ML18057A451

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Voglte, Units 3 and 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel and Load Item 2.2.04.05a.i (Index Number 226)
ML18057A451
Person / Time
Site: Vogtle  Southern Nuclear icon.png
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)
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Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynestjoro, GA 30830

k. Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell FEB 2 3 2018 myox @southernco.com Docket Nos.: 52-025 52-026 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) Item 2.2.04.05a.i

[Index Number 226] 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 notifications for 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 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 I equipment 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 seismic Category I equipment identified inTable 2.2.4-1 is located on the Nuclear Island.

ii) Type tests, analyses, or a combination oftype tests and analyses of seismic Category I equipment will be performed.

ill) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded bythe tested or analyzed conditions.

i) Type tests, analyses, ora combination of type tests and analyses will be performed on Class 1E equipment located in a harsh environment.

ii) Inspection will be performed of the as-built Class 1E equipment andthe associated 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 the time required to perform the safety function.

ii) Areport exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.4-1 as being qualified for a harsh environment are bounded bytype tests, analyses, or a combination of type tests 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 identified as seismic Category I or 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 I equipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section 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 IE) electrical equipment in the Table is seismically qualified by type testing combinedwith 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 connectorassemblies. The specific qualification method (i.e., type testing, analysis, or combination) used for 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 in Attachment A contain applicable test reports and associated documentation and conclude that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

iiil A report exists and concludes that the as-built eouioment includina anchorage is seismicallv bounded bv the tested or analvzed conditions.

An inspection (Reference 1) is conductedto 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

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-piant installation 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 Category i equipment listed inthe Table, including anchorage, is seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 5), 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 1E equipment in the Table is qualified by type testing and/or analyses. Class 1E electrical equipment type testing is performed 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 API 000 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 conclude that the equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without lossof safetyfunction for the time required to perform the safety function.

W) A reoort exists and concludes that the as-built Class 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 Class 1Eequipment in the Table. The inspection verifies the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirms that the environmental conditionsfor the zone (Attachment A) in which the equipment is mounted are bounded by the tested and/or analyzed conditions. It also documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 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 In Table 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 Unit 3 and Unit 4 ITAAC 2.2.04.05a.l 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 to the subject ITAAC and associated corrective actions. This finding 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 A for Units 3 and 4
3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

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"

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 for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 7 of 13 Attachment A System: Steam Generator System Class 1E/ Envir Seismic Envir. Type of EQ Reports As-Built EQRR Equipment Name ^ Tag No.

  • Qual. For Qual (Reference 7) (Reference 2) ^

Cat. i ^ Zone ^ Qual.

Harsh Envir.^ Program Type Main Steam Safety APP-PV65-VBR-012/ 2.2.04.05a.i-U3-SGS-PL-V030A Yes N/A N/A Testing &

Valve SG01 APP-PV65-VBR-011 EQRR-PCDXXX Analysis Type Main Steam Safety APP-PV65-VBR-012 / 2.2.04.05a.i-U3-SGS-PL-V030B Yes N/A N/A Testing &

Valve SG02 APP-PV65-VBR-011 EQRR-PCDXXX Analysis Type Main Steam Safety APP-PV65-VBR-012/ 2.2.04.05a.i-U3-SGS-PL-V031A Yes -/- N/A N/A Testing &

Valve SG01 APP-PV65-VBR-011 EQRR-PCDXXX Analysis Type Main Steam Safety Testing &

APP-PV65-VBR-012/ 2.2.04.05a.i-U3-SGS-PL-V031B Yes N/A N/A Valve SG02 APP-PV65-VBR-011 EQRR-PCDXXX Analysis Type Main Steam Safety APP-PV65-VBR-012 / 2.2.04.05a.i-U3-SGS-PL-V032A Yes -/- N/A N/A Testing &

Valve SG01 APP-PV65-VBR-011 EQRR-PCDXXX Analysis Type Main Steam Safety APP-PV65-VBR-012 / 2.2.04.05a.i-U3-SGS-PL-V032B Yes N/A N/A Testing &

Valve SG02 APP-PV65-VBR-011 EQRR-PCDXXX Analysis Type Main Steam Safety APP-PV65-VBR-012/ 2.2.04.05a.i-U3-SGS-PL-V033A Yes -/- N/A N/A Testing & EQRR-PGDXXX Valve SG01 APP-PV65-VBR-011 Analysis Type Main Steam Safety APP-PV65-VBR-012 / 2.2.04.05a.i-U3-SGS-PL-V033B Yes N/A N/A Testing &

Vaive SG02 APP-PV65-VBR-011 EQRR-PCDXXX Analysis Type Main Steam Safety APP-PV65-VBR-012/ 2.2.04.05a.i-U3-SGS-PL-V034A Yes N/A N/A Testing &

Vaive SG01 APP-PV65-VBR-011 EQRR-PCDXXX Analysis

U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 8 of 13 Class i e Envir Seismic Envir. Type of EQ Reports As-Built EQRR Equipment Name ^ Tag No. + Qual. For Qual Cat. 1 Zone ^ Qual. (Reference 7) (Reference 2) ^

Harsh Envir.^^ Program ^

Type 2.2.04.05a.i-U3-Main Steam Safety APP-PV65-VBR-012 /

SGS-PL-V034B Yes -/- N/A N/A Testing & EQRR-PCDXXX Valve SG02 APP-PV65-VBR-011 Analysis Type APP-PV65-VBR-012 / 2.2.04.05a.i-U3-Main Steam Safety N/A N/A Testing &

SGS-PL-V035A Yes -/- EQRR-PCDXXX Valve SG01 APP-PV65-VBR-011 Analysis Type 2.2.04.05a.i-U3-Main Steam Safety APP-PV65-VBR-012 /

SGS-PL-V035B Yes -/- N/A N/A Testing & EQRR-PCDXXX Valve SG02 APP-PV65-VBR-011 Analysis Power-operated Type Relief Valve Block APP-PV01-VBR-012/ 2.2.04.05a.i-U3-SGS-PL-V027A Yes Yes/Yes 5 M*ES Testing & EQRR-PCDXXX Motor-operated Valve APP-PV01-VBR-011 Analysis Steam Generator 01 Power-operated Type Relief Valve Block APP-PV01-VBR-012/ 2.2.04.05a.i-U3-SGS-PL-V027B Yes YesA'es 5 M* ES Testing & EQRR-PCDXXX Motor-operated Valve APP-PV01-VBR-011 Analysis Steam Generator 02 Steam Line Type 2.2.04.05a.i-U3-APP-PV14-VBR-002 /

Condensate Drain SGS-PL-V036A Yes YesA'es 5 M* ES Testing & EQRR-PCDXXX APP-PV14-VBR-001 Isolation Valve Analysis Steam Line Type 2.2.04.05a.i-U3-APP-PV14-VBR-002 /

Condensate Drain SGS-PL-V036B Yes YesA'es 5 M* ES Testing & EQRR-PCDXXX APP-PV14-VBR-001 Isolation Valve Analysis Type 2.2.04.05a.i-U3-Main Steam Line APP-PV64-VBR-XXX /

SGS-PL-V040A Yes Yes/Yes 5 M* ES Testing & EQRR-PCDXXX Isolation Valve APP-PV64-VBR-XXX Analysis Type 2.2.04.05a.i-U3-Main Steam Line APP-PV64-VBR-XXX /

SGS-PL-V040B Yes YesA'es 5 M*ES Testing & APP-PV64-VBR-XXX EQRR-PCDXXX Isolation Valve Analysis Steam Line Type APP-PV14-VBR-002 / 2.2.04.05a.i-U3-Condensate Drain SGS-PL-V086A Yes Yes/Yes 5 M* ES Testing & EQRR-PCDXXX APP-PV14-VBR-001 Control Valve Analysis

U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 9 of 13 CiasslE/ Envir Seismic Envir. Type of EQ Reports As-Built EQRR Equipment Name ^ Tag No. ^ Quai. For Quai (Reference 7) (Reference 2)"

Cat. 1 ^ Zone ^ Quai.

Harsh Envir.^^ Program ^

Steam Line Type 2.2.04.05a.i-U3-APP-PV14-VBR-002/

Condensate Drain SGS-PL-V086S Yes YesA'es 5 M* ES Testing & EQRR-PCDXXX APP-PV14-VBR-001 Control Valve Analysis Type 2.2.04.05a.i-U3-Main Feedwater APP-PV67-VBR-XXX /

SGS-PL-V057A Yes YesA'es 5 M* ES Testing &

Isolation Valve APP-PV67-VBR-XXX EQRR-PCDXXX Analysis Type Main Feedwater APP-PV67-VBR-XXX / 2.2.04.05a.i-U3-SGS-PL-V057S Yes YesA'es 5 M* ES Testing & EQRR-PCDXXX Isolation Valve APP-PV67-VBR-XXX Analysis Startup Feedwater Type 2.2.04.05a.i-U3-APP-PV01-VBR-012/

Isolation Motor- SGS-PL-V067A Yes YesA'es 5 M* ES Testing &

APP-PV01-VBR-011 EQRR-PCDXXX operated Valve Analysis Startup Feedwater Type 2.2.04.05a.i-U3-APP-PV01-VBR-012/

Isolation Motor- SGS-PL-V067S Yes YesA'es 5 M*ES Testing &

APP-PV01-VBR-011 EQRR-PCDXXX operated Valve Analysis Steam Generator Type 2.2.04.05a.i-U3-APP-PV14-VBR-002/

Slowdown Isolation SGS-PL-V074A Yes YesA'es 10 M* ES Testing &

APP-PV14-VBR-001 EQRR-PCDXXX Valve Analysis Steam Generator Type 2.2.04.05a.i-U3-APP-PV14-VBR-002/

Slowdown Isolation SGS-PL-V074S Yes YesA'es 10 M* ES Testing & EQRR-PCDXXX APP-PV14-VBR-001 Valve Analysis Steam Generator Type 2.2.04.05a.i-U3-APP-PV14-VBR-002/

Slowdown Isolation SGS-PL-V075A Yes YesA'es 10 M* ES Testing & EQRR-PCDXXX APP-PV14-VBR-001 Valve Analysis Steam Generator Type APP-PV14-VBR-002 / 2.2.04.05a.i-U3-Slowdown Isolation SGS-PL-V075S Yes YesA'es 10 M* ES Testing & EQRR-PCDXXX APP-PV14-VBR-001 Valve Analysis Type Power-operated APP-PV66-VBR-002 / 2.2.04.05a.i-U3-SGS-PL-V233A Yes YesA'es 5 M* ES Testing &

Relief Valve APP-PV66-VBR-001 EQRR-PCDXXX Analysis Type 2.2.04.05a.i-U3-Power-operated APP-PV66-VBR-002 /

SGS-PL-V233S Yes YesA'es 5 M* ES Testing & EQRR-PCDXXX Relief Valve APP-PV66-VBR-001 Analysis

U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 10 of 13 Class IE/ Envir Seismic Envir. Type of EQ Reports As-Built EQRR Equipment Name

  • Tag No.
  • Quai. For Quai (Reference 7) (Reference 2) ^

Cat. 1

  • Zone ^ Quai.

Harsh Envir.* Program ^

Main Steam Isolation Type APP-PV14-VBR-002 / 2.2.04.05a.i-U3-Valve Bypass SGS-PL-V240A Yes Yes/Yes 5 M* ES Testing &

APP-PV14-VBR-001 EQRR-PCDXXX Isolation Analysis Main Steam Isolation Type APP-PV14-VBR-002 / 2.2.04.05a.i-U3-Valve Bypass SGS-PL-V240B Yes Yes/Yes 5 M*ES Testing &

APP-PV14-VBR-001 EQRR-PCDXXX Isolation Analysis Type Main Feedwater APP-PV69-VBR-002 / 2.2.04.05a.i-U3-SGS-PL-V250A Yes Yes/Yes 5 M* ES Testing &

Control Valve APP-PV69-VBR-001 EQRR-PCDXXX Analysis Type Main Feedwater APP-PV69-VBR-002 / 2.2.04.05a.i-U3-SGS-PL-V250B Yes Yes/Yes 5 M* ES Testing &

Control Valve APP-PV69-VBR-001 EQRR-PCDXXX Analysis Type Startup Feedwater APP-PV69-VBR-002 / 2.2.04.05a.i-U3-SGS-PL-V255A Yes Yes/Yes 5 M* ES Testing &

Control Valve APP-PV69-VBR-001 EQRR-PCDXXX Analysis Type Startup Feedwater Testing &

APP-PV69-VBR-002 / 2.2.04.05a.i-U3-SGS-PL-V255B Yes Yes/Yes 5 M*ES Control Valve APP-PV69-VBR-001 EQRR-PCDXXX Analysis Type Main Feedwater APP-PV16-VBR-002/ 2.2.04.05a.i-U3-SGS-PL-V257A Yes -/- N/A N/A Testing &

Thermal Relief Valve APP-PV16-VBR-001 EQRR-PCDXXX Analysis Type Main Feedwater APP-PV16-VBR-002/ 2.2.04.05a.i-U3-SGS-PL-V257B Yes -/- N/A N/A Testing &

Thermal Relief Valve APP-PV16-VBR-001 EQRR-PCDXXX Analysis Type Startup Feedwater APP-PV16-VBR-002 / 2.2.04.05a.i-U3-SGS-PL-V258A Yes -/- N/A N/A Testing &

Thermal Relief Valve APP-PV16-VBR-001 EQRR-PCDXXX Analysis Type Startup Feedwater APP-PV16-VBR-002/ 2.2.04.05a.i-U3-SGS-PL-V258B Yes -/- N/A N/A Testing &

Thermal Relief Valve APP-PV16-VBR-001 EQRR-PCDXXX Analysis Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Narrow Range Level SGS-001 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis

U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 11 of 13 Class IE/ Envir Seismic Envir. Type of EQ Reports As-Built EQRR Equipment Name ^ Tag No.

  • Qual. For Quai Cat. 1 Zone ^ Qual. (Reference 7) (Reference 2) ^

Harsh Envir.+ Program ^

Steam Generator 1 Type APP-JE52-VBR-002/ 2.2.04.05a.i-U3-Narrow Range Level SGS-002 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Narrow Range Level SGS-003 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Narrow Range Level SGS-004 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Narrow Range Level SGS-005 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Narrow Range Level SGS-006 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Narrow Range Level SGS-007 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Narrow Range Level SGS-008 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Anaiysis Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Wide Range Levei SGS-011 Yes Yes/Yes 1 E* S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Wide Range Level SGS-012 Yes Yes/Yes 1 E* S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Wide Range Level SGS-013 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Wide Range Level SGS-014 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis

U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 12 of 13 Class IE/ Envir Seismic Envir. Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No.

  • Quai. For Quai Cat. 1 Zone ^ Quai. (Reference 7) (Reference 2) ^

Harsh Envir.^ Program ^

Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Wide Range Level SGS-015 Yes Yes/Yes 1 E*S Testing & EQRR-PCDXXX APP-JE52-VBR-001 Sensor Analysis Steam Generator 1 Type 2.2.04.05a.i-U3-APP-JE52-VBR-002 /

Wide Range Level SGS-016 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Wide Range Level SGS-017 Yes Yes/Yes 1 E*S Testing & EQRR-PCDXXX APP-JE52-VBR-001 Sensor Analysis Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Wide Range Level SGS-018 Yes Yes/Yes 1 E*S Testing & EQRR-PCDXXX APP-JE52-VBR-001 Sensor Analysis Main Steam Line Type 2.2.04.05a.i-U3-APP-JE52-VBR-002 /

Steam Generator 1 SGS-030 Yes Yes/Yes 1 E*S Testing &

APP-JE52-VBR-001 EQRR-PCDXXX Pressure Sensor Analysis Main Steam Line Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Steam Generator 1 SGS-031 Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Pressure Sensor Main Steam Line Type 2.2.04.05a.i-U3-APP-JE52-VBR-002 /

Steam Generator 1 SGS-032 Yes Yes/Yes 1 E* S Testing & EQRR-PCDXXX APP-JE52-VBR-001 Pressure Sensor Analysis Main Steam Line Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Steam Generator 1 SGS-033 Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Pressure Sensor Main Steam Line Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Steam Generator 2 SGS-034 Yes Yes/Yes 1 E*S Testing & EQRR-PCDXXX APP-JE52-VBR-001 Pressure Sensor Analysis Main Steam Line Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Steam Generator 2 SGS-035 Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Pressure Sensor Main Steam Line Type 2.2.04.05a.i-U3-APP-JE52-VBR-002 /

Steam Generator 2 SGS-036 Yes Yes/Yes 1 E*S Testing & EQRR-PCDXXX APP-JE52-VBR-001 Pressure Sensor Analysis

U.S. Nuclear Regulatory Commission ND-18-0198 Enclosure Page 13 of 13 Class 1E/ Envir Seismic Envir. Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No. ^ Quai. For Quai Quai. (Reference 7) (Reference 2) ^

Cat. 1

  • Zone ^

Harsh Envir.+ Program ^

Main Steam Line Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Steam Generator 2 SGS-037 Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Pressure Sensor Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Startup Feedwater SGS-55A Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Flow Sensor Steam Generator 1 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Startup Feedwater SGS-55B Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Flow Sensor Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Startup Feedwater SGS-56A Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Flow Sensor Steam Generator 2 Type APP-JE52-VBR-002 / 2.2.04.05a.i-U3-Startup Feedwater SGS-56B Yes Yes/No N/A N/A Testing APP-JE52-VBR-001 EQRR-PCDXXX Flow Sensor 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"
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