ML18057A451
| ML18057A451 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/23/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.2.04.05a.i, ND 18-0198 | |
| Download: ML18057A451 (16) | |
Text
k. Southern Nuclear FEB 2 3 2018 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynestjoro, GA 30830 706-848-6459 tel 410-474-8587 cell myox @southernco.com ND-18-0198 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 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.04.05a.i [Index Number 2261 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 20, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item2.2.04.05a.i
[Index Number 226] has not been completed greater than 225-days priorto 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 performedor 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 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
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.05a.i [Index Number 226]
MUY/PGIVamw
U.S. Nuclear Regulatory Commission ND-18-0198 Page 2 of 3 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. 0. 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. P. B. Donnelly 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 Oaiethoroe Power Corporation Mr. R. B. Brinkman Municipai Eiectric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0198 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. C. 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. 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 Sen/ice 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-18-0198 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-18-0198 Enclosure Vogtle Electric Generating Riant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.05a.i [Index Number 226]
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 2 of 13 ITAAC Statement Desion Commitment:
5.a) The seismic Category Iequipment identified in Table 2.2.4-1 can withstand seismic design basis loads without loss of safety function.
7.a) The Class 1E equipment identified in Table 2.2.4-1 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 verify that the seismicCategory Iequipment identified inTable 2.2.4-1 is located on the Nuclear Island.
ii) Type tests, analyses,or a combination oftypetests and analyses ofseismic Category I equipment will be performed.
ill) Inspection will be performed for the existence ofa report verifying thatthe as-built equipment including anchorageis seismically bounded bythe tested or analyzed conditions.
i) Type tests, analyses, ora combination of type testsand analyses will be performed on Class 1E equipment located in a harsh environment.
ii) Inspection will be performed of theas-built Class 1E equipment andtheassociated wiring, cables, and terminations located in a harsh environment.
Acceptance Criteria:
i) The seismic Category Iequipment identified in Table 2.2.4-1 is located on the Nuclear Island.
ii) Areport exists and concludes that the seismic Category Iequipment can withstand seismic design basis loads without loss of safety function.
iii) Areport exists and concludes that the as-built equipment including anchorage isseismically bounded by the tested or analyzed conditions.
i) Areport exists and concludes that the Class 1E equipment identified in Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental 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 and the associated wiring, cables, and terminations identified in Table2.2.4-1 as beingqualified fora harsh environment are bounded bytypetests, analyses, or a combination oftypetests and analyses.
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 3 of 13 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Steam Generator System (SGS) equipment identifiedas seismic Category Ior Class 1E in the Combined License (COL) Appendix C, Table 2.2.4-1 (the Table) is designed and constructed in accordance with applicable requirements.
\\) The seismic Category I eouioment identified in Table 2.2.4-1 is located on the Nuclear Island.
To assure that seismic Category I equipment can withstand seismic design basis loads without loss of safety function, all the equipment in the Table is designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the SGS to confirm the satisfactory installation of the seismically qualified equipment. The inspection includes verification of equipment make/model/serial number and verification of equipment 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 I equipment is located on the Nuclear Island.
ih A report exists and concludes that the seismic Category I eouioment can withstand seismic desion basis loads without loss of safety function.
Seismic Category Iequipment inthe Table requires type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category Ivalves is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of the subset ofactivesafety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).
Safety-related(Class IE) electrical equipmentinthe Table is seismically qualified bytype testing combinedwith analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard344-1987 (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 valvesand electrical connectorassemblies. The specific qualification method (i.e., type testing, analysis, or combination) usedfor each piece of equipment in the Table is identified in Attachment A. Additional information aboutthe methods used to qualify API000 safety-related equipment is provided inthe Updated Final Safety Analysis Report (UFSAR) Appendix 3D(Reference 6). The EG Reports (Reference 7) identified inAttachmentAcontain applicabletest reports and associated documentation and conclude that the seismicCategory Iequipment can withstand seismicdesign basis loads without loss of safety function.
iiilA report exists and concludes that the as-built eouioment includina anchorage is seismicallv bounded bv the tested or analvzed conditions.
An inspection (Reference1) is conductedto confirm the satisfactory installation ofthe 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
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 4 of 13 seismically qualified equipment 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) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-piantinstallation does not degrade the established qualification, interface requirements are defined based on the test configuration and other design requirements.
Attachment A identifiesthe EQRR (Reference 2) completed to verify that the as-built seismic Categoryi equipment listed inthe Table, including anchorage, isseismically bounded bythe tested or analyzedconditions, IEEE Standard 344-1987 (Reference5),and NRC Regulatory Guide (RG) 1.100 (Reference 8).
h A report exists and concludes that the Class 1E eouioment identified in Table 2.2.4-1 as being Qualifiedfor a harsh environment can withstand the environmental conditions that would exist before, durino. and following a design basis accident without loss of safetv function for the time reouired to perform the safetv function.
The harsh environment Class 1Eequipment in the Table is qualified bytypetestingand/or analyses. Class 1E electrical equipment type testing isperformed in accordance with IEEE Standard 323-1974 (Reference 9) and RG 1.89 (Reference 10) to meet the requirements of 10 CFR 50.49. Type testing of safety-related equipment meets the requirements of 10CFR Part 50, Appendix A, General Design Criterion 4. Attachment Aidentifies the EQ program and specific qualification method for each safety-related mechanical orClass 1E electrical equipment located in a harsh environment. Additional information about the methods used to qualify API000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 6).
EQ Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation and concludethat the equipmentcan withstand the environmental conditions thatwould exist before, during, andfollowing a design basisaccident without lossof safetyfunction for thetime required to perform the safety function.
W) A reoort exists and concludes that the as-builtClass 1E eouioment and the associated wiring.
cables, and terminations identified in Table 2.2.4-1 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 of the SGS to confirm the satisfactory installation of the Class1Eequipment in theTable. Theinspection verifies the equipment location, make/model/serial number, as-designedequipment mounting, wiring, cables, and terminations, and confirms that the environmental conditionsforthe zone (Attachment A) in which the equipment ismounted are bounded by the tested and/or analyzed conditions. It also documents the installed configuration with photographs or sketches/drawings ofequipment mounting and connections. The EQRR (Reference 2) identified in Attachment Adocument this inspection, and conclude that the as-built harsh environment Class 1E equiprnent and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 9).
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 5 of 13 Together, these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met; The seismic Category I equipment Identified In Table 2.2.4-1 Is located on the Nuclear Island; A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; A report exists and concludes that the as-bullt equipment Including anchorage Is selsmlcally bounded by the tested or analyzed conditions; A report exists and concludes that the Class 1E equipment Identified In Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function; and A report exists and concludes that the as-bullt Class 1E equipment and the associated wiring, cables, and terminations Identified InTable 2.2.4-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.
References 2 and 7 are available for NRC Inspection as part of the Unit3 and Unit4 ITAAC 2.2.04.05a.l Completion Packages (References 11 and 12, respectively).
List of ITAAC Findings Inaccordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review ofall ITAAC findings pertaining to the subject ITAAC and associated correctiveactions. Thisfinding review, which Included now-consolidated ITAAC Indexes 227, 228, 231, and 232, found no relevant ITAAC findings associated with this ITAAC.
References favaiiabie for NRC inspection) 1.
ND-xx-xx-001, "EG Walkdown ITAAC Guideline" 2.
EG As-Bullt Reconciliation Reports as Identified In Attachment Afor Units3 and 4
Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda
- 4. ASMEQME-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 Equipmentfor Nuclear Power Generating Stations"
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 6 of 13 6.
Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API 000 Safety-Related Electrical and Mechanical Equipment" 7.
Equipment Qualification 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 Equipment for Nuclear Power Generating Stations"
- 10. Regulatory Guide 1.89, Rev 1, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants" 11.2.2.04.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.2.04.05a.i [Index Number 226]"
12.2.2.04.05a.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.2.04.05a.i [Index Number 226]"
- 13. NEI 08-01, "Industry Guideline forthe ITAAC ClosureProcess Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 7 of 13 Attachment A System: Steam Generator System Equipment Name ^
Tag No.
- Seismic Cat. i ^
Class 1E/
Qual. For Harsh Envir.^
Envir.
Zone ^
Envir Qual Program Type of Qual.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2) ^
Main Steam Safety Valve SG01 SGS-PL-V030A Yes N/A N/A Type Testing &
Analysis APP-PV65-VBR-012/
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG02 SGS-PL-V030B Yes N/A N/A Type Testing &
Analysis APP-PV65-VBR-012 /
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG01 SGS-PL-V031A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV65-VBR-012/
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG02 SGS-PL-V031B Yes N/A N/A Type Testing &
Analysis APP-PV65-VBR-012/
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG01 SGS-PL-V032A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV65-VBR-012 /
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG02 SGS-PL-V032B Yes N/A N/A Type Testing &
Analysis APP-PV65-VBR-012 /
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG01 SGS-PL-V033A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV65-VBR-012/
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PGDXXX Main Steam Safety Vaive SG02 SGS-PL-V033B Yes N/A N/A Type Testing &
Analysis APP-PV65-VBR-012 /
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Vaive SG01 SGS-PL-V034A Yes N/A N/A Type Testing &
Analysis APP-PV65-VBR-012/
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 8 of 13 Equipment Name ^
Tag No. +
Seismic Cat. 1 Class ie Qual. For Harsh Envir.^^
Envir.
Zone ^
Envir Qual Program ^
Type of Qual.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2) ^
Main Steam Safety Valve SG02 SGS-PL-V034B Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV65-VBR-012 /
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG01 SGS-PL-V035A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV65-VBR-012 /
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Safety Valve SG02 SGS-PL-V035B Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV65-VBR-012 /
APP-PV65-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A Yes Yes/Yes 5
M*ES Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Line Condensate Drain Isolation Valve SGS-PL-V036B Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Isolation Valve SGS-PL-V040A Yes Yes/Yes 5
M* ES Type Testing &
Analysis APP-PV64-VBR-XXX /
APP-PV64-VBR-XXX 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Isolation Valve SGS-PL-V040B Yes YesA'es 5
M*ES Type Testing &
Analysis APP-PV64-VBR-XXX /
APP-PV64-VBR-XXX 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes Yes/Yes 5
M* ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 9 of 13 Equipment Name ^
Tag No. ^
Seismic Cat. 1 ^
CiasslE/
Quai. For Harsh Envir.^^
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)"
Steam Line Condensate Drain Control Valve SGS-PL-V086S Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV14-VBR-002/
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Feedwater Isolation Valve SGS-PL-V057A Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV67-VBR-XXX /
APP-PV67-VBR-XXX 2.2.04.05a.i-U3-EQRR-PCDXXX Main Feedwater Isolation Valve SGS-PL-V057S Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV67-VBR-XXX /
APP-PV67-VBR-XXX 2.2.04.05a.i-U3-EQRR-PCDXXX Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067S Yes YesA'es 5
M*ES Type Testing &
Analysis APP-PV01-VBR-012/
APP-PV01-VBR-011 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator Slowdown Isolation Valve SGS-PL-V074A Yes YesA'es 10 M* ES Type Testing &
Analysis APP-PV14-VBR-002/
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator Slowdown Isolation Valve SGS-PL-V074S Yes YesA'es 10 M* ES Type Testing &
Analysis APP-PV14-VBR-002/
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator Slowdown Isolation Valve SGS-PL-V075A Yes YesA'es 10 M* ES Type Testing &
Analysis APP-PV14-VBR-002/
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator Slowdown Isolation Valve SGS-PL-V075S Yes YesA'es 10 M* ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Power-operated Relief Valve SGS-PL-V233A Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV66-VBR-002 /
APP-PV66-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Power-operated Relief Valve SGS-PL-V233S Yes YesA'es 5
M* ES Type Testing &
Analysis APP-PV66-VBR-002 /
APP-PV66-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 10 of 13 Equipment Name
- Tag No.
- Seismic Cat. 1
- Class IE/
Quai. For Harsh Envir.*
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2) ^
Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Yes/Yes 5
M* ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Isolation Valve Bypass Isolation SGS-PL-V240B Yes Yes/Yes 5
M*ES Type Testing &
Analysis APP-PV14-VBR-002 /
APP-PV14-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Feedwater Control Valve SGS-PL-V250A Yes Yes/Yes 5
M* ES Type Testing &
Analysis APP-PV69-VBR-002 /
APP-PV69-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Feedwater Control Valve SGS-PL-V250B Yes Yes/Yes 5
M* ES Type Testing &
Analysis APP-PV69-VBR-002 /
APP-PV69-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Startup Feedwater Control Valve SGS-PL-V255A Yes Yes/Yes 5
M* ES Type Testing &
Analysis APP-PV69-VBR-002 /
APP-PV69-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Startup Feedwater Control Valve SGS-PL-V255B Yes Yes/Yes 5
M*ES Type Testing &
Analysis APP-PV69-VBR-002 /
APP-PV69-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Feedwater Thermal Relief Valve SGS-PL-V257A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Feedwater Thermal Relief Valve SGS-PL-V257B Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Startup Feedwater Thermal Relief Valve SGS-PL-V258A Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV16-VBR-002 /
APP-PV16-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Startup Feedwater Thermal Relief Valve SGS-PL-V258B Yes
-/-
N/A N/A Type Testing &
Analysis APP-PV16-VBR-002/
APP-PV16-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Narrow Range Level Sensor SGS-001 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 11 of 13 Equipment Name ^
Tag No.
- Seismic Cat. 1 Class IE/
Qual. For Harsh Envir.+
Envir.
Zone ^
Envir Quai Program ^
Type of Qual.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2) ^
Steam Generator 1 Narrow Range Level Sensor SGS-002 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002/
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Narrow Range Level Sensor SGS-003 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Narrow Range Level Sensor SGS-004 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Narrow Range Level Sensor SGS-005 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Narrow Range Level Sensor SGS-006 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Narrow Range Level Sensor SGS-007 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Narrow Range Level Sensor SGS-008 Yes Yes/Yes 1
E*S Type Testing &
Anaiysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Wide Range Levei Sensor SGS-011 Yes Yes/Yes 1
E* S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Wide Range Level Sensor SGS-012 Yes Yes/Yes 1
E* S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Wide Range Level Sensor SGS-013 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Wide Range Level Sensor SGS-014 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 12 of 13 Equipment Name ^
Tag No.
- Seismic Cat. 1 Class IE/
Quai. For Harsh Envir.^
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 7)
As-Buiit EQRR (Reference 2) ^
Steam Generator 1 Wide Range Level Sensor SGS-015 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Wide Range Level Sensor SGS-016 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Wide Range Level Sensor SGS-017 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Wide Range Level Sensor SGS-018 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Steam Generator 1 Pressure Sensor SGS-030 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Steam Generator 1 Pressure Sensor SGS-031 Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Steam Generator 1 Pressure Sensor SGS-032 Yes Yes/Yes 1
E* S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Steam Generator 1 Pressure Sensor SGS-033 Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Steam Generator 2 Pressure Sensor SGS-034 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Steam Generator 2 Pressure Sensor SGS-035 Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Main Steam Line Steam Generator 2 Pressure Sensor SGS-036 Yes Yes/Yes 1
E*S Type Testing &
Analysis APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 13 of 13 Equipment Name ^
Tag No. ^
Seismic Cat. 1
- Class 1E/
Quai. For Harsh Envir.+
Envir.
Zone ^
Envir Quai Program ^
Type of Quai.
EQ Reports (Reference 7)
As-Buiit EQRR (Reference 2) ^
Main Steam Line Steam Generator 2 Pressure Sensor SGS-037 Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Startup Feedwater Flow Sensor SGS-55A Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 1 Startup Feedwater Flow Sensor SGS-55B Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Startup Feedwater Flow Sensor SGS-56A Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Steam Generator 2 Startup Feedwater Flow Sensor SGS-56B Yes Yes/No N/A N/A Type Testing APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.2.04.05a.i-U3-EQRR-PCDXXX Notes:
+ Excerpt from COL Appendix C Table 2.2.4-1 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 "2.2.04.05a.i-U4-EQRR-PCDXXX"