ND-18-0175, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.02.05a.i (Index Number 126)
| ML18054A655 | |
| 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 | |
| ITAAC 2.2.02.05a.i, ND-18-0175 | |
| Download: ML18054A655 (14) | |
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Southern Nuclear FEB 2 2 2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Vox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 708-848-6459 tei 410-474-8587 ceii myox@souttiernco.com ND-18-0175 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.02.05a.i findex Number 1261 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 15, 2018, Vogtie Electric Generating Plant (VEGP) Unit3 and Unit4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item2.2.02.05a.i
[Index Number126]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 completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRCto support the Commission finding that all acceptance criteria are met priorto 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. Vox Regulatory Affairs Director Vogtie 3 &4
U.S. Nuclear Regulatory Commission ND-18-0175 Page 2 of 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Completion Plan for Uncompleted ITAAC 2.2.02.05a.i [Index Number 126]
MJY/PGLVamw
U.S. Nuclear Regulatory Commission ND-18-0175 Page 3 of 4 To:
Southern Nuclear Operating Company / Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Rauckhorst (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. 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 Regulatory 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0175 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. 8. 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, Balch BIngham
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-18-0175 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Completion Plan for Uncompleted ITAAC 2.2.02.05a.l [Index Number 126]
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 2 of 10 ITAAC Statement Design Commitment:
5.a) The seismic Category Icomponents identified in Table 2.2.2-1 can withstand seismic design basis loads without loss of safety function.
6.a) The Class 1E components identified in Table 2.2.2-1 as being qualifiedfor 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 verify that the seismic Category Icomponents and valves identified in Table 2.2.2-1 are located on the Nuclear Island.
ii) Typetests, analyses, or a combination oftype tests and analyses of seismic Category I components will be performed.
ill) Inspection will be performedforthe existence of a report verifying that the as-built components including anchorage are seismically bounded bythe tested or analyzed conditions.
i) Type tests or a combination oftype tests and analyses will be performedon Class 1E components located in a harsh environment.
ii) Inspection will be performed ofthe as-built Class 1E components and the associated wiring, cables, and terminations located in a harsh environment.
Acceptance Criteria:
i) The seismic Category Icomponents identified inTable 2.2.2-1 are located on the Nuclear Island.
ii) Areport existsand concludes thatthe seismic Category Icomponents can withstand seismic design basis loads without loss of safety function.
iii) The reportexists and concludes that the as-built components including anchorage are seismically bounded by the tested or analyzed conditions.
i) A report exists and concludes that the Class 1E components identified in Table 2.2.2-1 as beingqualified fora harsh environment can withstand the environmental conditions that would exist before,during, and following a design basis accident without loss ofsafety function forthe time required to perform the safety function.
ii) Areport existsand concludes thatthe as-built Class 1Ecomponents and the associated wiring, cables, and terminations identified inTable2.2.2-1 as being qualified fora harsh environmentare bounded bytype tests, analyses, or a combination of type tests and analyses.
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 3 of 10 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performedand documented to ensure the Passive Containment CoolingSystem (PCS) components identified as seismic Category IorClass 1E in the Combined License (COL) Appendix C,Table 2.2.2-1 (the Table) are designed and constructed in accordance with applicable requirements.
i) The seismic Category I components identified in Table 2.2.2-1 are located on the Nuclear Island.
To assure that seismic Category Icomponents can withstand seismic design basis loads without lossofsafetyfunction, all ofthe components in the Table are designedto be located on the seismic Category INuclear Island. In accordance with Equipment Qualification (EG)
Walkdown ITAAC Guideline (Reference 1),an inspection is conducted ofthe PCS to confirm the satisfactory installation ofthe seismically qualified components. The inspection includes verification ofcomponent make/model/serial numberand verification ofcomponent location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category Icomponents are locatedon the Nuclear Island.
ih A report exists and concludes that the seismic Cateoorv I components can withstand seismic design basis loads without loss of safety function.
SeismicCategory Icomponents inthe Table require typetests and/oranalyses to demonstrate structural integrity andoperability. Structural integrity of the seismic Category Ivalves, as well as otherpassive seismic Category Imechanical components, isdemonstrated byanalysis in accordance with American Societyof Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of thesubsetof active safety-related valves under seismic loads is determined using theguidance of ASME QME-1-2007 (Reference 4). Structural integrity of the passive containment cooling water storage tank (PCCWST) isdemonstrated by analysis.
Structural integrity of thewater distribution bucket andwater distribution weirs isdemonstrated byanalysis in accordance with ANSI/AISC N690-1994 (Reference 5).
Safety-related (Class 1E) electrical components in theTable are seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 6). These components include safety-related (Class 1E) field sensors andthesafety-related active valve accessories such as electric actuators, position switches, pilot solenoid valves andelectrical connector assemblies. The specific qualification method (i.e., type testing, analysis, orcombination) used for each component in theTable isidentified in Attachment A. Additional information about the methods used toqualify API 000 safety-related components isprovided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 7). The EG Reports (Reference 8) identified in Attachment Acontain applicable test reportsand associated documentation and conclude thatthe seismic Category Icomponents can withstand seismic design basis loadswithout loss of safety function.
iiil The report exists and concludes that the as-built comoonents including anchorage are seismicallv bounded bv the tested or analvzed conditions.
An inspection (Reference 1) isconducted toconfirm thesatisfactory installation of the
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 4 of 10 selsmlcally qualified components in the Table. The inspection verifies the component make/model/serial number, as-designed component mounting orientation, anchorage and clearances, and electrical and other interfaces.
The documentation of installed configuration of selsmlcally qualified components includes photographs and/or sketches/drawings of component/mounting/interfaces.
As part of the seismic qualification program, consideration is given to the definition of the clearances needed around the component mounted in the plant, to permit the component to move during a postulated seismic event without causing impact between adjacent pieces of safety-related components. This is done as part of seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the components. EQ Reports (Reference 8) identify the component mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification. Interface requirements are defined based on the test configuration and other design requirements.
Attachment A identifies the EQRR (Reference 2) completed to verify that the as-built seismic Category Icomponents listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 6), and NRG Regulatory Guide (RG) 1.100 (Reference 9).
i) A report exists and concludes that the Class 1E components identified in Table 2.2.2-1 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 safetv function for the time required to perform the safetv function.
The harsh environment Class IE components in the Table are qualified by type testing and/or analyses. Class IE electrical component type testing is performed in accordance with IEEE Standard 323-1974 (Reference 10) and RG 1.89 (Reference 11), to meet the requirements of 10 CFR 50.49. Type testing of safety-related components meets the requirements of 10 CFR Part 50, AppendixA, General Design Criterion 4. Attachment A identifiesthe EQ program and specific qualification method for each safety-related mechanical or Class 1E electrical component located in a harsh environment. Additional information about the methods used to qualify API 000 safety-related components is provided in the UFSARAppendix 3D (Reference 7). EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and conclude that the components 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 components and the associated wiring, cables, and terminations identified in Table 2.2.2-1 as being qualified for a harsh environment are bounded bv tvoe tests, analvses. or a combination of tvpe tests and analyses.
An inspection (Reference 1) is conducted of the PCS to confirmthe satisfactory installation of the Class IE components in the Table. The inspection verifies the component location, make/model/serial number, as-designed component mounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the component is mounted are bounded by the tested or analyzed conditions. It also documents the installed configuration with photographs and/or sketches/drawings of component mounting and connections. The EQRR (Reference 2) identified in Attachment A document this
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 5 of 10 Inspection, and conclude that the as-built harsh environment Class 1E component and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 10).
Together, these reports (References 2 and 8) provide evidence that the ITAAC Acceptance Criteria requirements are met:
The seismic Category Icomponents identified in Table 2.2.2-1 are located on the Nuclear Island; A report exists and concludes that the seismic Category Icomponents can withstand seismic design basis loads without loss of safety function; The report exists and concludes that the as-built components including anchorage are seismically bounded by the tested or analyzed conditions; A report exists and concludes that the Class 1E components identified in Table 2.2.2-1 as being qualified fora harsh environmentcan withstandthe environmental conditionsthat would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function; and A report exists and concludes that the as-built Class 1E components and the associated wiring, cables, and terminations identified inTable 2.2.2-1 as beingqualified fora harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.
References 2 and 8 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.02.05a.i Completion Packages (References 12 and 13, respectively).
List of ITAAC Findings Inaccordance with plant procedures for ITAAC completion, Southern NuclearOperating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.
This review, which included now consolidated ITAAC Indexes 127,128,131 and 132, found the following relevant ITAAC findings associated with this ITAAC:
- 1) Notice of Nonconformance 99900404/2012-201 -04 (Closed)
- 2) Notice of Nonconformance 99901412/2012-201 -02 (Closed)
Before submission of the ITAAC Closure Notification (ICN), corrective actions will be completed for relevant ITAACfindings.
References (available for NRC Inspection) 1.
ND-xx-xx-001, "EQ Walkdown ITAAC Guideline" 2.
EQ As-Built Reconciliation Reports (EQRR) as identified inAttachment Afor Units3 and 4
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 6 of 10 3.
American Society of Mecfianical Engineers (ASME) Boiler and Pressure Vessel (B&PV)
Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition, 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.
ANSI/AISC N690-1994, "American National Standard Specification for the Design, Fabrication, and Erection of Steel Safety-Related Structures for Nuclear Facilities" 6.
IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"
- 7. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodologyfor Qualifying API 000 Safety-Related Electrical and Mechanical Equipment" 8.
Equipment Qualification (EQ) Reports as identified in Attachment A 9.
Regulatory Guide 1.100, Rev. 2, "Seismic Qualificationof Electric and Mechanical Equipment for Nuclear Power Plants"
- 10. IEEE Standard 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations"
- 11. Regulatory Guide 1.89, Rev 1, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants" 12.2.2.02.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.2.02.05a.i [Index Number 126]"
13.2.2.02.05a.i-U4-CP-Rev X, "Completion Package for Unit4 ITAAC 2.2.02.05a.i [Index Number 126]"
- 14. NEI 08-01, "Industry Guidelinefor the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 7 of 10 Attachment A System: Passive Containment Cooling System (PCS)
Component Name ^
Tag No, ^
Seismic Cat. i ^
Class 1E/
Quai.
for Harsh Envir.^3 Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 8)
As-Buiit EQRR (Reference 2)"
PCCWST PCS-MT-01 Yes N/A N/A Analysis APP-XXX-XXX-XXX 2.2.02.05a.i-U3-EORR-PCDXXX Water Distribution Bucket PCS-MT-03 Yes N/A N/A Analysis APP-MT05-S3C-002 2.2.02.05a.i-U3-EORR-PCDXXX Water Distribution Wiers (sic)
PCS-MT-04 Yes N/A N/A Analysis APP-MT05-S3C-002 2.2.02.05a.i-U3-EORR-PCDXXX PCCWST Isoiation Valve PCS-PL-V001A Yes Yes/No N/A N/A Type Testing &
Analysis APP-PV11-VBR-004/
APP-PV11-VBR-003 2.2.02.05a.i-U3-EQRR-PCDXXX PCCWST Isolation Valve PCS-PL-V001B Yes Yes/No N/A N/A Type Testing &
Analysis APP-PV11-VBR-004/
APP-PV11-VBR-003 2.2.02.05a.i-U3-EORR-PCDXXX PCCWST Isolation Valve MOV PCS-PL-V001C Yes Yes/No N/A N/A Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.02.05a.i-U3-EORR-PCDXXX PCCWST Isolation Block MOV PCS-PL-V002A Yes Yes/No N/A N/A Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.02.05a.i-U3-EORR-PCDXXX PCCWST Isolation Block MOV PCS-PL-V002B Yes Yes/No N/A N/A Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.02.05a.i-U3-EORR-PCDXXX PCCWST Isolation Block MOV PCS-PL-V002C Yes Yes/No N/A N/A Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.02.05a.i-U3-EQRR-PCDXXX PCS Recirculatlon Return Isolation Valve PCS-PL-V023 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV03-VBR-010/
APP-PV03-VBR-009 2.2.02.05a.i-U3-EORR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 8 of 10 Component Name ^
Tag No.
- Seismic Cat. i +
Class 1E/
Quai.
for Harsh Envir.^
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 8)
As-Buiit EQRR (Reference 2) ^
POCWST Supply to Fire Protection System Isolation Valve PCS-PL-V005 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV03-VBR-010/
APP-PV03-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX PCS Makeup to SFS Isolation Valve PCS-PL-V009 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV03-VBR-010/
APP-PV03-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX Water Makeup Isolation Valve PCS-PL-V044 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV03-VBR-010/
APP-PV03-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX Water Bucket Makeup Line Drain Valve PCS-PL-V015 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX Water Bucket Makeup Line Isolation Valve PCS-PL-V020 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV03-VBR-010/
APP-PV03-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX PCCWST Long-Term Makeup Line Check Valve PCS-PL-V039 Yes
-/No N/A N/A Analysis APP-PV03-VBR-014 /
APP-PV03-VBR-013 2.2.02.05a.i-U3-EQRR-PCDXXX PCCWST Long-Term Makeup Drain isolation PCS-PL-V042 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX PCS Discharge to SFS Pool Isolation Valve PCS-PL-V045 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX Recirc Header Discharge to PCCWST Isolation Valve PCS-PL-V046 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV03-VBR-010/
APP-PV03-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX PCCWST Drain Isolation Valve PCS-PL-V049 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 9 of 10 Component Name ^
Tag No.
- Seismic Cat. 1 +
Class 1E/
Quai.
for Harsh Envir.+ 3 Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EG Reports (Reference 8)
As-Built EQRR (Reference 2)
-/No N/A N/A Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX PCCWST Discharge to SFS Pool Isolation Valve PCS-PL-V051 Yes
-/No N/A N/A Type Testing &
Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.2.02.05a.i-U3-EQRR-PCDXXX PCS Water Delivery Flow Sensor PCS-001 Yes Yes/No N/A N/A Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX PCS Water Delivery Flow Sensor PCS-002 Yes Yes/No N/A N/A Type Testing &
Analysis APP-JE52-VBR-006/
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX PCS Water Delivery Flow Sensor PCS-003 Yes Yes/No N/A N/A Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX PCS Water Delivery Flow Sensor PCS-004 Yes Yes/No N/A N/A Type Testing &
Analysis APP-JE52-VBR-006/
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX Containment Pressure Sensor PCS-005 Yes Yes/Yes 7
E*
Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX Containment Pressure Sensor PCS-006 Yes Yes/Yes 7
E*
Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX Containment Pressure Sensor PCS-007 Yes Yes/Yes 7
E*
Type Testing &
Analysis APP-JE52-VBR-006/
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX Containment Pressure Sensor PCS-008 Yes Yes/Yes 7
E*
Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX PCCWST Water Level Sensor PCS-010 Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.02.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0175 Enclosure Page 10 of 10 Component Name ^
Tag No. ^
Seismic Cat. i Class IE/
Qual.
for Harsh Envir.^
Envir.
Zone ^
Envir Qual Program Type of Quai.
EG Reports (Reference 8)
As-Built EQRR (Reference 2) ^
PCCWST Water Level Sensor PCS-011 Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.02.05a.i-U3-EQRR-PCDXXX High-range Containment Pressure Sensor PCS-012 Yes Yes/Yes 7
E*
Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX High-range Containment Pressure Sensor PCS-013 Yes Yes/Yes 7
E*
Type Testing &
Analysis APP-JE52-VBR-006 /
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX High-range Containment Pressure Sensor PCS-014 Yes Yes/Yes 7
E*
Type Testing &
Analysis APP-JE52-VBR-006/
APP-JE52-VBR-005 2.2.02.05a.i-U3-EQRR-PCDXXX Notes:
+ Excerpt from COL Appendix C Table 2.2.2-1 1.
See Table 3D.5-1 of UFSAR 2.
E = Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)
- = Harsh Environment 3.
Dash (-) indicates not applicable 4.
The Unit 4 As-Built EQRR are numbered "2.2.02.05a.i-U4-EQRR-PCDXXX"