ND-18-0266, Voglte, Units 3 and 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.05 (Index Number 291)
ML18057A434 | |
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 2.3.02.05.i, ND-18-0266 | |
Download: ML18057A434 (12) | |
Text
Michael J. Vox 7825 River Road
^ Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 WayneslDoro, GA 30830 706-848-6459 tel 410-474-8587 cell FEB 2 3 2018 myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0266 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 2.3.02.05.1 [Index Number 291]
Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 23, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.02.05.1
[Index Number 291] 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 contactTom Petrak at 706-848-1575.
Respectfully submitted.
Michael J. Vox Regulatory Affairs Director Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.05.1 [Index Number 291]
MJY/PGUamw
U.S. Nuclear Regulatory Commission ND-18-0266 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Companv 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 Reoulatorv Commission Mr. W. Jones (w/o enclosures)
Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. 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 Oolethoroe Power Corporation Mr. R. B. Brinkman MunlciDal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0266 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse 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. 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., CDS Associates, inc.
Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-18-0266 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.05.1 [Index Number 291]
U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 2 of 9 ITAAC Statement Design Commitment
- 5. The seismic Category I equipment identified in Table 2.3.2-1 can withstand seismic design basis loads without loss of safety function.
6.a) The Class 1E equipment identified in Table 2.3.2-1 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 safety function for the time required to perform the safety function.
Insoections. Tests. Analvses i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 2.3.2-1 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 thatthe 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 2.3.2-1 is located on the Nuclear Island.
ii) Areport exists and concludes that the seismic Category Iequipment can withstand seismic design basis dynamic loads without loss of safetyfunction.
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 2.3.2-1 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 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, andterminations identified in Table 2.3.2-1 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-18-0266 Enclosure Page 3 of 9 ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Chemical and Volume Control System (CVS) equipment identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 2.3.2-1 (the Table) is designed and constructed in accordance with applicable requirements.
i) The seismic Category I eouioment identified in Table 2.3.2-1 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 EquipmentQualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the CVS 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 Cateoorv I eauioment can withstand seismic desion basis dvnamic 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 ofthe 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 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 API000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6).
The EG Reports (Reference 7) identified in Attachment Acontain 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 reoort exists and concludes that the as-built eouioment includino anchorace 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-18-0266 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) identifythe 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 identifiesthe EQRR (Reference 2) completed to verify that the as-built seismic Category Iequipment listed in the Table, including anchorage, are seismically bounded bythe tested or analyzed conditions, IEEE Standard 344-1987 (Reference 5), and f^RC Regulatory Guide (RG) 1.100 (Reference 8).
i1 A reoort exists and concludes that the Class 1E eouioment identified in Table 2.3.2-1 as being Qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and followino 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 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 meetsthe requirements of 10CFR 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 Acontain applicable test reports and associated documentation and conclude that the equipmentcan 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.
iil A report exists and concludes that the as-built Class 1E eouioment and the associated wiring, cables, and terminations identified in Table 2.3.2-1 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 CVS 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 confirmsthat 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 equipment and the associated wiring, cables, and terminations are bounded by thequalified configuration and IEEE Standard 323-1974 (Reference 9).
U.S. Nuclear Regulatory Commission ND-18-0266 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 2.3.2-1 is located on the Nuclear Island;
- A report exists and concludes that the seismic Category I equipment can withstand seismic design basis dynamic 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 2.3.2-1 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; and
- A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.3.2-1 as being qualified for a harsh environmentare 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 2.3.02.05.i Completion Packages (References 11 and 12, respectively).
List of ITAAC Findings In accordance with plantprocedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.
This review, which included nowconsolidated ITAAC Indexes 292, 293, 294 and 295, found the following relevant ITAAC findings associated with this ITAAC:
- 1) Notice of Nonconformance (NGN) 99901412/2012-201 -02 (Closed)
References ^available for NRC inspection)
- 1. ND-xx-xx-001, "EG Walkdown ITAAC Guideline"
- 2. EG As-Built Reconciliation Reports (EORR) as identified in Attachment Afor Units 3 and 4
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 Equipmentfor Nuclear Power Generating Stations"
U.S. Nuclear Regulatory Commission ND-18-0266 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, "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" 11.2.3.02.05.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.3.02.05.i [Index Number 291]"
12.2.3.02.05.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.3.02.05.1 [Index Number 291]"
- 13. NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 7 of 9 Attachment A System; Chemical and Volume Control System (CVS)
Ciass 1E/
Seismic Quai. for Envir. Envir Quai Type of EQ Reports As-Buiit EQRR Equipment Name ^ Tag No.
- Program^ Quai. (Reference 7) (Reference 2)
Cat. i ^ Harsh Zone^
Envir.+ 3 RCS Purification Motor- Type Testing APP-PV01-VBR-012/ 2.3.02.05.i-U3-EQRR-CVS-PL-V001 Yes YesA'es 1 M*ES operated Isolation Valve & Analysis APP-PV01-VBR-011 PCDXXX-RevO RCS Purification Motor- Type Testing APP-PV01-VBR-012/ 2.3.02.05.i-U3-EQRR-CVS-PL-V002 Yes YesA'es 1 M*ES operated Isolation Valve & Analysis APP-PV01-VBR-011 PCDXXX-Rev 0 RCS Purification Motor- Type Testing APP-PV01-VBR-014/ 2.3.02.05.i-U3-EQRR-CVS-PL-V003 Yes YesA'es 1 M*ES operated Isolation Valve & Analysis APP-PV01-VBR-013 PCDXXX-Rev 0 CVS Resin Flush Line Type Testing APP-PV10-VBR-008/ 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V040 Yes -/- NA NA
& Analysis APP-PV10-VBR-007 PCDXXX-Rev 0 Valve CVS Resin Flush Line Type Testing APP-PV10-VBR-008 / 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V041 Yes -/- NA NA
& Analysis APP-PV10-VBR-007 PCDXXX-Rev 0 Valve CVS Demineralizer Resin Flush Line Containment Type Testing APP-PV16-VBR-002 / 2.3.02.05.i-U3-EQRR-CVS-PL-V042 Yes -/- NA NA Isolation Thermal Relief & Analysis APP-PV16-VBR-001 PCDXXX-Rev 0 Valve CVS Letdown Type Testing APP-PV14-VBR-002 / 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V045 Yes YesA'es 1 M* E S
& Analysis APP-PV14-VBR-001 PCDXXX-Rev 0 Valve CVS Letdown Type Testing APP-PV14-VBR-002 / 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V047 Yes Yes/No NA NA
& Analysis APP-PV14-VBR-001 PCDXXX-Rev 0 Valve CVS Letdown Line Type Testing APP-PV16-VBR-002 / 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V058 Yes -/- NA NA
& Analysis APP-PV16-VBR-001 PCDXXX-Rev 0 Thermal Relief Valve CVS Makeup Return Line Type Testing APP-PV02-VBR-012/ 2.3.02.05.i-U3-EQRR-CVS-PL-V067 Yes -/- NA NA Bypass Check Valve & Analysis APP-PV02-VBR-011 PCDXXX-Rev 0
U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 8 of 9 Class 1E/
Seismic Qua!, for Envir. Envir Qual Type of EG Reports As-Built EORR Equipment Name ^ Tag No.
- Harsh Zone^ Program^ Qual. (Reference 7) (Reference 2)
Cat. 1 ^
Envir.+
CVS Purification Return APP-PV03-VBR-014/ 2.3.02.05.i-U3-EQRR-Line Pressure Boundary CVS-PL-V080 Yes -/- NA NA Analysis APP-PV03-VBR-013 PCDXXX-Rev 0 Check Valve CVS Purification Return APP-PV14-VBR-190002 Type Testing 2.3.02.05.i-U3-EQRR-Line Pressure Boundary CVS-PL-V081 Yes -/- NA NA /
& Analysis PCDXXX-Rev 0 Isolation Check Valve APP-PV14-VBR-190001 CVS Purification Return APP-PV03-VBR-014 / 2.3.02.05.i-U3-EQRR-Line Pressure Boundary CVS-PL-V082 Yes -/- NA NA Analysis APP-PV03-VBR-013 PCDXXX-Rev 0 Check Valve CVS Auxiliary Pressurizer Type Testing APP-PV14-VBR-002 / 2.3.02.05.i-U3-EQRR-Spray Line Pressure CVS-PL-V084 Yes Yes/Yes 1 M*ES
& Anaiysis APP-PV14-VBR-001 PCDXXX-RevO Boundary Vaive CVS Auxiliary Pressurizer APP-PV02-VBR-012/ 2.3.02.05.i-U3-EQRR-Spray Line Pressure CVS-PL-V085 Yes -/- NA NA Analysis PCDXXX-Rev 0 APP-PV02-VBR-011 Boundary Check Valve CVS Makeup Line Type Testing APP-PV01-VBR-012/ 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V090 Yes Yes/No NA NA
& Analysis APP-PV01-VBR-011 PCDXXX-Rev 0 Motor-operated Valve CVS Makeup Line Type Testing APP-PV01-VBR-012/ 2.3.02.05.i-U3-EQRR-Containment isolation CVS-PL-V091 Yes YesA'es 1 M*ES
& Analysis APP-PV01-VBR-011 PCDXXX-Rev 0 Motor-operated Vaive CVS Zinc Injection Type Testing APP-PV14-VBR-002 / 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V092 Yes Yes/Yes 10 M*ES
& Analysis APP-PV14-VBR-001 PCDXXX-Rev 0 Valve ORC CVS Zinc injection Type Testing APP-PV14-VBR-002/ 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V094 Yes Yes / Yes 1 M*ES
& Analysis APP-PV14-VBR-001 PCDXXX-Rev 0 Valve IRC CVS Zinc Addition Line Type Testing APP-PV16-VBR-002/ 2.3.02.05.i-U3-EQRR-Ctmt Isol Thermal Relief CVS-PL-V098 Yes -/- NA NA
& Analysis APP-PV16-VBR-001 PCDXXX-Rev 0 Valve
U.S. Nuclear Regulatory Commission ND-18-0266 Enclosure Page 9 of 9 Class 1E/
Seismic Qual. for Envir. Envir Qual Type of EQ Reports As-Built EQRR Equipment Name ^ Tag No.
- Program^ Qual. (Reference 7) (Reference 2)
Cat. i ^ Harsh Zone^
Envir.+ 3 CVS Makeup Line APP-PV02-VBR-012 / 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V100 Yes -/- NA NA Analysis APP-PV02-VBR-011 PCDXXX-Rev 0 Thermal Relief Valve CVS Demineralized Type Testing APP-PV11-VBR-004/ 2.3.02.05.i-U3-EQRR-CVS-PL-V136A Yes Yes/No NA NA Water Isolation Valve & Analysis APP-PV11-VBR-003 PCDXXX-Rev 0 CVS Demineralized Type Testing APP-PV11-VBR-004/ 2.3.02.05.i-U3-EQRR-CVS-PL-V136B Yes Yes/No NA NA Water Isolation Valve & Analysis APP-PV11-VBR-003 PCDXXX-Rev 0 CVS Hydrogen Injection APP-PV02-VBR-017/ 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V217 Yes -/- NA NA Analysis APP-PV02-VBR-018 PCDXXX-Rev 0 Check Valve IRC CVS Hydrogen Injection Type Testing APP-PV14-VBR-002 / 2.3.02.05.i-U3-EQRR-Containment Isolation CVS-PL-V219 Yes YesA'es 10 M*ES
& Analysis APP-PV14-VBR-001 PCDXXX-Rev 0 Vaive ORC Notes:
+ Excerpt from COL Appendix C Table 2.3.2-1
- 1. See Table 3D.5-1 of UFSAR
- 2. E - Electrical Equipment Program (limit switch and the motor operator, squib operator, soienoid 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 "2.3.02.05.i-U4-EQRR-PCDXXX-Rev 0"