ND-18-0322, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.02.1 (Index Number 522)
| ML18078A034 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/16/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ITAAC 2.5.02.02.i, ND-18-0322 | |
| Download: ML18078A034 (14) | |
Text
hk. Southern Nuclear mar 16 2018 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com ND-18-0322 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 2.5.02.02.1 [Index Number 5221 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern NuclearOperating Company hereby notifies the NRC that as of March 1, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.02.02.1
[Index Number 522] has not been completed greaterthan225-days prior to initial fuel load. The Enclosure describes the planfor completing this ITAAC. Southern NuclearOperating Company will, at a laterdate, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.
This notification is informed bythe guidance described in NEI 08-01, Industry Guideline forthe 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, oranalyses 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 supportthe 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. Yo>
Regulatory Affairs Director Vogtie 3 &4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.02.1 [Index Number 522]
MJY/PGL/amw
U.S. Nuclear Regulatory Commission ND-18-0322 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. Vox Mr. D. L. Fulton Mr. J. B. Klecha 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 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 Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0322 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. 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., CDS Associates, Inc.
Mr. 8. Roetger, Georgia PublicService Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 1 of 11 Southern Nuclear Operating Company ND-18-0322 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.02.1 [Index Number 522]
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 2 of 11 ITAAC Statement Design Commitment
- 2. The seismic Category I equipment, identified in Table 2.5.2-1, can withstand seismic design basis loads without loss of safety function.
- 3. The Class 1E equipment, identified in Table 2.5.2-1, has electrical surge withstand capability (SWC), and can withstand the electromagnetic interference (EMI), radio frequency interference (RFI), and electrostatic discharge (ESD) 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.
- 4. The Class 1E equipment, identified in Table 2.5.2-1, can withstand the room ambient temperature, humidity, pressure, and mechanical vibration conditions that would exist before, during, and following a design basis accidentwithout loss ofsafety function forthe time required to perform the safety function.
Inspections. Tests. Analvses i) Inspection will be performed toverify thattheseismic Category Iequipment identified in Table 2.5.2-1 is located on the Nuclear Island.
ii) Type tests, analyses, ora combination of type tests and analysesof seismic Category I equipment will be performed.
ill) Inspection will be performed for the existence of a report verifying thattheas-built equipment including anchorage isseismically bounded bythe tested oranalyzed conditions.
Type tests, analyses, ora combination of type testsand analyses will be performed on the equipment.
Type tests, analyses, ora combination of type tests and analyses will be performed on the Class 1E equipment identified inTable 2.5.2-1.
Acceptance Criteria i) The seismic Category Iequipment identified in Table 2.5.2-1 islocated on the Nuclear Island.
ii) Areport exists and concludes that theseismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function.
iii) Areport exists and concludes that the as-built equipment including anchorage isseismically bounded by the tested or analyzed conditions.
Areport exists and concludes thatthe Class IE equipment identified in Table 2.5.2-1 can withstand the SWC, EMI, RFI, and ESD conditions that would existbefore, during, and following a design basis accident without loss of safety function for the time required toperform the safety function.
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 3 of 11 A report exists and concludes that the Class 1E equipment identified in Table 2.5.2-1 can withstand the room ambient temperature, humidity, pressure, and mechanical vibration 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.
ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Protection and Safety Monitoring System (PMS) equipment identified as seismic CategoryIor Class 1E in the Combined License (COL) Appendix C, Table2.5.2-1 (theTable) is designed and constructed in accordance with applicable requirements.
h The seismic Cateoorv I eouioment identified in Table 2.5.2-1 is located on the Nuclear Island.
To assure that seismic Category Iequipment can withstand seismic design basis loads without lossofsafety function, all the equipment in the Table is designed to be located ontheseismic Category INuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection isconducted of the PMS to confirm the satisfactory installation ofthe seismically qualified equipment. The inspection includes verification of equipment make/model/serial number andverification of equipment location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment Adocumentthe results ofthe inspection and concludethat the seismic Category I equipment is located on the NuclearIsland.
ih A reoort exists and concludes that the seismic Cateoorv Ieouioment can withstand seismic desion basis loads without loss of safetv function.
Seismic Category Iequipment in theTable requires type tests and/or analyses todemonstrate structural integrity and operability. 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 3). 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 toqualify API000 safety-related equipment isprovided in theUpdated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 4). The EG Reports (Reference 5) identified in Attachment Acontain applicable test reports andassociated documentation andconclude that the seismic Category Iequipment can withstand seismic design basis loads without loss of safety function.
iiil A report exists and concludes that the as-built eouiomentincludino anchorage is seismicallv bounded bv the tested or analvzed conditions.
An inspection (Reference 1) isconducted toconfirm thesatisfactory installation of the seismically qualified equipment in theTable. The inspection verifies theequipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, andelectrical andother interfaces. The documentation of installed configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 4 of 11 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 5) 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, includinganchorage, are seismically bounded by the tested or analyzed conditions, IEEEStandard 344-1987 (Reference 3) and NRC Regulatory Guide (RG) 1.100 (Reference 6).
A report exists and concludes that the Class IE eouioment identified in Table 2.5.2-1 can withstand the SWC. EMI. RFI. and ESP conditions that would exist before, during, and following a design basis accident without loss of safetv function for the time reouired to perform the safetv function.
The Class IE equipment in the Table is qualified by a combination oftype testing and analysis inaccordance with RG 1.180 (Reference 7) and industry standards. The specificqualification method (i.e., type testing, analysis, or combination) used foreach piece ofequipmentinthe Table is identified inAttachment A. The baseline Military Standard ("MIL-STD") program is used in its entiretyfor emissions testing as described inAttachment B, and shows the Electromagnetic Compatibility (EMC) type test and category(SWC, EMI, RFI or ESD), the test standard, and the application. The alternate International Electrotechnical Commission (lEC) program is used in itsentirety for susceptibility testing as described in similar fashion in Attachment C. The testingdescribed in the attachments is a complete set forthis ITAAC in accordance with RG 1.180 and the ESD test requirement, and compliant results of these tests combinedwith the location analysis indicatethat the ITAAC acceptance criteriais met.
The results ofthe tests and analysis are documented in the EQ Reports (Reference 5) identified inAttachmentA and conclude that the Class IE equipment identified inthe Table has SWC and can withstandthe EMI, RFI, and ESD conditions that would exist before, during, and following a design basis accident without lossofsafety function for the time required to perform the safety function.
A reoort exists and concludes that the Class IE equipment identified in Table 2.5.2-1 can withstand the room ambient temperature, humiditv. pressure, and mechanical vibration conditions that would exist before, durino. and followino a design basis accident without loss of safetv function for the time reouired to perform the safetv function.
The Class IE equipment identified in theTable isqualified by a combination oftype testing and analysis in accordance with IEEE Standard 323-1974 (Reference 8)and RG 1.89 (Reference 9) to meet the requirements of 10 CFR50.49. Thisdemonstrates that the equipmentcan withstand the roomambienttemperature, humidity, pressure, and mechanicalvibration conditions thatwould exist before, during, and following a design basis accident without loss of safety function for thetime required to perform thesafety function. Additional information about the methods used to qualify API000 safety-related equipment is provided in UFSAR Appendix 3D (Reference 4).
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 5 of 11 EQ Reports (Reference 5) Identified in Attachment A contain applicable test reports and associated documentation and conclude the equipment identified in the Table can withstand the room ambient temperature, humidity, pressure, and mechanical vibration 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.
Together, these reports (References 2 and 5) provide evidence that the ITAAC Acceptance Criteria requirements are met:
The seismic Category Iequipment identified inTable 2.5.2-1 is located on the Nuclear Island; A reportexists and concludes that the seismic Category Iequipmentcan withstand seismic design basis loads without loss of safety function; A reportexists and concludes that the as-built equipmentincluding anchorage is seismically bounded by the tested or analyzed conditions; A report exists and concludes that the Class 1E equipmentidentified in Table 2.5.2-1 can withstand the SWC, EMI, RFI, and ESD conditions that would exist before, during, and following a design basis accidentwithout loss ofsafetyfunction forthe time required to perform the safety function; and A reportexists and concludes that the Class 1E equipmentidentified in Table 2.5.2-1 can withstand the room ambient temperature, humidity, pressure, and mechanical vibration conditions that would exist before, during, and following a design basis accident without loss ofsafety function forthe time required to perform the safety function.
References 2 and 5 are available for NRCinspection as part of the Unit 3 and Unit 4 ITAAC 2.5.02.02.1 Completion Packages (References 10 and 11, respectively).
List of ITAAC Findings Inaccordance with plant procedures for ITAAC completion. Southern NuclearOperating Company (SNC) performed a review ofall ITAAC findings pertaining to the subject ITAAC and associated correctiveactions. Thisfinding review, which included now-consolidated ITAAC Indexes 523, 524, 525, and 526, found the following Noticesof Nonconformance (NGN) associated with this ITAAC:
- 1) 99900404/2015-204-02 (closed)
- 2) 99900404/2015-204-03 (closed)
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 6 of 11 References (available for NRG inspection) 1.
ND-xx-xx-001, "EQ Walkdown ITAAC Guideline" 2.
EQ As-Built Reconciliation Reports (EQRR) as identified in Attacfiment Afor Units 3 and 4 3.
IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"
- 4. Vogtle 3&4 Updated Final SafetyAnalysis Report Appendix 3D, "Methodology for Qualifying API 000 Safety-Related Electricaland Mechanical Equipment"
- 5. EquipmentQualification (EQ) Reports as identified inAttachmentA
- 6. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"
- 7. Regulatory Guide 1.180, Rev. 1, "Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems" 8.
IEEE Standard 323-1974, "IEEEStandard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations"
- 9. Regulatory Guide 1.89, Rev. 1,"Environmental Qualification of Certain Electric Equipment Importantto Safety for Nuclear Power Plants" 10.2.5.02.02.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.5.02.02.1 [Index Number 522]"
11.2.5.02.02.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.5.02.02.1 [Index Number 522]"
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 7 of 11 Attachment A System: Protection and Safety Monitoring System (PMS)
Equipment Name^
Seismic Cat. 1+
Class 1 El Qual. For Harsh Envir.^
Type of Qual.
EG Reports (Reference 5)
As-Built EQRR (Reference 2)^
PMS Cabinets, Division A Yes Yes/No Type Test &
Analysis APP-PMS-VBR-002 APP-PMS-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX PMS Cabinets, Division B Yes Yes/No Type Test &
Analysis APP-PMS-VBR-002 APP-PMS-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX PMS Cabinets, Division C Yes Yes/No Type Test &
Analysis APP-PMS-VBR-002 APP-PMS-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX PMS Cabinets, Division D Yes Yes/No Type Test &
Analysis APP-PMS-VBR-002 APP-PMS-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX Reactor Trip Switchgear, Division A Yes Yes/No Type Test &
Analysis APP-JY50-VBR-002 APP-JY50-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX Reactor Trip Switchgear, Division B Yes Yes/No Type Test&
Analysis APP-JY50-VBR-002 APP-JY50-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX Reactor Trip Switchgear, Division C Yes Yes/No Type Test &
Analysis APP-JY50-VBR-002 APP-JY50-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX Reactor Trip Switchgear, Division D Yes Yes/No Type Test &
Analysis APP-JY50-VBR-002 APP-JY50-VBR-003 2.5.02.02.i-U3-EQRR-PCDXXX MCR/RSW Transfer Panels Yes Yes/No Type Test &
Analysis APP-JW03-VBR-001 APP-JW03-VBR-002 2.5.02.02.i-U3-EQRR-PCDXXX MCR Safety-related Display, Division A Yes Yes/No Type Test &
Analysis APP-OCS-VBR-006 APP-OCS-VBR-008 2.5.02.02.i-U3-EQRR-PCDXXX MCR Safety-related Display, Division B Yes Yes/No Type Test &
Analysis APP-OCS-VBR-006 APP-OCS-VBR-008 2.5.02.02.i-U3-EQRR-PCDXXX MCR Safety-related Display, Division C Yes Yes/No Type Test &
Analysis APP-OCS-VBR-006 APP-OCS-VBR-008 2.5.02.02.i-U3-EQRR-PCDXXX MCR Safety-related Display, Division D Yes Yes/No Type Test &
Analysis APP-OCS-VBR-006 APP-OCS-VBR-008 2.5.02.02.i-U3-EQRR-PCDXXX MCR Safety-related Controls Yes Yes/No Type Test &
Analysis APP-OCS-VBR-006 APP-OCS-VBR-008 2.5.02.02.i-U3-EQRR-PCDXXX Notes:
Excerpt from COL Appendix C Table 2.5.2-1
- 1. The Unit 4 As-Built EQRR are numbered "2.5.02.02.i-U4-EQRR-PCDXXX"
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 8 of 11 Attachment B RMSApplicable SWO Test Standards, Baseline (MIL-STD) Emissions Testing Program EMC Type Test Test Standard Application Conducted Emissions, Low Frequency (EMI/ RFI)
MIL-STD-461E (CE101) "Requirements for the Control of Electromagnetic Interference Characteristics of Subsystems and Equipment," U.S.
Department of Defense, August 1999.
Reactor Trip Switchgear Power Leads (Note 1)
Conducted Emissions, High Frequency (EMI/ RFI)
MIL-STD-461E (CE102), "Requirements for the Control of Electromagnetic Interference Characteristics of Subsystems and Equipment," U.S.
Department of Defense, August 1999.
PMS Cabinet Power Leads Reactor Trip Switchgear Power Leads Main Control Room (MCR)
Safety-related (SR) Display &
Control Power Leads Radiated Emissions, Magnetic Field (EMI/RFI)
MIL-STD-461E (RE101), "Requirements for the Control of Electromagnetic Interference Characteristics of Subsystems and Equipment," U.S.
Department of Defense, August 1999.
PMS Cabinet Reactor Trip Switchgear MCR SR Display &Control Radiated Emissions, Electric Field (EMI/ RFI)
MIL-STD-461E (RE102), "Requirements for the Control of Electromagnetic Interference Characteristics of Subsystems and Equipment," U.S.
Department of Defense, August 1999.
PMS Cabinet Reactor Trip Switchgear MCR SR Display & Control
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 9 of 11 RMS Applicable SWC Test Standards, Alternate (IEC) Susceptibility Testing Program EMC Type Test Test Standard Application Conducted Susceptibility, Low Frequency, (EMI/ RFI) lEC 61000-4-16, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 16: Test for Immunityto Conducted, Common Mode Disturbances in the Frequency Range of 0 Hzto 150 kHz," 1998.
PMS Cabinet Power &Signal Leads Reactor Trip Switchgear Power &
Signal Leads Main Control Room/Remote Shutdown Workstation (MCR/RSW)
Transfer Panel Signal Leads MCR SR Display &Control Power &
Signal Leads (Note 1)
Conducted Susceptibility, Low Frequency, (EMI/ RFI) lEC 61000-4-13, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 13:
Harmonics and Interharmonics Including Mains Signaling at AC Power Port, Low Frequency Immunity Tests," 2002.
PMS Cabinet Power Leads MCR SR Display & Control Power Leads Conducted Susceptibility, High Frequency (EMI/ RFI) lEC 61000-4-6, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 6:
Immunityto Conducted Disturbances, Induced by Radio-Frequency Fields," 1996.
PMS Cabinet Power &Signal Leads Reactor Trip Switchgear Power &
Signal Leads MCR/RSW Transfer Panel Signal Leads MCR SR Display &Control Power &
Signal Leads Radiated Susceptibility, Magnetic Field, (EMI/ RFI) lEC 61000-4-8, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 8:
Power Frequency Magnetic Field Immunity Test," 1993. (Note 2)
PMS Cabinet Reactor Trip Switchgear MCR SR Display & Control Radiated Susceptibility, Magnetic Field, (EMI/ RFI) lEC 61000-4-9, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 9:
Power Frequency Magnetic Field Immunity Test," 1993.
PMS Cabinet Reactor Trip Switchgear MCR SR Display & Control Radiated Susceptibility, Magnetic Field, (EMI/ RFI) lEC 61000-4-10, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 10:
Damped Oscillatory Magnetic Field Immunity Test," 1993.
PMS Cabinet Reactor Trip Switchgear MCR SR Display & Control
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 10 of 11 EMC Type Test Test Standard Application Radiated Susceptibility, Electrical Field, (EMI/ RFI) lEC 61000-4-3, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 3:
Radiated, Radio-Frequency, Electromagnetic Field ImmunityTest,"
1995.
PMS Cabinet Reactor Trip Switchgear MCR/RSW Transfer Panel MCR SR Display & Control Radiated Susceptibility, Electrical Field, (EMI/ RFI)
(Note 2)
MIL-STD-461E (RS103), "Requirements for the Control of Electromagnetic Interference Characteristics of Subsystems and Equipment," U.S. Department of Defense, August 1999.
PMS Cabinet Reactor Trip Switchgear MCR/RSW Transfer Panel MCR SR Display & Control Electrical Fast Transient (SWO) lEC 61000-4-4, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 4:
Electrical Fast Transient/Burst Immunity Test," 1995.
PMS Cabinet Power & Signal Leads Reactor Trip Switchgear Power &
Signal Leads MCR/RSW Transfer Panel Signal Leads MCR SR Display &Control Power &
Signal Leads
- Surge, Combination Wave (SWC) lEC 61000-4-5, "Electromagnetic Compatibility (EMC), Part 4; Testing and Measurement Techniques, Section 5:
Surge ImmunityTest," 1995 &2005.
PMS Cabinet Power &Signal Leads Reactor Trip Switchgear Power &
Signal Leads MCR/RSW Transfer Panel Signal Leads MCR SR Display &Control Power &
Signal Leads Surge, Ring Wave (EMI/ RFI) lEC 61000-4-12, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 12:
OscillatoryWaves Immunity Test," 1995 &
2006.
PMS Cabinet Power &Signal Leads Reactor Trip Switchgear Power &
Signal Leads MCR/RSW Transfer Panel Signal Leads MCR SR Display & Control Power &
Signal Leads
U.S. Nuclear Regulatory Commission ND-18-0322 Enclosure Page 11 of 11 EMC Type Test Test Standard Application Electrostatic Discharge Immunity (ESD)
(Note 3) lEC 61000-4-2, "Electromagnetic Compatibility (EMC), Part 4: Testing and Measurement Techniques, Section 2:
Electrostatic Discharge Immunity Test,"
2008.
PMS Cabinet Reactor Trip Switchgear MCR/RSW Transfer Panel MCR SR Display & Control Notes:
- 1. Voltage Total Harmonic Distortion (VTHD) tests were performed to support exemption ofthe following equipment from CE101 tests under Regulatory Guide 1.180 Position 3.1.
a.
MCR SR Display &Control Power Leads
- 2. MIL-STD-461E RSI03 (Radiated susceptibility, electricfield) test is used to extend the alternative susceptibility test range ofthe radiatedelectrical fields susceptibility above 1 GHz, as indicated in RG 1.180 Position 6.