ND-18-0185, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.05a.i (Index Number 165)
| ML18054A413 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/22/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0185 | |
| Download: ML18054A413 (20) | |
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Southern Nuclear F£B 2 2 2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox @southernco.com ND-18-0185 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.05a.i [Index Number 165]
Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.05a.i
[Index Number165] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notificationsfor ITAAC that have not been completed 225-days prior to initial fuel load.
This notification is informed by the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.
All ITAAC will be fully completedand all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).
This letter contains no new NRC regulatory commitments.
If there are any questions, please contact Tom Petrak at 706-848-1575.
Respectfully submitted.
Michael J. Yox Regulatory Affairs Director Vogtle 3 &4
U.S. Nuclear Regulatory Commission ND-18-0185 Page 2 of 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.05a.i [Index Number 165]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0185 Page 3 of 4 To:
Southern Nuclear Operating Company/ Georgia Power Company 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. McKlnney M. J. Vox D. L. Fulton J. D. Williams 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 Reoulatorv 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 Oolethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0185 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, inc.
Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 1 of 16 Southern Nuclear Operating Company ND-18-0185 Enclosure VogtleElectricGenerating Plant (VEGP) Unit 3 and Unit 4 Completion Pianfor Uncompleted ITAAC 2.2.03.05a.i [Index Number 165]
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 2 of 16 ITAAC Statement Desian Commitment:
5.a) The seismic Category I equipment identified in Table 2.2.3-1 can withstand seismic design basis loads without loss of safety function.
7.a) The Class 1E equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
Inspections. Tests. Analvses:
i) Inspection will be performed to verifythat the seismic Category I equipment and valves identified in Table 2.2.3-1 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 performedfor the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
i) Typetests, analyses, or a combination oftypetests and analyses will be performed on Class 1E equipment located in a harsh environment.
ii) Inspection will be performedof the as-built Class 1E equipment and the associated wiring, cables, and terminations located in a harsh environment.
Acceptance Criteria:
i) The seismicCategory Iequipment identified in Table2.2.3-1 is locatedon the Nuclear Island.
ii) Areport exists and concludesthat the seismicCategoryIequipment can withstand seismic design basis dynamic loads without loss ofsafetyfunction. Forthe PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dynamic loads and also post-accidentoperating loads, including head loss and debris weights.
iii) Areport exists and concludesthat the as-built equipment including anchorage is seismically bounded bythe tested or analyzedconditions. Forthe PXS containment recirculation and IRWST screens, a reportexists and concludes that the as-builtscreens including their anchorage are bounded bythe seismicloadsand also post-accident operating loads, including head loss and debris weights.
i) Areport exists and concludesthat the Class 1E equipment identified inTable2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accidentwithout loss ofsafetyfunction forthe time required to perform the safety function.
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 3 of 16 ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.
ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Passive Core Cooling System (PXS) equipment identified as seismic Category Ior Class IE in the Combined License (COL) Appendix C, Table 2.2.3-1 (the Table) is designed and constructed in accordance with applicable requirements.
n The seismic Cateoorv I eauioment identified in Table 2.2.3-1 is located on the Nuclear Island.
To assure that seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function, all the equipment in the Table is designed to be located on the seismic Category INuclear Island. In accordancewith Equipment Qualification (EG) Walkdown ITAAC Guideline(Reference 1), an inspection is conducted ofthe PXSto confirm the satisfactory installation of the seismicallyqualified equipment. The inspection includesverification of equipmentmake/model/serial numberand verification ofequipment location (Building, Elevation, Room). The EGAs-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment Adocument the results of the inspection and conclude that the seismic Category I equipment is located on the Nuclear Island.
W) A reoort exists and concludes that the seismic Cateoorv I equipment can withstand seismic desion basis dvnamic loads without loss of safetv function. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dvnamic loads and also oost-accident ooeratino loads, including head loss and debris weights.
SeismicCategory Iequipment in the Table requirestypetests and/oranalyses to demonstrate structural integrity and operability. Structural integrity ofthe seismic Category Ivalves, as well as otherpassiveseismic Category Imechanical equipment, isdemonstrated byanalysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality ofthesubsetof active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4). Structural integrity ofthe in-containment refueling waterstorage tank (IRWST) is demonstrated byanalysis in accordance with American Concrete Institute (ACI) Standard349-01 (Reference 5) and American Institute of Steel Construction (AISC) Specification N690 (Reference6). Structural integrity ofthe pH adjustment baskets isdemonstrated byanalysis in accordance with AISC Specification N690 (Reference 6).
Safety-related (Class1E) electrical equipment in the Table isseismically qualified bytype testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 7). This equipment includes safety-related (Class 1E) field sensors and thesafety-related active valve accessoriessuch as electric actuators, position switches, pilot solenoid valves and electrical connector assemblies. The specific qualification method (i.e., type testing, analysis, orcombination) used for eachpiece of equipment in theTable isidentified in Attachment A. Additional information about the methods used to qualify API 000safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 8). The EG Reports (Reference 9) identified
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 4 of 16 in Attachment A contain applicable test reports and associated documentation and conclude that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function. For the PXS containment recirculation and IRWST screens, the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights.
iii) A report exists and concludes that the as-built equipment includino anchorage is seismicallv bounded bv the tested or analyzed conditions. For the PXS containment recirculation and IRWST screens, a reoort exists and concludes that the as-built screens includino their anchorage are bounded bv the seismic loads and also post-accident ooeratino loads, including head loss and debris weights.
An inspection (Reference 1) is conducted to confirm the satisfactory installation of the seismically qualified equipment in the Table. The inspection verifies the equipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other interfaces. The documentation of installed configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.
As part ofthe seismic qualification program, consideration is given to the definition ofthe clearances needed around the equipment mounted inthe plant to permit the equipment to move during a postulated seismicevent without causing impact betweenadjacent pieces ofsafety-related equipment. This is done as part ofseismictesting by measuringthe maximum dynamic relative displacementofthe top and bottom ofthe equipment. EQ Reports (Reference 9) identify the equipmentmounting employed forqualification and establish interfacerequirements forassuringthat subsequent in-plant installation does notdegrade the established qualification.
Interface requirements are defined based on the test configuration and other design requirements.
AttachmentA identifies the EQRR(Reference 2) completed to verify that the as-builtseismic Category Iequipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzedconditions, IEEE Standard 344-1987 (Reference7), and NRG Regulatory Guide (RG) 1.100(Reference 10). Forthe PXS containment recirculation and IRWST screens, the as-builtscreens including their anchorage are bounded by the seismic loads and also post-accidentoperating loads, including head loss and debris weights.
n A report exists and concludes that the Class 1E equipment identified in Table 2.2.3-1 as being 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 environment Class 1E equipment inthe Table is qualified by type testing and/or analyses. Class 1Eelectrical equipment type testing is performed in accordance with IEEE Standard 323-1974 (Reference11)and RG 1.89 (Reference 12) to meet the requirements of 10 CFR50.49. Typetestingofsafety-related equipment meets the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment Aidentifies the EQ program and specific qualification method for each piece ofsafety-related mechanical orClass 1Eelectrical equipment located in a harsh environment. Additional information about the methods usedto qualify API000 safety-related equipment isprovided in the UFSAR Appendix 3D (Reference 8).
EQ Reports (Reference9) identified in Attachment Acontain applicable test reportsand
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 5 of 16 associated documentation and conclude that the equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.3-1 as being Qualified for a harsh environment are bounded bv tvoe tests, analvses. or a combination of tvoe tests and analvses.
An inspection (Reference 1) is conducted ofthe PXSto confirm the satisfactory installation of the Class 1E equipment inthe Table. The inspection verifies the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the equipmentis mountedare bounded bythe tested and/or analyzed conditions. It also documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 2) identified in Attachment Adocument this inspection, and conclude that the as-built harsh environment Class 1E equipment and the associated wiring, cables, and terminations are bounded bythe qualified configuration and IEEE Standard 323-1974 (Reference 11).
Together, these reports (References 2 and 9) provide evidence thatthe ITAAC Acceptance Criteria requirements are met:
TheseismicCategory Iequipment identified in Table 2.2.3-1 is located on the Nuclear Island; Areport exists andconcludes thattheseismic Category Iequipment canwithstand seismic design basisdynamic loads without lossofsafety function. For the PXS containment recirculation and IRWSTscreens, a report exists and concludes that the screens can withstand seismicdynamic loads and also post-accident operating loads, including head loss and debris weights; Areport exists andconcludes that theas-built equipment including anchorage is seismically bounded by thetestedoranalyzed conditions. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the as-builtscreens including their anchorage are bounded by the seismic loads andalso post-accident operating loads, including head loss and debris weights; Areport exists andconcludes that theClass 1E equipment identified in Table 2.2.3-1 as being qualified for a harsh environment canwithstand theenvironmental conditions that would exist before, during, andfollowing a design basis accident without lossof safety function for the time required to performthe safety function; and Areport exists and concludes that the as-built Class 1E equipment and theassociated wiring, cables, and terminations identified in Table 2.2.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, ora combination oftype tests and analyses.
References2 and 9 are available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.2.03.05a.i Completion Packages (References 13 and 14, respectively).
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 6 of 16 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.
This review, which included now consolidated ITAAC Indexes 166,167,170, and 171, found the following relevant ITAAC findings associated with this ITAAC:
- 1) Notice of Nonconformance (NGN) 99901441/2014-201 -03 (Open)
- 2) NON 99901431/2013-201-01 (Closed)
- 3) NON 99901377/2012-201 -02 (Closed)
- 4) NON 99901377/2012-201-03 (Closed)
- 5) NON 99900404/2012-201-01 (Closed)
- 6) NON 99900404/2012-201-02 (Closed) 7)
NON 99900404/2012-201-03 (Closed)
Before submission of the ITAAC Closure Notification (ICN), corrective actions will be completed for relevant findings identified priorto ICN submission.
References (available for NRG inspection) 1.
ND-xx-xx-001, "EQ Walkdown IT/\\AC Guideline"
- 2. EQ As-Built Reconciliation Reports (EQRR) as identified inAttachmentAfor Units 3 and 4
Code,Section III, "RulesforConstruction of Nuclear Power PlantComponents," 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. American Concrete Institute (ACI) Standard 349-01, "CodeRequirements for Nuclear Safety Related Concrete Structures," 2001.
- 6. American National Standards Institute(ANSI) / American Instituteof Steel Construction (AISC) N690-1994, "Specification for the Design, Fabrication and Erection of Safety-Related Steel Structures for Nuclear Facilities"
- 7. IEEEStandard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipmentfor Nuclear Power Generating Stations"
- 8. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment"
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 7 of 16 9.
Equipment Qualification (EG) Reports as identified in Attachment A
- 10. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"
- 11. IEEE Standard 323-1974, "IEEEStandard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations"
- 12. Regulatory Guide 1.89, Rev 1, "Environmental Qualification ofCertain Electric Equipment Importantto Safety for Nuclear Power Plants" 13.2.2.03.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.2.03.05a.i [Index Number 165]"
14.2.2.03.05a.i-U4-CP-Rev X,"Completion Package for Unit 4 ITAAC 2.2.03.05a.i [Index Number 165]"
15.NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10CFR Part52"
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 8 of 16 Attachment A System; Passive Core Cooling System Equipment Name ^
Tag No.
- Seismic Cat. i^3 Class 1E/
Quai. Harsh Envir.
Envir.
Zone ^
Envir Qua!
Program ^
Type of Quai.
EQ Reports (Reference 9)
As-Built EORR (Reference 2)"
Passive Residual Heat Removal Heat Exchanger (PRHR HX)
PXS-ME-01 Yes
-/-
N/A N/A Analysis APP-ME02-Z0R-100 2.2.03.05a.i-U3-EQRR-PCDXXX Accumulator Tank A PXS-MT-01A Yes
-/-
N/A N/A Analysis APP-MT02-Z0R-101 2.2.03.05a.i-U3-EQRR-PCDXXX Accumulator Tank B PXS-MT-01B Yes
-/-
N/A N/A Analysis APP-MT02-Z0R-101 2.2.03.05a.i-U3-EQRR-PCDXXX Core Makeup Tank (CMT)
A PXS-MT-02A Yes N/A N/A Analysis APP-MT01-Z0R-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMTB PXS-MT-02B Yes
-/-
N/A N/A Analysis APP-MT01-Z0R-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST PXS-MT-03 Yes
-/-
N/A N/A Analysis APP-MT03-VFR-XXX 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Screen A PXS-MY-Y01A Yes
-/-
N/A N/A Analysis APP-MY03-VDR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Screen B PXS-MY-Y01B Yes
-/-
N/A N/A Analysis APP-MY03-VDR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Screen C PXS-MY-Y01C Yes
- / -
N/A N/A Analysis APP-MY03-VDR-001 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Recirculation Screen A PXS-MY-Y02A Yes N/A N/A Analysis APP-MY03-VDR-001 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Recirculation Screen B PXS-MY-Y02B Yes
-/-
N/A N/A Analysis APP-MY03-VDR-001 2.2.03.05a.i-U3-EQRR-PCDXXX pH Adjustment Basket 3A PXS-MY-Y03A Yes N/A N/A Analysis APP-MY07-Z0C-002 2.2.03.05a.i-U3-EQRR-PCDXXX pH Adjustment Basket 3B PXS-MY-Y03B Yes N/A N/A Analysis APP-MY07-Z0C-002 2.2.03.05a. i-U3-EQRR-PCDXXX pH Adjustment Basket 4A PXS-MY-Y04A Yes N/A N/A Analysis APP-MY07-Z0C-002 2.2.03.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 9 of 16 Attachment A System: Passive Core Cooling System Equipment Name ^
Tag No. ^
Seismic Cat. i+3 Giass 1E/
Quai. Harsh Envir.
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 9)
As-Buiit EQRR (Reference 2) ^
pH Adjustment Basket 48 PXS-MY-Y04B Yes N/A N/A Analysis APP-MY07-Z0C-002 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 1A PXS-MY-Y81 Yes
-/-
N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 1B PXS-MY-Y82 Yes N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 1C PXS-MY-Y83 Yes
-/-
N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 1D PXS-MY-Y84 Yes N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 2A PXS-MY-Y85 Yes N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 2B PXS-MY-Y86 Yes
-/-
N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 2C PXS-MY-Y87 Yes N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX Downspout Screen 2D PXS-MY-Y88 Yes
- / -
N/A N/A Analysis APP-MY02-Z0C-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A Yes YesA'es 1
M* ES Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B Yes YesA'es 1
M* ES Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Discharge Isolation Valve PXS-PL-V014A Yes Yes/Yes 1
M* ES Type Testing &
Analysis APP-PV14-VBR-002/
APP-PV14-VBR-001 2.2.03.05a. i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 10 of 16 Attachment A System: Passive Core Cooling System Equipment Name
- Tag No.
- Seismic Cat.
CiasslE/
Qual. Harsh Envir.
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EG Reports (Reference 9)
As-Buiit EQRR (Reference 2)"
CMT B Discharge Isolation Valve PXS-PL-V014B Yes Yes/Yes 1
M* ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Discharge Isolation Valve PXS-PL-V015A Yes YesA'es 1
M*ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Discharge Isolation Valve PXS-PL-V015B Yes YesA'es 1
M* ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Discharge Check Valve PXS-PL-V016A Yes
- / -
N/A N/A Analysis APP-PV03-VBR-004/
APP-PV03-VBR-003 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Discharge Check Valve PXS-PL-V016B Yes N/A N/A Analysis APP-PV03-VBR-004/
APP-PV03-VBR-003 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Discharge Check Valve PXS-PL-V017A Yes N/A N/A Analysis APP-PV03-VBR-004 /
APP-PV03-VBR-003 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Discharge Check Valve PXS-PL-V017B Yes N/A N/A Analysis APP-PV03-VBR-004 /
APP-PV03-VBR-003 2.2.03.05a.i-U3-EQRR-PCDXXX Accumulator A Pressure Relief Valve PXS-PL-V022A Yes N/A N/A Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX Accumulator B Pressure Relief Valve PXS-PL-V022B Yes
- / -
N/A N/A Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX Accumulator A Discharge Isolation Valve PXS-PL-V027A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.03.05a.i-U3-EQRR-PCDXXX Accumulator B Discharge Isolation Valve PXS-PL-V027B Yes N/A N/A Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.03.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 11 of 16 Attachment A System: Passive Core Cooling System Equipment Name ^
Tag No. ^
Seismic Class 1E/
Quai. Harsh Envir.*'
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 9)
As-Buiit EQRR (Reference 2)
- Accumulator A Discharge Check Valve PXS-PL-V028A Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014 /
APP-PV03-VBR-013 2.2.03.05a.l-U3-EQRR-PCDXXX Accumulator B Discharge Check Valve PXS-PL-V028B Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014 /
APP-PV03-VBR-013 2.2.03.05a.l-U3-EQRR-PCDXXX Accumulator A Discharge Check Valve PXS-PL-V029A Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014 /
APP-PV03-VBR-013 2.2.03.05a.l-U3-EQRR-PCDXXX Accumulator B Discharge Check Valve PXS-PL-V029B Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014 /
APP-PV03-VBR-013 2.2.03.05a.l-U3-EQRR-PCDXXX Nitrogen Supply Containment Isolation Valve PXS-PL-V042 Yes Yes/No N/A N/A Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.03.05a.l-U3-EQRR-PCDXXX Nitrogen Supply Containment Isolation Check Valve PXS-PL-V043 Yes
-/-
N/A N/A Analysis APP-PV02-VBR-016 /
APP-PV02-VBR-015 2.2.03.05a.l-U3-EQRR-PCDXXX PRHR HX Inlet Isolation Motor-operated Valve PXS-PL-V101 Yes YesA'es 1
M*ES Type Testing &
Analysis APP-PV01-VBR-012 /
APP-PV01-VBR-011 2.2.03.05a.l-U3-EQRR-PCDXXX PRHR HX Control Valve PXS-PL-V108A Yes YesA'es 1
M*ES Type Testing &
Analysis APP-PV20-VBR-002 /
APP-PV20-VBR-001 2.2.03.05a.l-U3-EQRR-PCDXXX PRHR HX Control Valve PXS-PL-V108B Yes Yes/Yes 1
M*ES Type Testing &
Analysis APP-PV20-VBR-002 /
APP-PV20-VBR-001 2.2.03.05a.l-U3-EQRR-PCDXXX Containment Reclrculatlon A Isolation Motor-operated Valve PXS-PL-V117A Yes YesA'es 1
M*ES Type Testing &
Analysis APP-PV01-VBR-012 /
APP-PV01-VBR-011 2.2.03.05a.l-U3-EQRR-PCDXXX Containment Reclrculatlon B Isolation Motor-operated Valve PXS-PL-V117B Yes YesA'es 1
M*ES Type Testing &
Analysis APP-PV01-VBR-012 /
APP-PV01-VBR-011 2.2.03.05a.l-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 12 of 16 Attachment A System: Passive Core Cooling System Equipment Name ^
Tag No.
- Seismic Cat. i+3 Ciass IE/
Quai. Harsh Envir.
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 9)
As-Buiit EQRR (Reference 2) ^
Containment Recirculation A Squib Valve PXS-PL-V118A Yes Yes/Yes 1
M* ES Type Testing &
Analysis APP-PV70-VBR-003 /
APP-PV70-VBR-002 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Recirculation B Squib Valve PXS-PL-V118B Yes Yes/Yes 1
M*ES Type Testing &
Analysis APP-PV70-VBR-003/
APP-PV70-VBR-002 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Recirculation A Check Valve PXS-PL-V119A Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014/
APP-PV03-VBR-013 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Recirculation B Check Valve PXS-PL-V119B Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014/
APP-PV03-VBR-013 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Recirculation A Squib Valve PXS-PL-V120A Yes Yes/Yes 1
M* ES Type Testing &
Analysis APP-PV70-VBR-003 /
APP-PV70-VBR-002 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Recirculation B Squib Valve PXS-PL-V120B Yes Yes/Yes 1
M*ES Type Testing &
Analysis APP-PV70-VBR-003/
APP-PV70-VBR-002 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Injection A Check Vaive PXS-PL-V122A Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014/
APP-PV03-VBR-013 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Injection B Check Valve PXS-PL-V122B Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014/
APP-PV03-VBR-013 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Injection A Squib Valve PXS-PL-V123A Yes Yes/Yes 1
M*ES Type Testing &
Analysis APP-PV70-VBR-003 /
APP-PV70-VBR-002 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Injection B Squib Valve PXS-PL-V123B Yes Yes/Yes 1
M*ES Type Testing &
Analysis APP-PV70-VBR-003/
APP-PV70-VBR-002 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Injection A Check Valve PXS-PL-V124A Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014/
APP-PV03-VBR-013 2.2.03.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 13 of 16 Attachment A System: Passive Core Cooling System Equipment Name ^
Tag No.
Seismic Cat. i Class 1E/
Qual. Harsh Envir.
Envir.
Zone ^
Envir Qual Program ^
Type of Qual.
EQ Reports (Reference 9)
As-Built EQRR (Reference 2) ^
IRWST Injection B Check Valve PXS-PL-V124B Yes
-/-
N/A N/A Analysis APP-PV03-VBR-014/
APP-PV03-VBR-013 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Injection A Squib Valve PXS-PL-V125A Yes YesA'es 1
M*ES Type Testing &
Analysis APP-PV70-VBR-003 /
APP-PV70-VBR-002 2.2.03.05a. i-U3-EQRR-PCDXXX IRWST Injection B Squib Valve PXS-PL-V125B Yes YesA'es 1
M*ES Type Testing &
Analysis APP-PV70-VBR-003 /
APP-PV70-VBR-002 2.2.03.05a. i-U3-EQRR-PCDXXX IRWST Gutter Isolation Valve PXS-PL-V130A Yes Yes/Yes 1
M* ES Type Testing &
Analysis APP-PV10-VBR-003/
APP-PV10-VBR-004 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Gutter Isolation Valve PXS-PL-V130B Yes YesA'es 1
M* ES Type Testing &
Analysis APP-PV10-VBR-003/
APP-PV10-VBR-004 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-011A Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-011B Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE61-VBR-002 /
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-011C Yes YesA^es 1
E* S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-011D Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Level Sensor PXS-012A Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 14 of 16 Attachment A System: Passive Core Cooiing System Equipment Name ^
Tag No. ^
Seismic Cat. i^3 Giass 1E/
Quai. Harsh Envir.^
Envir.
Zone ^
Envir Quai Program Type of Quai.
EG Reports (Reference 9)
As-Buiit EORR (Reference 2)
CMT B Level Sensor PXS-012B Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Level Sensor PXS-012C Yes YesA'es 1
E* S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Level Sensor PXS-012D Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-013A Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-013B Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a. i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-013C Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT A Level Sensor PXS-013D Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Level Sensor PXS-014A Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT B Level Sensor PXS-014B Yes YesA'es 1
E*S Type Testing &
Anaiysis APP-JE61-VBR-002 /
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission N D-18-0185 Enclosure Page 15 of 16 Attachment A System: Passive Core Cooling System Equipment Name ^
Tag No.
- Seismic Cat. 1^3 Class 1E/
Qual. Harsh Envir.
Envir.
Zone ^
Envir Qual Program ^
Type of Qual.
EQ Reports (Reference 9)
As-Built EQRR (Reference 2) ^
CMT B Level Sensor PXS-014C Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX CMT 8 Level Sensor PXS-014D Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Wide Range Level Sensor PXS-046 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002/
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Wide Range Level Sensor PXS-047 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002/
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Wide Range Level Sensor PXS-048 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX PRHR HX Flow Sensor PXS-049A Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002/
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX PRHR HX Flow Sensor PXS-049B Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Flood-up Level Sensor PXS-050 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX Containment Flood-up Level Sensor PXS-051 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0185 Enclosure Page 16 of 16 Attachment A System: Passive Core Cooling System Equipment Name ^
Tag No. ^
Seismic Cat. i Class 1E/
Quai. Harsh Envir.
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 9)
As-Buiit EQRR (Reference 2) ^
Containment Flood-up Level Sensor PXS-052 Yes YesA'es 1
E* S Type Testing &
Analysis APP-JE61-VBR-002/
APP-JE61-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Lower Narrow Range Level Sensor PXS-066 Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Lower Narrow Range Level Sensor PXS-067 Yes YesA'es 1
E* S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Lower Narrow Range Level Sensor PXS-068 Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.03.05a.i-U3-EQRR-PCDXXX IRWST Lower Narrow Range Level Sensor PXS-069 Yes YesA'es 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.03.05a. i-U3-EQRR-PCDXXX RNS Suction Leak Test Valve PXS-PL-V208A Yes
-/-
N/A N/A Analysis APP-PV17-VBR-004/
APP-PV17-VBR-003 2.2.03.05a.i-U3-EQRR-PCDXXX Notes:
+Excerpt from COL Appendix C Table 2.2.3-1 1.
See Table 3D.5-1 of UFSAR 2.
E - Electrical Equipment Program (limitswitch 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 "2.2.03.05a.i-U4-EQRR-PCDXXX"