ND-18-0258, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.06.05a.i (Index Number 361)

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Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.06.05a.i (Index Number 361)
ML18054A426
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 02/22/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.3.06.05a.i, ND-18-0258
Download: ML18054A426 (12)
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Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 hk. Southern Nuclear Vogtie 3 & 4 706-848-6459 tei 410-474-8587 ceii FEB 2 2 201B myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0258 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 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 2.3.06.05a.i llndex Number 3611 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, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.06.05a.i

[Index Number361] 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 Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.05a.i [Index Number 361]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0258 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. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. 0. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc; Nuclear Reouiatorv 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 Oaiethoroe Power Corooration Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0258 Page 3 of 3 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. 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 Pubiic Service Commission Ms. 8. W. Kernizan, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-18-0258 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.05a.i [Index Number 361]

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 2 of 9 ITAAC Statement Design Commitment 5.a) The seismic Category I equipment identified in Table 2.3.6-1 can withstand seismic design basis loads without loss of safety function.

7.a) The Class 1E equipment identified in Table 2.3.6-1 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 in Table 2.3.6-1 is 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.

ill) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the 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 1Eequipment and the associated wiring, cables, and terminations located in a harsh environment.

Acceptance Criteria i) The seismic Category Iequipment identified in Table 2.3.6-1 islocated 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 is seismically bounded by the tested or analyzed conditions.

i) Areport exists and concludes that the Class 1E equipment identified in Table 2.3.6-1 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 thetime 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 2.3.6-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 3 of 9 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Normal Residual Heat Removal System (RNS) equipment identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 2.3.6-1 (the Table) is designed and constructed in accordance with applicable requirements.

if The seismic Cateaorv I eauioment identified in Table 2.3.6-1 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 RNS 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 EQ 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.

iif A report exists and concludes that the seismic Cateaorv I eauioment can withstand seismic desian basis loads without loss of safetv 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, as well as other passive seismic Category I mechanical equipment, 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 1E) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). This equipment includes safety-related active valve accessories such as electric actuators, position switches, pilot solenoid valves and electrical connector assemblies. The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment in the Table is identified in Attachment A.

Additional information about the methods used to qualify API 000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6).

The EQ Reports (Reference 7) identified in Attachment 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.

iih A reoort exists and concludes that the as-built equipment including anchoraoe is seismicallv bounded bv the tested or analvzed conditions.

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

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 4 of 9 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-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 Iequipment listed in the Table, including anchorage, is seismically bounded bythe tested or analyzed conditions, IEEE Standard 344-1987 (Reference 5) and NRC Regulatory Guide (RG) 1.100 (Reference 8).

\) A report exists and concludes that the Class 1E eouipment identified in Table 2.3.6-1 as beina Qualified for a harsh environment can withstand the environmental conditions that would exist before, durino. and followinc a desion 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 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 10CFR 50.49. Type testing of safety-related equipment meetsthe requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment Aidentifies the EQ program and specific qualification method for each piece of safety-related mechanical 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 A contain applicable test reports and associated documentation and conclude thatthe 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.

W) A report exists and concludes that the as-built Class 1E eouioment and the associated wiring, cables, and terminations identified in Table 2.3.6-1 as beina qualified for a harsh environment are bounded bv tvoe tests, analvses. or a combination of tvpe tests and analvses.

An inspection (Reference 1) isconducted of the RNS to confirm thesatisfactory installation of the Class 1E equipment 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 conditions for the zone (Attachment A) in which the equipment is mounted are bounded by thetestedand/or analyzed conditions. It also documentsthe 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 by the qualified configuration and IEEE Standard 323-1974 (Reference 9).

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 5 of 9 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 2.3.6-1 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-built equipment including anchorage is seismically bounded by the tested or analyzed conditions;
  • A report exists and concludes that the Class 1E equipment identified in Table 2.3.6-1 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-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.3.6-1 as being qualifiedfor 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 2.3.06.05a.i Completion Packages (References 11 and 12, respectively).

List of iTAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 362, 363, 366, and 367, found no relevant ITAAC findings associated with this ITAAC.

References favallable for NRC inspection)

1. ND-xx-xx-001, "EG Walkdown ITAAC Guideline"
2. EG As-Built Reconciliation Reports (EQRR) 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-18-0258 Enclosure Page 6 of 9

6. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment"
7. Equipment Qualification (EQ) Reports as identified in Attachment A
8. Regulatory Guide 1.100, Rev. 2, "SeismicQualification 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 Importantto Safety for Nuclear Power Plants" 11.2.3.06.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.3.06.05a.i [Index Number 361]"

12.2.3.06.05a.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.3.06.05a.i [Index Number 361]"

13. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 7 of 9 Attachment A System: Normal Residual Heat Removal System (RNS)

CiasslE/

Seismic Quai. For Envir. Envir Qual Type of EG Reports As-Buiit EORR Equipment Name ^ Tag No.

  • Program (Reference 7) (Reference 2)

Cat. i Harsh Zone ^ Quai.

Envir.*

RNS Pump A (Pressure 2.3.06.05a.l-U3-EQRR-RNS-MP-01A Yes -/- NA NA Analysis APP-MP08-VDR-001 Boundary) PCDXXX RNS Pump B (Pressure 2.3.06.05a.l-U3-EQRR-RNS-MP-01B Yes -/- NA NA Analysis APP-MP08-VDR-001 Boundary) PCDXXX RNS Heat Exchanger A 2.3.06.05a.l-U3-EQRR-RNS-ME-01A Yes -/- NA NA Analysis APP-ME1C-VDR-001 (Tube Side) PCDXXX RNS Heat Exchanger B 2.3.06.05a.l-U3-EQRR-RNS-ME-01B Yes -/- NA NA Analysis APP-ME1C-VDR-001 (Tube Side) PCDXXX RCS Inner Hot Leg 2.3.06.05a.l-U3-EQRR-Type Test & APP-PV01-VBR-012/

Suction Motor-operated RNS-PL-V001A Yes YesA'es 1 ME*S PCDXXX Analysis APP-PV01-VBR-011 Isolation Valve RCS Inner Hot Leg 2.3.06.05a.l-U3-EQRR-Type Test & APP-PV01-VBR-012/

Suction Motor-operated RNS-PL-V001B Yes YesA^es 1 M E*S PCDXXX Analysis APP-PV01-VBR-011 Isolation Valve RCS Outer Hot Leg 2.3.06.05a.l-U3-EQRR-Type Test & APP-PV01-VBR-012/

Suction Motor-operated RNS-PL-V002A Yes YesA'es 1 ME*S PCDXXX Analysis APP-PV01-VBR-011 Isolation Valve RCS Outer Hot Leg 2.3.06.05a.l-U3-EQRR-Type Test& APP-PV01-VBR-012/

Suction Motor-operated RNS-PL-V002B Yes YesA'es 1 M E* S PCDXXX Analysis APP-PV01-VBR-011 Isolation Valve RCS Pressure Boundary 2.3.06.05a.l-U3-EQRR-APP-PV02-VBR-012/

Thermal Relief Check RNS-PL-V003A Yes -/- NA NA Analysis PCDXXX APP-PV02-VBR-011 Valve RCS Pressure Boundary 2.3.06.05a.l-U3-EQRR-APP-PV02-VBR-012/

Thermal Relief Check RNS-PL-V003B Yes -/- NA NA Analysis PCDXXX APP-PV02-VBR-011 Valve RNS Discharge Motor- 2.3.06.05a.l-U3-EQRR-Type Test & APP-PV01-VBR-012/

operated Containment RNS-PL-V011 Yes Yes/No NA NA PCDXXX Analysis APP-PV01-VBR-011 Isolation Valve

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 8 of 9 CiasslE/

Seismic Quai. For Envir. Envir Quai Type of EG Reports As-Buiit EQRR Equipment Name ^ Tag No. ^ Harsh Zone ^ Program ^ Quai. (Reference 7) (Reference 2) ^

Cat. i +

Envir.+ 3 RNS Discharge Type Test& APP-PV02-VBR-010/ 2.3.06.05a.i-U3-EQRR-Containment Isolation RNS-PL-V012 Yes -/- NA NA Analysis APP-PV02-VBR-009 PCDXXX Test Connection RNS Discharge Header APP-PV03-VBR-014/ 2.3.06.05a.i-U3-EQRR-Containment isolation RNS-PL-V013 Yes -/- NA NA Analysis APP-PV03-VBR-013 PCDXXX Check Valve RNS Discharge RCS Type Test& APP-PV03-VBR-012/ 2.3.06.05a.i-U3-EQRR-Pressure Boundary RNS-PL-V015A Yes -/- NA NA Analysis APP-PV03-VBR-011 PCDXXX Check Valve RNS Discharge RCS Type Test& APP-PV03-VBR-012/ 2.3.06.05a.i-U3-EQRR-Pressure Boundary RNS-PL-V015B Yes -/- NA NA Analysis APP-PV03-VBR-011 PCDXXX Check Valve RNS Discharge RCS APP-PV03-VBR-014/ 2.3.06.05a.i-U3-EQRR-Pressure Boundary RNS-PL-V017A Yes -/- NA NA Analysis APP-PV03-VBR-013 PCDXXX Check Valve RNS Discharge RCS APP-PV03-VBR-014/ 2.3.06.05a.i-U3-EQRR-Pressure Boundary RNS-PL-V017B Yes -/- NA NA Analysis APP-PV03-VBR-013 PCDXXX Check Valve RNS Hot Leg Suction Type Test& APP-PV16-VBR-001 / 2.3.06.05a.i-U3-EQRR-RNS-PL-V020 Yes -/- NA NA Pressure Relief Valve Analysis APP-PV16-VBR-002 PCDXXX RNS Hot Leg Suction Type Test& APP-PV16-VBR-001 / 2.3.06.05a.i-U3-EQRR-RNS-PL-V021 Yes -/- NA NA Pressure Relief Valve Analysis APP-PV16-VBR-002 PCDXXX RNS Suction Header Motor-operated Type Test& APP-PV01-VBR-012/ 2.3.06.05a.i-U3-EQRR-RNS-PL-V022 Yes Yes/No NA NA Containment Isolation Analysis APP-PV01-VBR-011 PCDXXX Valve RNS Suction from Type Test & APP-PV01-VBR-012/ 2.3.06.05a.i-U3-EQRR-IRWST Motor-operated RNS-PL-V023 Yes YesT/es 1 ME*S Analysis APP-PV01-VBR-011 PCDXXX Isolation Valve RNS Discharge to Type Test & APP-PV01-VBR-012/ 2.3.06.05a.i-U3-EQRR-IRWST Motor-operated RNS-PL-V024 Yes -/- NA NA Analysis APP-PV01-VBR-011 PCDXXX Isolation Valve

U.S. Nuclear Regulatory Commission ND-18-0258 Enclosure Page 9 of 9 Ciass IE/

Seismic Qual. For Envir. Envir Quai Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No.

  • Cat. 1 ^ Harsh Zone ^ Program ^ Quai. (Reference 7) (Reference 2)"

Envir.*

RNS Pump Discharge Type Test & APP-PV16-VBR-001 / 2.3.06.05a.i-U3-EQRR-RNS-PL-V045 Yes -/- NA NA Relief Analysis APP-PV16-VBR-002 PCDXXX RNS Suction from Cask Type Test & APP-PV01-VBR-012/ 2.3.06.05a.i-U3-EQRR-Loading Pit Motor- RNS-PL-V055 Yes No/No NA NA Analysis APP-PV01-VBR-011 PCDXXX operated Isolation Valve RNS Suction from Cask APP-PV03-VBR-014/ 2.3.06.05a.i-U3-EQRR-RNS-PL-V056 Yes -/- NA NA Analysis Loading Pit Check Valve APP-PV03-VBR-013 PCDXXX RNS Pump Miniflow Air- Type Test & APP-PV14-VBR-002/ 2.3.06.05a.i-U3-EQRR-RNS-PL-V057A Yes No/No NA NA Operated Isolation Valve Analysis APP-PV14-VBR-001 PCDXXX RNS Pump Miniflow Air- Type Test & APP-PV14-VBR-002 / 2.3.06.05a.i-U3-EQRR-RNS-PL-V057B Yes No/No NA NA Operated Isolation Valve Analysis APP-PV14-VBR-001 PCDXXX RNS Return from Chemical and Volume Type Test & APP-PV14-VBR-002/ 2.3.06.05a.i-U3-EQRR-Control System (CVS) RNS-PL-V061 Yes Yes/Yes 1 ME*S Analysis APP-PV14-VBR-001 PCDXXX' Containment Isolation Valve Notes:

+ Excerpt from COL Appendix C Table 2.3.6-1

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 "2.3.06.05a.i-U4-EQRR-PCDXXX"
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