature Sensor RCS-211B Yes YesA^es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.l-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 16 of 17 Equipment Name^
Tag No/
Seismic Cat. i^
Ciass lE/Quai.
For Harsh Envir/3 Envir.
Zone^
Envir Qual Program^
Type of Qual.
EQ Reports (Reference 7)
As-Buiit EQRR (Reference 2)^
RCP 1A Bearing Water Temperature Sensor RCS-211C Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 1A Bearing Water Temperature Sensor RCS-211D Yes Yes/Yes 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP IB Bearing Water Temperature Sensor RCS-212A Yes Yes/Yes 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP IB Bearing Water Temperature Sensor RCS-212B Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 1B Bearing Water Temperature Sensor RCS-212C Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 1B Bearing Water Temperature Sensor RCS-212D Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2A Bearing Water Temperature Sensor RCS-213A Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2A Bearing Water Temperature Sensor RCS-213B Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2A Bearing Water Temperature Sensor RCS-213C Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2A Bearing Water Temperature Sensor RCS-213D Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2B Bearing Water Temperature Sensor RCS-214A Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2B Bearing Water Temperature Sensor RCS-214B Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2B Bearing Water Temperature Sensor RCS-214C Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2B Bearing Water Temperature Sensor RCS-214D Yes YesA'es 1
E*
Type Testing APP-MP01-VBR-002/
APP-MP01-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 1A Pump Speed Sensor RCS-281 Yes YesA'es 1
E*
Type Testing &
Analysis APP-JE62-VBR-002 /
APP-JE62-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0327 Enclosure Page 17 of 17 Equipment Name^
Tag No.+
Seismic Cat. i^
Class lE/Quai.
For Harsh Envir.*
Envir.
Zone^
Envir Qual Program Type of Quai.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)^
RCP 1B Pump Speed Sensor RCS-282 Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE62-VBR-002 /
APP-JE62-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2A Pump Speed Sensor RCS-283 Yes Yes/Yes 1
E*
Type Testing &
Analysis APP-JE62-VBR-002 /
APP-JE62-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX RCP 2B Pump Speed Sensor RCS-284 Yes YesA'es 1
E*
Type Testing &
Analysis APP-JE62-VBR-002 /
APP-JE62-VBR-001 2.1.02.05a.i-U3-EQRR-PCDXXX 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
- 4. The Unit 4 As-Built EQRR are numbered "2.1.02.05a.i-U4-EQRR-PCDXXX"