Regulatory guides are issued to describe and make available to the public such information as methods acceptable to the NRC staff for implementing specific parts

of the NRC’s regulations, techniques used by the staff in evaluating specific problems or postulated accidents, and data needed by the NRC staff in its review of

applications for permits and licenses. Regulatory guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions different

from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the

Commission.

This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all

times, and guides will be revised, as appropriate, to accommodate comments and to reflect new information or experience. Written comments may be submitted to the

Rules and Directives Branch, ADM, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 

Regulatory guides are issued in ten broad divisions: 1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting;

5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health; 9, Antitrust and Financial Review; and 10, General. 

Single copies of regulatory guides (which may be reproduced) may be obtained free of charge by writing the Distribution Services Section, U.S. Nuclear Regulatory

Commission, Washington, DC 20555-0001, or by fax to (301)415-2289, or by email to DISTRIBUTION@NRC.GOV. Electronic copies of this guide and other recently

issued guides are available at NRC’s home page at <WWW.NRC.GOV> through the Electronic Reading Room, Accession Number ML032740277.

U.S. NUCLEAR REGULATORY COMMISSION Revision 1

October 2003

REGULATORY GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 1.180

(Draft was issued as DG-1119)

GUIDELINES FOR EVALUATING ELECTROMAGNETIC AND

RADIO-FREQUENCY INTERFERENCE 

IN SAFETY-RELATED INSTRUMENTATION

AND CONTROL SYSTEMS

A. INTRODUCTION

This regulatory guide has been revised to provide guidance to licensees and applicants on additional

methods acceptable to the NRC staff for complying with the NRC’s regulations on design, installation, and testing

practices for addressing the effects of electromagnetic and radio-frequency interference (EMI/RFI) and power

surges on safety-related instrumentation and control (I&C) systems. The changes in this revision include

endorsing Military Standard MIL-STD-461E and the International Electrotechnical Commission (IEC) 61000

series of EMI/RFI test methods, extending the guidance to cover signal line testing, incorporating frequency

ranges where portable communications devices are experiencing increasing use, and relaxing the operating

envelopes (test levels) when experience and confirmatory research warrants. Exemptions from specific test

criteria are also offered based on technical considerations such as plant conditions and the intended location of

the safety-related I&C equipment. 

The NRC’s regulations in Part 50, “Domestic Licensing of Production and Utilization Facilities,” of Title

10 of the Code of Federal Regulations (10 CFR Part 50) state that structures, systems, and components

important to safety in a nuclear power plant are to be designed to accommodate the effects of environmental
1

 IEEE publications may be purchased from the IEEE Service Center, 445 Hoes Lane, Piscataway, NJ 08855-1331.

2

 An applicant who references an advanced reactor certification is not allowed to depart from the Tier 2* commitments without

NRC approval. Thus, changes cannot be made under a process such as that in 10 CFR 50.59.

3

 Copies are available at current rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328

(telephone (202)512-1800); or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road,

Springfield, VA 22161; <http://www.ntis.gov/ordernow> (telephone (703)487-4650;. Copies are available for inspection or

copying for a fee from the NRC Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDR’s mailing address is

USNRC PDR, Washington, DC 20555; telephone (301)415-4737 or (800)397-4209; fax (301)415-3548; email is

PDR@NRC.GOV.

1.180-2

conditions (i.e., remain functional under all postulated service conditions) and that design control

measures such as testing are to be used to check the adequacy of design. Section 50.55a(h) of 10 CFR

Part 50 states that protection systems must meet the requirements of the Institute of Electrical and

Electronics Engineers (IEEE) standard (Std) 603-1991, “Criteria for Safety Systems for Nuclear Power

Generating Stations,”1 or IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power

Generating Stations,”1 contingent on the date of construction permit issuance. The design basis criteria

identified in those standards, or by similar provisions in the licensing basis for such facilities, include the

range of transient and steady state environmental conditions during normal, abnormal, and accident

circumstances throughout which the equipment must perform. Criterion III, “Design Control,” Criterion

XI, “Test Control,” and Criterion XVII, “Quality Assurance Records,” of Appendix B, “Quality

Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50

establish practices to confirm that a design fulfills its technical requirements. Furthermore, 10 CFR 50.49

and 50.55a address validation measures such as testing that can be used to check the adequacy of

design. Related requirements are contained in General Design Criteria 1, 2, 4, 13, 21, 22, and 23 of

Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50. Additionally,

Subpart B, “Standard Design Certifications,” of 10 CFR Part 52, “Early Site Permits; Standard Design

Certifications; and Combined Licenses for Nuclear Power Plants,” addresses verification requirements

for advanced reactor designs. Specifically, 10 CFR 52.47(a)(vi) requires that an application for design

certification must state the tests, inspections, analyses, and acceptance criteria that are necessary and

sufficient to provide reasonable assurance that a plant will operate within the design certification. 

Methods for addressing electromagnetic compatibility (EMC) constitute Tier 2* information under the 10

CFR Part 52 requirements.2

Electromagnetic interference (EMI), radio-frequency interference (RFI), and power surges have

been identified as environmental conditions that can affect the performance of safety-related electrical

equipment. Confirmatory research findings to support this observation can be found in NUREG/CR5700, “Aging Assessment of Reactor Instrumentation and Protection System Components”3

 (July 1992);

NUREG/CR-5904, “Functional Issues and Environmental Qualification of Digital Protection Systems of

Advanced Light-Water Nuclear Reactors”3 (April 1994); NUREG/CR-6406, “Environmental Testing of

an Experimental Digital Safety Channel”3 (September 1996); and NUREG/CR-6579, “Digital I&C

Systems in Nuclear Power Plants: Risk-Screening of Environmental Stressors and a Comparison of

Hardware Unavailability With an Existing Analog System”3 (January 1998). Therefore, controlling

electrical noise and the susceptibility of I&C systems to EMI/RFI and power surges is an important step

in meeting the aforementioned requirements. 
4

 Military Standards are available from the Department of Defense, Standardization Documents Order Desk, Building 4D, 700

Robbins Avenue, Philadelphia, PA 19111-5094.

5

 IEC publications may be purchased from the International Electrotechnical Commission, 3 rue de Varembé, Geneva,

Switzerland. Telefax: +41 22 919 0300.

1.180-3

This regulatory guide endorses design, installation, and testing practices acceptable to the NRC

staff for addressing the effects of EMI/RFI and power surges on safety-related I&C systems in a nuclear

power plant environment. The design and installation practices described in IEEE Std 1050-1996,

“IEEE Guide for Instrumentation and Control Equipment Grounding in Generating Stations,”1 are

endorsed for limiting EMI/RFI subject to the conditions stated in the Regulatory Position. EMC testing

practices from military and commercial standards are endorsed to address electromagnetic emissions,

EMI/RFI susceptibility, and power surge withstand capability (SWC). Selected EMI/RFI test methods

from MIL-STD-461E, “Requirements for the Control of Electromagnetic Interference Characteristics of

Subsystems and Equipment,”4 and the IEC 61000 Series are endorsed to evaluate conducted and

radiated EMI/RFI phenomena for safety-related I&C systems. The IEC standards include IEC 61000-

3, “Electromagnetic Compatibility (EMC) - Part 3: Limits,”5 IEC 61000-4, “Electromagnetic

Compatibility (EMC) - Part 4: Testing and Measurement Techniques,”5 and IEC 61000-6,

Electromagnetic Compatibility (EMC) - Part 6: Generic Standards.”5 This regulatory guide provides

acceptable suites of EMI/RFI emissions and susceptibility methods from the most recent versions of the

military standard and international commercial standards. These suites of test methods can be applied as

alternative sets (guidance is provided in the Regulatory Position). This regulatory guide also endorses

electromagnetic operating envelopes corresponding to the MIL-STD-461E test methods. These

operating envelopes were tailored from the MIL-STD-461E test limits to represent the characteristic

electromagnetic environment in key locations at nuclear power plants. Comparable operating envelopes

for the IEC 61000 test methods are also endorsed. The operating envelopes are presented within the

Regulatory Position, along with descriptions of the endorsed MIL-STD-461E and IEC 61000 test

methods. 

The SWC practices described in IEEE Std C62.41-1991 (reaffirmed in 1995), “IEEE

Recommended Practice on Surge Voltages in Low-Voltage AC Power Circuits,”1 and IEEE Std

C62.45-1992 (reaffirmed in 1997), “IEEE Guide on Surge Testing for Equipment Connected to LowVoltage AC Power Circuits,”1

 are acceptable to the NRC staff regarding the effect of power surges on

safety-related I&C systems in nuclear power plants. A specific set of surge test waveforms are endorsed

from IEEE Std C62.41-19911 as acceptable SWC test criteria. The associated test methods in IEEE

Std C62.45-19921 are endorsed to describe the approach to be employed when assessing SWC. 

General withstand levels are endorsed for use with the SWC test criteria and are presented within the

Regulatory Position, along with the description of the endorsed surge waveforms. Alternative SWC

practices from IEC 61000-45 are acceptable to the NRC staff and are also presented within the

Regulatory Position.

The practices endorsed in this regulatory guide apply to both safety-related I&C systems and

non-safety-related I&C systems whose failures can affect safety functions. The rationale for the selection

of the practices depicted in this guide is that they provide a well established, systematic approach for

ensuring EMC and the capability to withstand power surges in I&C equipment within the environment in
1.180-4

which it operates. The technical basis for selecting these particular practices is given in NUREG/CR5941, “Technical Basis for Evaluating Electromagnetic and Radio-Frequency Interference in SafetyRelated I&C Systems”3

 (April 1994), NUREG/CR-6431, “Recommended Electromagnetic Operating

Envelopes for Safety-Related I&C Systems in Nuclear Power Plants”3 (April 1999), NUREG/CR5609, “Electromagnetic Compatibility Testing for Conducted Susceptibility Along Interconnecting Signal

Lines”3 (May 2003), and NUREG/CR-6782, “Comparison of U.S. Military and International

Electromagnetic Compatibility Guidance”3 (May 2003).

In general, information provided by regulatory guides is reflected in the Standard Review Plan

(NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power

Plants”).3 NRC’s Office of Nuclear Reactor Regulation uses the Standard Review Plan to review

applications to construct and operate nuclear power plants. This regulatory guide conforms to the

revised Chapter 7, “Instrumentation and Controls,” of the Standard Review Plan.

The information collections contained in this regulatory guide are covered by the requirements of

10 CFR Part 50, which were approved by the Office of Management and Budget (OMB), approval

number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,

a request for information or an information collection requirement unless the requesting document displays

a currently valid OMB control number.

B. DISCUSSION

Existing I&C equipment in nuclear power plants is currently being replaced with computer-based

digital I&C systems or advanced analog systems. However, these technologies may exhibit greater

vulnerability to the nuclear power plant EMI/RFI environment than existing I&C systems. This regulatory

guide provides an acceptable method for qualifying digital and advanced analog systems for the projected

electromagnetic environment in nuclear power plants.

The typical environment in a nuclear power plant includes many sources of electrical noise, for

example, hand-held two-way radios, arc welders, switching of large inductive loads, high fault currents,

and high-energy fast transients associated with switching at the generator or transmission voltage levels. 

The increasing use of advanced analog- and microprocessor-based I&C systems in reactor protection

and other safety-related plant systems has introduced concerns with respect to the creation of additional

noise sources and the susceptibility of this equipment to the electrical noise already present in the nuclear

power plant environment.

Digital technology is constantly evolving, and manufacturers of digital systems are incorporating

increasingly higher clock frequencies and lower logic level voltages into their designs. However, these

performance advancements may have an adverse impact on the operation of digital systems with respect

to EMI/RFI and power surges because of the increased likelihood of extraneous noise being

misinterpreted as legitimate logic signals. With recent advances in analog electronics, many of the

functions presently being performed by several analog circuit boards could be combined into a single
1.180-5

analog circuit board operating at reduced voltage levels, thereby making analog circuitry more

susceptible to EMI/RFI and power surges as well. Hence, opera-tional and functional issues related to

safety in the nuclear power plant environment must address the possibility of upsets and malfunctions in

I&C systems caused by EMI/RFI and power surges.

The NRC staff accepted the Electric Power Research Institute (EPRI) topical report

TR-102323, "Guidelines for Electromagnetic Interference Testing in Nuclear Power Plants," in a Safety

Evaluation Report (SER) by letter dated April 17, 1996, as one method of addressing issues of EMC for

safety-related digital I&C systems in nuclear power plants. The original Regulatory Guide 1.180

(January 2000) and this revision complement the position set forth in the SER. The guidance in these

documents constitutes acceptable methods for addressing EMC considerations for qualifying

safety-related I&C systems for the expected electromagnetic environment in nuclear power plants. This

guide provides additional acceptable methods and includes guidance on testing to address signal line

susceptibility and very high frequency (> 1 Ghz) phenomena.

The EMI/RFI practices, SWC practices, and operating envelopes endorsed in this guide are only

elements of the total package that is needed to ensure EMC within nuclear power plants. In addition to

assessing the electromagnetic environment, plants should apply sound engineering practices for nonsafety-related upgrades and I&C maintenance as part of an overall EMC program. While non-safetyrelated systems are not part of the regulatory guidance being developed, control of EMI/RFI from these

systems is necessary to ensure that safety-related I&C systems can continue to perform properly in the

nuclear power plant environment. When feasible, the emissions from non-safety-related systems should

be held to the same levels as safety-related systems.

As with the original Regulatory Guide 1.180, this revision endorses IEEE Std 1050-1996 with

one exception as stated in Regulatory Position 2. The exception was cited in NUREG/CR-5941. IEEE

Std 1050-1996 provides guidance on the engineering practices needed to control upsets and

malfunctions in safety-related I&C systems when exposed to EMI/RFI and power surges. IEEE Std

1050-1996 was developed to provide guidance on the design and installation of grounding systems for

I&C equipment specific to power generating stations. Further purposes of the standard are to achieve

both a suitable level of protection for personnel and equipment and suitable electrical noise immunity for

signal ground references in power generating stations.

IEEE Std 1050-1996 addresses grounding and noise-minimization techniques for I&C systems in

a generating station environment. This standard recommends practices for the treatment of both analog

and digital systems that address the grounding and shielding of electronic circuits on the basis of

minimizing emissions and their susceptibility to EMI/RFI and power surges. The standard is

comprehensive in that it covers both the theoretical and practical aspects of grounding and

electromagnetic compatibility.

Design verification measures for EMI/RFI testing (emissions and susceptibility) are beyond the

scope of IEEE Std 1050-1996. To determine the adequacy of safety-related I&C system designs, the

NRC staff has endorsed the applicable EMI/RFI test methods in MIL-STD-461E and the IEC 61000
1.180-6

Series (i.e., the most recently issued military and international commercial guidance), along with custom

operating envelopes developed to represent the characteristic electromagnetic environment for nuclear

power plants. The test methods and operating envelopes are cited in Regulatory Positions 3, 4, and 6 of

this guide. MIL-STD-461E is included in this revision because it replaced MIL-STD-461D and MILSTD-462D. The associated changes are discussed in NUREG/CR-6782. The original Regulatory

Guide 1.180 cited EMI/RFI test guidance from MIL-STD-461C, 461D, -462, and -462D. MIL-STD461E was developed as a measure to ensure the electromagnetic compatibility of equipment. The

application of the MIL-STD-461E test methods is tailored for the intended function of the equipment and

the characteristic environment (i.e., which tests are applied and what levels are used depend on the

function to be performed and the location of operation). Previous versions of the standard have been

used successfully by the U.S. Department of Defense for many years and are commonly referenced in

commercial applications. The IEC 61000 series of tests include IEC 61000-3, IEC 61000-4, and IEC

61000-6.

Regulatory Position 3 describes the conducted EMI/RFI emissions tests and operating envelopes

acceptable to the NRC staff. In turn, Regulatory Position 4 describes the acceptable EMI/RFI

susceptibility tests and operating envelopes. The rationale for the selection of the particular EMI/RFI

tests and operating envelopes is discussed in NUREG/CR-6782. These discussions include how the

EMI/RFI tests were selected, how the IEC 61000 tests should be applied, the exemptions that can be

applied with the use of some tests, and the adjustments made to the operating envelopes recommended

in MIL-STD-461E.

In addition, Regulatory Position 4 also describes the conducted EMI/RFI susceptibility tests and

operating envelopes that are acceptable to the NRC staff for addressing the susceptibility of signal lines

to interference. The rationale for the selection of the test methods and operating envelopes is discussed

in detail in NUREG/CR-5609. Regulatory Position 6 describes the guidance that is acceptable to the

NRC staff for validating the performance of safety-related I&C systems above 1 GHz, and its rationale is

cited in NUREG/CR-6782.

Design verification measures for power surge withstand testing are also beyond the scope of

IEEE Std 1050-1996. Accordingly, the NRC in the original regulatory guide endorsed the test criteria

recommended in IEEE Std C62.41-1991 and the associated test methods recommended in IEEE Std

C62.45-1992. This revision would update that guidance to also include the IEC 61000-4 tests relevant

to power surge withstand testing. The entire complement of SWC test criteria, test methods, and

operating envelopes endorsed by the NRC are described in Regulatory Position 5. Comparisons of the

IEEE and IEC power surge withstand tests, along with rationale for adjusting test levels, are discussed in

NUREG/CR-6782.

General operating envelopes that form the basis for establishing EMI/RFI and power surge

testing levels are cited in this regulatory guide. The technical basis for the electromagnetic operating

envelopes is presented in NUREG/CR-6431, NUREG/CR-5609, and NUREG/CR-6782. The

operating envelopes are applicable for locations within a nuclear power plant where safety-related I&C

systems either are or are likely to be installed. These locations include control rooms, remote shutdown
1.180-7

panels, cable spreading rooms, equipment rooms, relay rooms, auxiliary instrument rooms, and other

areas (e.g., the turbine deck) where safety-related I&C system installations are planned. The operating

envelopes are also applicable for both analog and digital system installations.

Any modifications to the electromagnetic operating envelopes (e.g., lower site-specific

envelopes) should be based on technical evidence comparable to that presented in NUREG/CR-6431,

NUREG/CR-5609, and NUREG/CR-6782. Relaxation in the operating envelopes should be based on

actual measurement data collected in accordance with IEEE Std 473-1985 (reaffirmed in 1997), “IEEE

Recommended Practice for an Electromagnetic Site Survey (10 kHz to 10 GHz).”

C. REGULATORY POSITION

1. GENERAL

Establishing and continuing an EMC program for safety-related I&C systems in nuclear power

plants contributes to the assurance that safety-related structures, systems, and components are designed

to accommodate the effects of and to be compatible with the environmental conditions associated with

nuclear power plant service conditions. Application of consensus standard practices regarding the

design, testing, and installation of safety-related I&C system modifications or new installations constitutes

an important element of such a program. This guidance recommends design and installation practices to

limit the impact of electromagnetic effects, testing practices to assess the emissions and susceptibility of

equipment, and testing practices to evaluate the power SWC of the equipment. Operating envelopes

characteristic of the electromagnetic environment in nuclear power plants are cited in this guidance as the

basis for establishing acceptable testing levels. Table 1 lists the specific regulatory positions on EMC that

are set forth below. This guidance is applicable to all new safety-related systems or modifications to

existing safety-related systems that include analog, digital, or hybrid (i.e., combined analog and digital)

electronics equipment. The endorsed test methods for evaluating the electromagnetic emissions,

EMI/RFI susceptibility, and power surge withstand capability of safety-related equipment are intended

for application in test facilities or laboratories before installation.

The electromagnetic conditions at the point of installation for safety-related I&C systems should

be assessed to identify any unique EMI/RFI sources that may generate local interference. The EMI/RFI

sources could include both portable and fixed equipment (e.g., portable transceivers, arc welders, power

supplies, and generators). Steps should be taken during installation to ensure that systems are not

exposed to EMI/RFI levels from the identified sources that are greater than 8 dB below the specified

operating envelopes.

To ensure that the operating envelopes are being used properly, equipment should be tested in

the same physical configuration as that specified for its actual installation in the nuclear power plant. In

addition, the equipment should be in its normal mode of operation (i.e., performing its intended function)

during the testing. Following the tests, the physical configuration of the safety-related I&C system should

be maintained and all changes in the configuration controlled. The design specifications that should be
1.180-8

maintained and controlled include wire and cable separations, shielding techniques, shielded enclosure

integrity, apertures, gasketing, grounding techniques, EMI/RFI filters, circuit board layouts, and other

design parameters that may impact the EMC qualification testing results. 

Exclusion zones should be established through administrative controls to prohibit the activation of

portable EMI/RFI emitters (e.g., welders and transceivers) in areas where safety-related I&C systems

have been installed. An exclusion zone is defined as the minimum distance permitted between the point

of installation and where portable EMI/RFI emitters are allowed to be activated. The size of the

exclusion zones should be site-specific and depend on the effective radiated power and antenna gain of

the portable EMI/RFI emitters used within a particular nuclear 

Table 1 Specific Regulatory Positions for EMC Guidance

Regulatory

Position

EMC Issue

Addressed

Standards Endorsed Comments/Conditions

2 EMI/RFI limiting

practices

IEEE Std 1050-1996 Full standard endorsed with one

exception taken.

3, 4, 6 EMI/RFI emissions

and susceptibility

(radiated, conducted

power line and

conducted signal

line) testing

MIL-STD-461E

IEC 61000-3

IEC 61000-4

IEC 61000-6

Selected MIL-STD-461E test

methods and operating envelopes

endorsed.

Selected IEC 61000 test methods and

operating envelopes endorsed.

Option of alternative test suites from

most recent versions of MIL-STD and

IEC guidelines.

General electromagnetic operating

envelopes for key nuclear power plant

locations are included in Regulatory 

Positions 3, 4, and 6.
1.180-9

d

PG

E

meters

t t

=

30

( )

5 SWC testing IEEE Std C62.41-

1991

IEEE Std C62.45-

1992

IEC 61000-4

Selected IEEE Std C62.41-1991

surge test waveforms endorsed with

associated IEEE Std C62.45-1992

test methods.

Selected IEC 61000-4 surge test

waveforms and test methods

endorsed.

General withstand levels for nuclear

power plants are included in

Regulatory Position 5.

power plant. The size of exclusion zones should also depend on the allowable electric field emission

levels designated for the area in the vicinity of the installed safety-related I&C system. To establish the

size of an exclusion zone, an 8 dB difference between the susceptibility operating envelope and the

allowed emissions level should be maintained. For the radiated electric field operating envelope of 10

V/m (140 dBμV/m), the size of the exclusion zones should be set such that the radiated electric fields

emanating from the portable EMI/RFI emitters are limited to 4 V/m (132 dBμV/m) in the vicinity of

safety-related I&C systems. The minimum distance of an exclusion zone (d) in meters should be

calculated by the following equation derived from the free space propagation model:

where:

Pt = the effective radiated power of the EMI/RFI emitter (in Watts);

Gt = the gain of the EMI/RFI emitter (dimensionless); and,

E = the allowable radiated electric field strength of the EMI/RFI emitter (in 

 Volts/meter) at the point of installation.

Note that unintentional transmitters (welders, motors, etc.) will typically have a gain that is less than or

equal to 1 (the gain of an isotropic emitter), and the gain for intentional transmitters (two-way radios, cell

phones, etc.) will typically be greater than 1. Typical values for the gain of intentional transmitters might

vary from 1.5 for a short dipole antenna to 3 for a monopole antenna, and to 6 for a horn antenna.

2. IEEE Std 1050-1996

IEEE Std 1050-1996, “IEEE Guide for Instrumentation and Control Equipment Grounding in

Generating Stations,”1 describes design and installation practices that are acceptable to the NRC staff

regarding EMI/RFI- and power surge-related effects on safety-related I&C systems employed in nuclear

power plants with the following exception. 
1.180-10

Section 4.3.7.4, “Radiative Coupling,” of the standard maintains that the “field strength” of

propagating electromagnetic waves is inversely proportional to the square of the distance from the source

of radiation. This statement needs to be re-evaluated because radiative coupling is a far-field effect. A

distance, r, greater than the wavelength divided by 2p (r > ?/2p) from the source of radiation is

considered to be far field, which is the region where the wave impedance is equal to the characteristic

impedance of the medium. Both the electric and magnetic “field strengths” fall off as 1/r in the far field,

i.e., in inverse proportion to distance (not as its square). This concept is not to be confused with the

propagation of electromagnetic waves in the near field (r < ?/2p) where the wave impedance is

determined by the characteristics of the source and the distance from the source. In the near field, if the

source impedance is high (>377O), the electric and magnetic “field strengths” attenuate at rates of 1/r3

and 1/r2, respectively. If the source impedance is low (<377O), the rates of attenuation are reversed: 

the electric “field strength” will fall off at a rate of 1/r2 and the magnetic “field strength” at a rate of 1/r3. 

The user should understand that radiative coupling is a far-field effect and the “field strength” falls off as

1/r, not as 1/r2.

IEEE Std 1050-1996 references other standards that contain complementary and supplementary

information. In particular, IEEE Std 518-1982 (reaffirmed in 1996), “IEEE Guide for the Installation of

Electrical Equipment To Minimize Noise Inputs to Controllers from External Sources,” and IEEE Std

665-1995 (reaffirmed in 2001), “IEEE Guide for Generating Station Grounding,” are referenced

frequently. The portions of IEEE Std 518-1982 and IEEE Std 665-1995 referenced in IEEE Std 1050-

1996 are endorsed by this guide and are to be used in a manner consistent with the practices in IEEE Std

1050-1996.

3. EMI/RFI EMISSIONS TESTING

MIL-STD-461E, “Requirements for the Control of Electromagnetic Interference Characteristics

of Subsystems and Equipment,” contains test practices that can be applied to characterize EMI/RFI

emissions. IEC 61000-6, “Electromagnetic Compatibility (EMC) – Part 6: Generic Standards,” also

specifies test practices that can be applied to characterize EMI/RFI emissions for industrial environments. 

 The specific test methods acceptable to the NRC staff in regard to emissions testing for safety-related

I&C systems in nuclear power plants are presented in Tables 2 and 3. Table 2 lists the EMI/RFI

emissions test methods in MIL-STD-461E while Table 3 lists the corresponding criteria in IEC 61000-6-

4, “Electromagnetic Compatibility (EMC) – Part 6: Generic Standards – Section 4: Emission standard for

industrial environments.” These test methods cover conducted (along power leads) and radiated

interference emitted from equipment under test.
1.180-11

Table 2 MIL-STD-461E Test Methods for EMI/RFI Emissions

Method Description

CE101 Conducted emissions, low-frequency, 30 Hz to 10 kHz

CE102 Conducted emissions, high-frequency, 10 kHz to 2 MHz

RE101 Radiated emissions, magnetic field, 30 Hz to 100 kHz

RE102 Radiated emissions, electric field, 2 MHz to 1 GHz

C = conducted, R = radiated, and E = emissions.

Table 3 IEC 61000-6-4 Test Methods for EMI/RFI Emissions

Method Description

None Conducted emissions, low-frequency, 30 Hz to 10 kHz

CISPR 11 Conducted emissions, high-frequency, 150 kHz to 30 MHz

None Radiated emissions, magnetic field, 30 Hz to 100 kHz

CISPR 11 Radiated emissions, electric field, 30 MHz to 1 GHz

MIL-STD-461E provides the latest revision of domestic guidance for emissions test methods

(including improvements based on experience and the most recent technical information), thus it

represents current practice. IEC 61000-6-4 provides the most recent international guidance for

emissions test practices and incorporates by reference the test methods of CISPR 11, “Limits and

Methods of Measurement of Electromagnetic Disturbance Characteristics of Industrial, Scientific and

Medical (ISM) Radio-Frequency Equipment.” It is intended that either set of test methods be applied in

its entirety, without selective application of individual methods (i.e., no mixing and matching of test

methods) for emissions testing. Because of the absence of IEC 61000 test methods to address lowfrequency conducted emissions testing, low-frequency (magnetic field) radiated emissions testing, and

high-frequency conducted emissions testing in the frequency range from 10 kHz to 150 kHz, the IEC

emissions testing option is only acceptable under conditions that correspond to the special exemption

conditions for the MIL-STD emissions testing option related to power quality control and proximity to

equipment sensitive to magnetic fields.

The MIL-STD-461E test methods listed in Table 2 have associated operating envelopes that

serve to establish test levels. General operating envelopes that are acceptable to the NRC staff are given

below in the discussion of the listed MIL-STD-461E test methods. Likewise, operating envelopes for the

IEC 61000-6-45 test methods have been identified that are comparable to the corresponding MIL-STD

counterparts and are given below in the IEC discussion. These operating envelopes are acceptable for

locations where safety-related I&C systems either are or are likely to be installed and include control

rooms, remote shutdown panels, cable spreading rooms, equipment rooms, auxiliary instrument rooms,
1.180-12

relay rooms, and other areas (e.g., the turbine deck) where safety-related I&C system installations are

planned. The operating envelopes are acceptable for analog, digital, and hybrid system installations. 

The detailed technical basis for the electromagnetic operating envelopes is presented in

NUREG/CR-6431, NUREG/CR-5609, and NUREG/CR-6782. The technical basis for the operating

envelopes begins with the MIL-STD envelopes corresponding to the electromagnetic environment for

military ground facilities, which were judged to be comparable to that of nuclear power plants based on

general layout and equipment type considerations. Plant emissions data were used to confirm the

adequacy of the operating envelopes. From the MIL-STD starting point, adjustments to the equipment

emissions envelopes were based on consideration of the primary intent of the MIL-STD envelopes (e.g.,

whether the envelopes were based on protecting sensitive receivers on military platforms) and maintaining

some margin with the susceptibility envelopes. When changes to the operating envelopes from the MILSTD origin were motivated by technical considerations, consistency among the envelopes for comparable

test methods was promoted and commercial emissions envelopes for industrial environments were

factored into adjustments of the operating envelopes. As a result of these considerations, the operating

envelopes presented in this regulatory guide are equivalent or less restrictive than the MIL-STD

envelopes that served as their initial basis.

Generic envelopes for industrial environments were identified in IEC 61000-6-4 for both

conducted and radiated emissions. These envelopes were compared with the plant-data-based operating

envelopes and selected based on their compatibility with the nuclear power plant environment. As a

result, the IEC 61000-6-4 envelopes are equivalent or as restrictive as the plant-data-based operating

envelopes.

The MIL-STD- 461E test methods that demonstrate EMI/RFI emissions compliance are

discussed below. These methods are acceptable to the NRC staff for accomplishing EMI/RFI emissions

testing for safety-related I&C systems intended for installation in nuclear power plants. Where

applicable, conditions permitting exemption of specific tests are described.

3.1 CE101—Conducted Emissions, Low Frequency

The CE101 test measures the low-frequency conducted emissions on power leads of equipment

and subsystems in the frequency 30 Hz to 10 kHz. Equipment could be exempt from this test if the

following two conditions exist. First, the power quality requirements of the equipment are consistent with

the existing power supply; and second, the equipment will not impose additional harmonic distortions on

the existing power distribution system that exceed 5% total harmonic distortion (THD) or other power

quality criteria established with a valid technical basis. When the test is to be performed, it is applicable

to ac and dc power leads, including grounds and neutrals, that obtain power from other sources not part

of the equipment under test. Conducted emissions on power leads should not exceed the applicable root

mean square (rms) values shown in Figure 3.1. Alternative envelopes are given for ac-operated

equipment based on power consumption (less than or equal to 1 kVA and greater than 1kVA). For acoperated equipment with a fundamental current (i.e., load current at the power line frequency) greater

than 1 ampere, the envelopes in Figure 3.1 may be relaxed as follows:
1.180-13

dB relaxation = 20 log (fundamental current)

Figure 3.1 Low-Frequency Emissions Envelopes

3.2 CE102—Conducted Emissions, High Frequency

The CE102 test measures the high-frequency conducted emissions on power leads of equipment

and subsystems in the frequency range 10 kHz to 2 MHz. The test is applicable to ac and dc power

leads, including grounds and neutrals, that obtain power from other sources that are not part of the

equipment under test. Conducted emissions on power leads should not exceed the applicable rms values

shown in Figure 3.2. The values are specified according to the voltage of the power source feeding the

equipment under test. Equipment could be exempted from application of this test in the frequency range

10 kHz to 450 kHz if the nuclear power plant has power quality control (see the conditions for exemption

of the CE101 test). In addition, the following exemptions are permissible at higher frequencies. FCC

Class A certification is acceptable in lieu of CE102 testing in the frequency range from 450 kHz to 2
1.180-14

MHz. CISPR 11 Class A certification is acceptable in lieu of CE102 testing in the frequency range from

150 kHz to 2 MHz. Otherwise, the CE102 test should be performed over the full frequency range from

10 kHz to 2 MHz.

Figure 3.2 High-Frequency Conducted Emissions Envelopes

3.3 RE101—Radiated Emissions, Magnetic Field

The RE101 test measures radiated magnetic field emissions in the frequency range 30 Hz to

100 kHz. Equipment not intended to be installed in areas with other equipment sensitive to magnetic

fields could be exempt from this test. The test is applicable for emissions from equipment and subsystem

enclosures, as well as all interconnecting leads. The test does not apply at transmitter fundamental

frequencies or to radiation from antennas. Magnetic field emissions should not be radiated in excess of

the levels shown in Figure 3.3. Magnetic field emissions are measured at the specified distances of 7 cm

and compared against the corresponding envelope.
1.180-15

Figure 3.3 Magnetic-Field Radiated Emissions Envelope

3.4 RE102—Radiated Emissions, Electric Field

The RE102 test addresses measurement of radiated electric field emissions in the frequency range

of interest, 2 MHz to 1 GHz. This test is also applicable at frequencies above 1 GHz and the criteria for

those applications are given in Position 6. It is applicable for emissions from equipment and subsystem

enclosures, as well as all interconnecting leads. The test does not apply at transmitter fundamental

frequencies or to radiation from antennas.

Electric field emissions should not be radiated in excess of the rms values shown in Figure 3.4. 

At frequencies above 30 MHz, the test method should be performed for both horizontally and vertically

polarized fields.
1.180-16

Figure 3.4 Electric-Field Radiated Emissions Envelopes

3.5 IEC Emissions Tests

The IEC 61000-6-4 test practices that demonstrate EMI/RFI emissions compliance incorporate

the test methods of CISPR 11 by reference. Under the following conditions, these methods are

acceptable to the NRC staff for accomplishing EMI/RFI emissions testing for safety-related I&C systems

intended for installation in nuclear power plants. For the IEC emissions testing option to be acceptable,

two conditions must be met. First, power quality controls must be in place, which eliminates the need to

perform the CE101 test. Second, separation from equipment that is sensitive to magnetic fields must be

maintained, hence it is unnecessary to perform the RE101 test.

The specifications for the IEC 61000-6-4 test call for employing the CISPR 11 measurement

techniques. These techniques are similar to those used in the MIL-STD-461E CE102 and RE102 tests,

with some differences. For example, CISPR 11 requires a quasi-peak or average test signal detector,

while CE102 requires a peak detector. Also, CISPR 11 requires that radiated electric field

measurements be made at 30 meters and 10 meters in an open area site, while RE102 requires that the

testing be performed in a shielded enclosure and that measurements be made at a distance of 1 meter. 

Despite the differences, the tests are expected to yield similar results. Values for the IEC 61000-6-4

envelope comparable to CE102 are given in Table 4. Since the CISPR 11 Class A operating envelopes
1.180-17

are the same as the IEC 61000-6-4 operating envelopes, the CISPR 11 Class A certification for

conducted emissions satisfies IEC 61000-6-4 in the frequency range from 150 kHz to 2 MHz. In turn,

the CISPR 11 Class A certification for radiated emissions satisfies IEC 61000-6-4 in the frequency range

from 2 MHz to 1 GHz. Values for the IEC 61000-6-4 envelope comparable to RE102 are given in

Table 5.

Table 4 IEC 61000-6-4 Conducted Emissions Envelopes

(CISPR 11 Class A)

Frequency Range Test Level (dBμV)

150 kHz to 500 kHz 79 quasi-peak, 66 average

500 kHz to 5 MHz 73 quasi-peak, 60 average

5 MHz to 30 MHz 73 quasi-peak, 60 average

Table 5 IEC 61000-6-4 Radiated Emissions Envelopes

(CISPR 11 Class A)

Frequency Range Test Level (dBμV/m)

30 MHz to 230 MHz 30 quasi-peak, measured at 30 m

230 MHz to 1 GHz 37 quasi-peak, measured at 30 m

3.6 EMI/RFI Emissions Test Summary

The CE101, CE102, RE101, and RE102 tests represent the baseline emissions testing program. 

Alternative programs are allowed if the conditions for two exemptions for low frequency emissions testing

are met. A CE101 exemption is allowed if power quality control is employed and a RE101 exemption is

allowed for equipment not intended to be installed in the proximity of magnetic field emitters. 

Alternatively, either emissions testing based on IEC 61000-6-4 or that satisfying FCC Part 15 Class A

requirements is acceptable under the identified conditions. Figure 3.5 shows all of the acceptable testing

programs and notes that the alternative programs are acceptable only when the conditions for exemption

are satisfied. Thus, when the identified conditions for exempting low frequency emissions testing are met,

any of the three alternative emissions testing programs may be selected. However, regardless of the

emissions testing program selected, it is intended that each be applied in its entirety, without selective

application of individual methods (i.e., no mixing and matching of test methods) for emissions testing.
1.180-18

Conducted

EMI/RFI Emissions

CE101

CE102

RE101

RE102

Radiated

61000-6-4

(CISPR 11

Class A)

FCC Part 15

Class A

Alternate #1 Alternate #2 Alternate #3

MIL-STD IEC FCC

Baseline

with

exemptions

CE102

(450 kHz -

2 MHz)

RE102

MIL-STD

or or

Figure 3.5 Acceptable Alternatives for Emissions Testing

4. EMI/RFI SUSCEPTIBILITY TESTING

MIL-STD-461E contains test methods that can be applied to address EMI/RFI susceptibility for

a selection of environments. IEC 61000-4, “Electromagnetic Compatibility (EMC) – Part 4: Testing and

Measurement Techniques,” also specifies test methods that can be applied to characterize equipment

susceptibility to conducted and radiated EMI/RFI. The specific test methods acceptable to the NRC

staff in regard to susceptibility testing for safety-related I&C systems in nuclear power plants are

presented in Tables 6 and 7. Table 6 lists the EMI/RFI test methods in MIL-STD-461E while Table 7

lists the corresponding methods in IEC 61000-4. It is intended that either set of test methods be applied

in its entirety, without selective application of individual methods (i.e., no mixing and matching of test

methods) for susceptibility testing. These methods cover susceptibility to conducted and radiated

interference resulting from exposure to electric and magnetic fields and noise coupling through power and

signal leads.
1.180-19

Table 6 MIL-STD-461E EMI/RFI Susceptibility Test Methods

Method Description

CS101 Conducted susceptibility, low frequency, 30 Hz to 150 kHz

CS114 Conducted susceptibility, high frequency, 10 kHz to 30 MHz

CS115 Conducted susceptibility, bulk cable injection, impulse excitation

CS116 Conducted susceptibility, damped sinusoidal transients,

10 kHz to 100 MHz

RS101 Radiated susceptibility, magnetic field, 30 Hz to 100 kHz

RS103 Radiated susceptibility, electric field, 30 MHz to 1 GHz

C = conducted, R = radiated, and S = susceptibility.

Table 7 IEC 61000-4 EMI/RFI Susceptibility Test Methods

Method Description

61000-4-4 Conducted susceptibility, electrically fast transients/bursts

61000-4-5 Conducted susceptibility, surges

61000-4-6 Conducted susceptibility, disturbances induced by radio-frequency

fields

61000-4-12 Conducted susceptibility, 100 kHz ring wave

61000-4-13 Conducted susceptibility, low frequency, 16 Hz to 2.4 kHz

61000-4-16 Conducted susceptibility, low frequency, 15 Hz to 150 kHz

61000-4-8 Radiated susceptibility, magnetic field, 50 Hz and 60 Hz

61000-4-9 Radiated susceptibility, magnetic field, 50/60 Hz to 50 kHz

61000-4-10 Radiated susceptibility, magnetic field, 100 kHz and 1 MHz

61000-4-3 Radiated susceptibility, electric field, 26 MHz to 1 GHz

The MIL-STD-461E test methods listed in Table 6 have associated operating envelopes that

serve to establish test levels. General operating envelopes that are acceptable to the NRC staff are given

below in the discussion of the MIL-STD 461E test methods. Likewise, operating envelopes for the IEC

61000 test methods have been identified that are comparable to the corresponding MIL-STD
1.180-20

counterparts and are given below in the discussion of the MIL-STD 461E test methods. These operating

envelopes are acceptable for locations where safety-related I&C systems either are or are likely to be

installed and include control rooms, remote shutdown panels, cable spreading rooms, equipment rooms,

auxiliary instrument rooms, relay rooms, and other areas (e.g., the turbine deck) where safety-related

I&C system installations are planned. The operating envelopes are acceptable for analog, digital, and

hybrid system installations. 

The detailed technical basis for the electromagnetic operating envelopes is presented in

NUREG/CR-6431, NUREG/CR-5609, and NUREG/CR-6782. The technical basis for the operating

envelopes begins with the MIL-STD envelopes corresponding to the electromagnetic environment for

military ground facilities, which were judged to be comparable to that of nuclear power plants based on

general layout and equipment type considerations. Plant emissions data were used to confirm the

adequacy of the operating envelopes. From the MIL-STD starting point, susceptibility envelopes were

adjusted to account for the plant emissions data reported in NUREG/CR-6436, “Survey of Ambient

Electromagnetic and Radio-Frequency Interference Levels in Nuclear Power Plants” (November 1996)

and EPRI TR-102323. When changes to the operating envelopes from the MIL-STD origin were

motivated by technical considerations, consistency among the envelopes for comparable test criteria was

promoted. As a result of these considerations, the operating envelopes presented in this regulatory guide

are equivalent or less restrictive than the MIL-STD envelopes that served as their initial basis.

The MIL-STD-461E and IEC test methods that demonstrate EMI/RFI susceptibility compliance

are discussed below. These methods are acceptable to the NRC staff for accomplishing EMI/RFI

susceptibility testing for safety-related I&C systems intended for installation in nuclear power plants. 

Where applicable, conditions permitting exemption of specific test methods are described.

4.1 EMI/RFI Conducted Susceptibility Testing—Power Leads

The MIL-STD-461E test methods that are acceptable to the NRC staff to address conducted

EMI/RFI susceptibility along power leads are listed in Table 8. The comparable IEC 61000-4 test

methods that are acceptable to characterize equipment susceptibility to conducted EMI/RFI along power

leads are listed in Table 9. These test methods cover susceptibility to conducted interference resulting

from noise coupling through the power leads of safety-related I&C systems in nuclear power plants. 

Discussions of the test methods and operating envelopes follow below. 

Table 8 MIL-STD-461E EMI/RFI Conducted Susceptibility Test Methods—Power

Leads

Method Description

CS101 Conducted susceptibility, low-frequency, 30 Hz to 150 kHz

CS114 Conducted susceptibility, high-frequency, 10 kHz to 30 MHz
1.180-21

C = conducted and S = susceptibility.

Table 9 IEC 61000-4 EMI/RFI Conducted Susceptibility Test Methods—Power Leads

Method Description

61000-4-6 Conducted susceptibility, disturbances induced by radio-frequency

fields

61000-4-13 Conducted susceptibility, low-frequency, 16 Hz to 2.4 kHz

61000-4-16 Conducted susceptibility, low-frequency, 15 Hz to 150 kHz

 4.1.1 CS101—Conducted Susceptibility, Low Frequency

The CS101 test ensures that equipment and subsystems are not susceptible to EMI/RFI present

on power leads in the frequency range 30 Hz to 150 kHz. The test is applicable to ac and dc input

power leads, not including grounds and neutrals. If the equipment under test is dc operated, this test is

applicable over the frequency range 30 Hz to 150 kHz. If the equipment under test is ac operated, this

test is applicable starting from the second harmonic of the power line frequency and extending to 150

kHz.

The equipment under test should not exhibit any malfunction or degradation of performance

beyond specified operational tolerances when subjected to a test signal with the rms voltage levels

specified in Figure 4.1. Alternative envelopes are given for equipment with nominal source voltages at or

below 28 V and those operating above 28 V. Acceptable performance should be defined in the test plan

by the end user or testing organization according to the applicable equipment, subsystem, or system

specifications.
1.180-22

Figure 4.1 Low-Frequency Conducted Susceptibility Operating Envelopes

4.1.2 CS114—Conducted Susceptibility, High Frequency

The CS114 test simulates currents that will be developed on leads as a result of EMI/RFI

generated by antenna transmissions. The test covers the frequency range 10 kHz to 30 MHz and is

applicable to all interconnecting leads, including the power leads of the equipment under test. Although

the CS114 test can be applied to assess signal line susceptibility, the test levels given in this section apply

only to power and control lines. 

The equipment under test should not exhibit any malfunction or degradation of performance

beyond specified operational tolerances when subjected to a test signal with the rms levels shown in

Figure 4.2. Acceptable performance should be defined in the test plan by the end user or testing

organization according to the applicable equipment, subsystem, or system specifications.
1.180-23

0.01 0.1 1 10 100 1000

60

70

80

90

100

110

120

97

0.2 30

Figure 4.2 High-Frequency Conducted Susceptibility Operating Envelopes for Power Leads

4.1.3 IEC Conducted Susceptibility Tests—Power Leads

The IEC counterparts to the CS101 and CS114 tests are IEC 61000-4-13, IEC 61000-4-16,

and IEC 61000-4-6. The Class 2 devices in IEC 61000-4-13 are similar to the industrial-grade

devices used in nuclear power plants and the Class 2 operating envelope is shown in Table 10. For the

IEC 61000-4-16 test, the Level 3 (typical industrial) environment is representative of the nuclear power

plant environment. The Level 3 operating envelopes for the IEC 61000-4-16 test are shown in Table 11. 

The Level 3 test level for IEC 61000-4-6 is 140 dBFV and is most similar to the CS114 operating

envelope recommended for a typical industrial environment. These are the levels acceptable to NRC

staff.
1.180-24

Table 10 IEC 61000-4-13 Operating Envelope for 115-V System

(Class 2)

Harmonic no. (n) Class 2 (% of supply voltage) Class 2 (voltage

level)

2 3 3.5

3 8 9.2

4 1.5 1.7

5 8 9.2

6 n.a. —

7 6.5 7.5

8 n.a. —

9 2.5 2.9

10 n.a. —

11 5 5.8

12 n.a. —

13 4.5 5.2

15 n.a. —

17 3 3.5

19 2 2.3

21 n.a. —

23 2 2.3

25 2 2.3

27 n.a. —

29 1.5 1.7

31 1.5 1.7

33 n.a. —

35 1.5 1.7

37 1.5 1.7

39 n.a. —

Table 11 Operating Envelopes for IEC 61000-4-16 Conducted Susceptibility

Tests

(Level 3)

Disturbance Selected level Test level

dc and power line frequency,

continuous disturbance

Level 3—typical industrial

environment

10 Vrms

dc and power line frequency,

short-duration disturbance

Level 3—typical industrial

environment

100 Vrms

Conducted disturbance, 15 Hz to

150 kHz

Level 3—typical industrial

environment

 10–1 Vrms (15–150 Hz)

1 Vrms (150–1.5 kHz)

1–10 Vrms (1.5–15 kHz)

10 Vrms (15–150 kHz)
1.180-25

4.2 EMI/RFI Conducted Susceptibility Testing—Signal Leads

MIL-STD-461E contains test methods that can be applied to address conducted EMI/RFI

susceptibility for interconnecting signal leads. In addition, IEC 61000-4 specifies test methods that can be

applied to characterize equipment susceptibility to conducted EMI/RFI along interconnecting signal leads. 

The specific test methods acceptable to the NRC staff in regard to conducted susceptibility testing for signal

leads of safety-related I&C systems in nuclear power plants are presented in Tables 12 and 13. Table 12

lists the EMI/RFI test methods for signal leads in MIL-STD-461E, while Table 13 lists the corresponding

methods in specific sections of IEC 61000-4. These test methods cover susceptibility to conducted

interference resulting from noise coupling through interconnecting signal leads. 

Table 12 MIL-STD-461E Conducted Susceptibility Test Methods—Signal Leads

Method Description

CS114 Conducted susceptibility, high-frequency, 10 kHz to 30 MHz

CS115 Conducted susceptibility, bulk cable injection, impulse excitation

CS116 Conducted susceptibility, damped sinusoidal transients, 10 kHz to 100 MHz

C = conducted and S = susceptibility.

Table 13 IEC 61000-4 Conducted Susceptibility Test Methods—Signal Leads

Method Description

61000-4-4 Electrical fast transient/burst immunity test

61000-4-5 Surge immunity test

61000-4-6 Immunity to conducted disturbances, induced by radio-frequency fields

61000-4-12 Oscillatory waves immunity test

61000-4-16 Test for immunity to conducted, common mode disturbances in the

frequency range 0 Hz to 150 kHz

The MIL-STD-461E test methods listed in Table 12 have associated operating envelopes that serve

to establish test levels for signal leads. General operating envelopes that are acceptable to the NRC staff

are shown in Table 14. Likewise, signal lead operating envelopes for the IEC 61000-4 test criteria listed in

Table 13 have been identified in Table 15 and are comparable to their corresponding MIL-STD

counterparts. Note that the withstand level is based on the location of a cable, along with its level of

exposure. Most locations in the interior of a facility, which are typical for signal leads, correspond to a

Category B classification, as described in IEEE Std C62.41-1991 and discussed in Regulatory Position 5. 
1.180-26

Most signal leads are expected to be subject to surge environments that correspond to Low Exposure levels

(see IEEE Std C62.41-1991 and Regulatory Position 5). However, for I&C systems that are implemented

in plant areas that are characterized by surge environments corresponding to Medium Exposure levels (see

IEEE Std C62.41-1991 and Regulatory Position 5), the operating envelopes for signal leads that are given in

Table 14 should be doubled. For the IEC tests, the operating envelopes in Table 16 should be used for I&C

systems that are implemented in plant areas that are characterized by surge environments corresponding to

Medium Exposure levels.

Table 14 MIL-STD-461E Conducted Susceptibility Operating Envelopes—Signal

Leads

Method Description

CS114 91 dBFA

CS115 2 A 

CS116 5 A

Table 15 IEC 6100-4 Conducted Susceptibility Operating Envelopes 

for Low Exposure—Signal Leads

Method Description

61000-4-4 Level 3: 1 kV test voltage

61000-4-5 Level 2: 1 kV open circuit test voltage and 0.5 kA short circuit

current

61000-4-6 Level 2:130 dBμV test voltage,

61000-4-12 Ring wave: Level 2 - 1 kV test voltage 

61000-4-16 Level 2: 3/10 of the values in Table 11
1.180-27

Table 16 IEC 6100-4 Conducted Susceptibility Operating Envelopes 

for Medium Exposure—Signal Leads

Method Description

61000-4-4 Level 4: 2 kV test voltage

61000-4-5 Level 3: 2 kV open circuit test voltage and 1 kA short circuit

current

61000-4-6 Level 3:140 dBμV test voltage,

61000-4-12 Ring wave: Level 3 - 2 kV test voltage 

61000-4-16 Level 3: see Table 11

4.3 EMI/RFI Radiated Susceptibility Testing

The MIL-STD-461E test methods that are acceptable to the NRC staff for addressing the radiated

EMI/RFI susceptibility of safety-related I&C systems in nuclear power plants are listed in Table 17. The

comparable IEC 61000-4 test methods deemed acceptable to characterize equipment susceptibility to

radiated EMI/RFI are listed in Table 18. These test methods cover susceptibility to radiated interference

resulting from electromagnetic emissions in nuclear power plants. Discussions of the test methods and

operating envelopes follow below. 

Table 17 MIL-STD-461E EMI/RFI Radiated Susceptibility Test Methods

Method Description

RS101 Radiated susceptibility, magnetic field, 30 Hz to 100 kHz

RS103 Radiated susceptibility, electric field, 30 MHz to 1 GHz

R = radiated and S = susceptibility.

Table 18 IEC 61000-4 EMI/RFI Radiated Susceptibility Test Methods

Method Description

61000-4-8 Radiated susceptibility, magnetic field, 50 Hz and 60 Hz

61000-4-9 Radiated susceptibility, magnetic field, 50/60 Hz to 50 kHz

61000-4-10 Radiated susceptibility, magnetic field, 100 kHz and 1 MHz

61000-4-3 Radiated susceptibility, electric field, 26 MHz to 1 GHz
1.180-28

4.3.1 RS101—Radiated Susceptibility, Magnetic Fields

The RS101 test ensures that equipment and subsystems are not susceptible to radiated magnetic

fields in the frequency range 30 Hz to 100 kHz. Equipment that is not intended to be installed in areas

with strong sources of magnetic fields (e.g., CRTs, motors, cable bundles carrying high currents) and that

follows the limiting practices endorsed in this regulatory guide could be exempt from this test. The test is

applicable to equipment and subsystem enclosures and all interconnecting leads. The test is not

applicable for electromagnetic coupling via antennas.

The equipment under test should not exhibit any malfunction or degradation of performance

beyond specified operational tolerances when subjected to the rms magnetic field levels shown in

Figure 4.3. Acceptable performance should be defined in the test plan by the end user or testing

organization according to the applicable equipment, subsystem, or system specifications.

Figure 4.3 Low-Frequency Radiated Susceptibility Envelopes

4.3.2 RS103—Radiated Susceptibility, Electric Fields

The RS103 test ensures that equipment and subsystems are not susceptible to radiated electric

fields in the frequency range 30 MHz to 1 GHz. This test is also applicable at frequencies above 1 GHz

and the criteria for those applications are given in Position 6. The test is applicable to equipment and

subsystem enclosures and all interconnecting leads. The test is not applicable at the tuned frequency of

antenna-connected receivers unless otherwise specified.

The equipment under test should not exhibit any malfunction or degradation of performance
1.180-29

beyond specified operational tolerances when subjected to the radiated electric fields. The impressed

electric field level should be 10 V/m (rms), measured in accordance with the techniques specified in the

RS103 test method. The test method should be performed for both horizontally and vertically polarized

fields. According to MIL-STD-461E, circularly polarized fields are not acceptable because radiated

electric fields are typically linearly polarized. Acceptable performance should be defined in the test plan

by the end user or testing organization according to the applicable equipment, subsystem, or system

specifications.

4.3.3 IEC Radiated Susceptibility Tests

The IEC counterparts for the RS101 test are IEC 61000-4-8, IEC 61000-4-9, and IEC 61000-

4-10. Operating envelopes for the typical industrial environment (Class 4) are shown in Table 19. The

IEC counterpart for the RS103 test is IEC 61000-4-3 and its frequency range is 26 MHz to 1 GHz. The

Level 3 in IEC 61000-4-3 is most similar to the nuclear power plant environment and requires a test level

of 10 V/m. This level is equal to the RS103 operating envelope of 10 V/m. These levels are acceptable

to NRC staff for the IEC radiated susceptibility tests.

Table 19 IEC 61000-4-8, -4-9, and -4-10 Operating Envelopes

Method Selected Class Test Level

IEC 61000-4-8 Continuous pulses: Class 4 – typical

industrial environment

Short duration pulses: Class 4 – typical

industrial environment

30 A/m (152 dBpT)

300 A/m (172 dBpT)

IEC 61000-4-9 Class 4 – typical industrial environment 300 A/m (172 dBpT)

IEC 61000-4-10 Class 4 – typical industrial environment 30 A/m (152 dBpT)

4.4 EMI/RFI Susceptibility Test Summary

The CS101 and CS114 tests for power leads, the CS114, CS115, and CS116 tests for signal

leads, and the RS101 and RS103 tests represent the baseline susceptibility testing program. An

alternative susceptibility testing program based on IEC 61000 is acceptable for establishing susceptibility

characteristics of safety-related I&C systems. Figure 4.4 shows the two acceptable susceptibility testing

programs. While there is no restriction on the selection of either susceptibility testing program, it is

intended that each be applied in its entirety, without selective application of individual methods (i.e., no

mixing and matching of test methods) for susceptibility testing.
1.180-30

(*) Exemption based on proximity to magnetic field emitters

Conducted

EMI/RFI Susceptibility

CS101

CS114

Radiated

61000-4-6

Alternate

MIL-STD IEC

Baseline

CS114

CS115

CS116

Power Signal

61000-4-13

61000-4-16

61000-4-6

61000-4-16

61000-4-4

61000-4-5

61000-4-12

61000-4-10(*)

Power Signal

RS101(*)

RS103

61000-4-8(*)

61000-4-9(*)

61000-4-3

Figure 4.4 Acceptable Alternatives for EMI/RFI Susceptibility Testing

5. SURGE WITHSTAND CAPABILITY

The SWC practices described in IEEE Std C62.41-1991 (reaffirmed in 1995), “IEEE

Recommended Practice on Surge Voltages in Low-Voltage AC Power Circuits,” and IEEE Std C62.45-

1992 (reaffirmed in 1997), “IEEE Guide on Surge Testing for Equipment Connected to Low-Voltage

AC Power Circuits,” are acceptable to the NRC staff regarding the effect of power surges on safetyrelated I&C systems in nuclear power plants. IEEE Std C62.41-1991 defines a set of surge test

waveforms that has manageable dimensions and represents a baseline surge environment. IEEE Std

C62.45-1992 describes the associated test methods and equipment to be employed when performing the

surge tests. Typical environmental conditions for power surges in a nuclear power plant can be

represented by the waveforms given in Table 20.

Table 20 IEEE C62.41-1991 Power Surge Waveforms

Parameter Ring Wave Combination Wave EFT

Waveform Open-circuit

voltage

Open-circuit Short-circuit

 voltage current

Pulses in

15-ms bursts

Rise time 0.5 μs 1.2 μs 8 μs 5 ns

Duration 100 kHz

ringing 

 50 μs 20 μs 50 ns
1.180-31

The IEC 61000-4 tests comparable to the IEEE C62.41-1991 tests are listed in Table 21. The

test waveforms are the same and the test procedures are very similar. Hence, a direct interchange of the

test methods is acceptable to the NRC staff. Test levels for the IEC 61000-4 tests are specified

according to the intended environment.

Table 21 Comparable SWC Test Methods

IEEE C62.41-1991 IEC Method

Ring Wave 61000-4-12

Combination Wave 61000-4-5

EFT 61000-4-4

IEEE Std C62.41-1991 describes location categories and exposure levels that define applicable

amplitudes for the surge waveforms that should provide an appropriate degree of SWC. Location

categories depend on the proximity of equipment to the service entrance and the associated line

impedance. Exposure levels relate to the rate of surge occurrence versus the voltage level (e.g., surge

crest) to which equipment is exposed. The withstand levels presented in this regulatory position are

based on Category B and Category C locations, along with Low Exposure and Medium Exposure

levels. Category B covers feeders and short branch circuits extending to interior locations from the

service entrance. Category C covers the exterior and service entrance. Low Exposure levels

encompass systems in areas known for little load or capacitor switching and low-power surge activity. 

Medium Exposure levels encompass systems in areas subject to significant switching transients and

medium to high lightning activity. Table 22 lists the withstand levels that are acceptable for nuclear

power plant application. Interior locations where safety-related I&C systems either are or are likely to

be installed include control rooms, remote shutdown panels, cable spreading rooms, equipment rooms,

auxiliary instrument rooms, relay rooms, and other areas (e.g., the turbine deck). Many of these areas

can be classified as Category B locations with Low Exposure levels. However, locations where primary

power is provided through connection to external lines or there are sources of significant switching

transients present (e.g., switchgear, large motors) should be treated as Category B locations with

Medium Exposure levels. A determination of the exposure level classification that characterizes a

location is necessary to select the applicable withstand levels. 

Table 22 Surge Withstand Levels for Power Lines

Surge Waveform

Category B

Low Exposure

Category B

Medium Exposure

Category C

Exterior

Ring Wave 2 kV 4 kV N/A
Surge Waveform

Category B

Low Exposure

Category B

Medium Exposure

Category C

Exterior

1.180-32

Combination Wave 2 kV / 1 kA 4 kV / 2 kA 6 kV / 3 kA

EFT 2 kV 4 kV N/A

5.1 IEEE C62.41 Ring Wave and IEC 61000-4-12

The Ring Wave simulates oscillatory surges of relatively high frequency on the ac power leads of

equipment and subsystems and is represented by an open-circuit voltage waveform. The waveform,

100-kHz sinusoid, has an initial rise time of 0.5 μs and continually decaying amplitude. A plot of the

waveform is shown in Figure 5.1. The rise time is defined as the time difference between the 10% and

90% amplitude points on the leading edge of the waveform. The amplitude of the waveform decays with

each peak being 60% of the amplitude of the preceding peak of the opposite polarity.

 The peak voltage value of the Ring Wave is given in Table 22. For the IEC test, the withstand

levels correspond to Level 3 and Level 4 for the Low Exposure and Medium Exposure categories,

respectively. During the performance of the test, the equipment under test should not exhibit any

malfunction or degradation of performance beyond specified operational tolerances when subjected to

the Ring Wave. Acceptable performance of the equipment under test should be defined in the test plan

by the end user or testing organization according to the applicable equipment, subsystem, or system

specifications.

5.2 IEEE C62.41 Combination Wave and IEC 61000-4-5

The Combination Wave involves two exponential waveforms, an open-circuit voltage and a

short-circuit current. It is intended to represent direct lightning discharges, fuse operation, or capacitor

switching on the ac power leads of equipment and subsystems. The open-circuit voltage waveform has a

1.2-μs rise time and an exponential decay with a duration (to 50% of initial peak level) of 50 μs. The

short-circuit current waveform has an 8-μs rise time and a duration of 20 μs. Plots of the waveforms are

shown in Figures 5.2 and 5.3.

The rise time is defined as the time difference between the 10% and 90% amplitude points on the

leading edge of the waveform. The duration is defined as the time between virtual origin and the time at

the 50% amplitude point on the tail of the waveform. Virtual origin is the point where a straight line

between the 30% and 90% points on the leading edge of the waveform intersects the V=0 line for the

open-circuit voltage and the i=0 line for the short-circuit current.

 The peak value of the open-circuit voltage of the Combination Wave and the peak value of the

short-circuit current are given in Table 22. For the IEC test, the withstand levels correspond to Level 3

and Level 4 for the Low Exposure and Medium Exposure categories, respectively. The Category C
1.180-33

withstand level corresponds to the special class, Level x , for the IEC test. During the performance of

the test, the equipment under test should not exhibit any malfunction or degradation of performance

beyond specified operational tolerances when subjected to the Combination Wave. Acceptable

performance of the equipment under test should be defined in the test plan by the end user or testing

organization according to the applicable equipment, subsystem, or system specifications.

Figure 5.1 100-kHz Ring Wave
1.180-34

Figure 5.2 Combination Wave, Open-Circuit Voltage

Figure 5.3 Combination Wave, Short-Circuit Current
1.180-35

5.3 IEEE C62.41 Electrically Fast Transients and IEC 61000-4-4

The EFT waveform consists of repetitive bursts, with each burst containing individual

unidirectional pulses, and is intended to represent local load switching on the ac power leads of

equipment and subsystems. The individual EFT pulses have a 5-ns rise time and a duration (width at halfmaximum) of 50 ns. Plots of the EFT pulse waveform and the pattern of the EFT bursts are shown in

Figures 5.4 and 5.5. The number of pulses in a burst is determined by the pulse frequency. For peaks

less than or equal to 2 kV, the pulse frequency will be 5 kHz±1 kHz. For peaks greater than 2 kV, the

pulse frequency will be 2.5 kHz±0.5 kHz.

The rise time is defined as the time difference between the 10% and 90% amplitude points on the

leading edge of the waveform. The duration is defined as the time between the 50% amplitude points on

the leading and trailing edges of each individual pulse. Individual pulses occur in bursts of 15 ms duration.

The peak value of the individual EFT pulses is given in Table 22. For the IEC test, the withstand

levels correspond to Level 3 and Level 4 for the Low Exposure and Medium Exposure categories,

respec-tively. During the performance of the test, the equipment under test should not exhibit any

malfunction or degradation of performance beyond specified operational tolerances when subjected to

the EFT pulses.

Figure 5.4 Waveform of the EFT Pulse
1.180-36

Figure 5.5 Pattern of EFT Bursts

Acceptable performance of the equipment under test should be defined in the test plan by the end

user or testing organization according to the applicable equipment, subsystem, or system specifications.

6. RADIATED EMI/RFI TESTING ABOVE 1 GHz

MIL-STD-461E contains test methods and criteria that can be applied to address radiated

EMI/RFI emissions and susceptibility above 1 GHz for a selection of environments. IEC 61000-3 and

IEC 61000-4 do not. The RE102 test is applicable above 1 GHz for up to 10 times the highest

intentionally generated frequency within the equipment under test. The associated emissions operating

envelope is shown in Figure 6.1. The specific test method acceptable to the NRC staff in regard to

radiated susceptibility testing above 1 GHz is contained in the MIL-STD-461E presentation of RS103. 

This method covers susceptibility above 1 GHz to radiated interference resulting from exposure to electric

fields.

The need for radiated susceptibility testing in the frequency range 1 GHz to 10 GHz has arisen

because of the development of faster speed microprocessors and wireless communications, which

contribute to interference concerns in the very high frequency band. Susceptibility testing in this range

covers the unlicensed frequency bands where much of the communications activity is taking place (2.45

GHz and 5.7 GHz). The new developments are not expected to be strong emitters because of FCC

restrictions, so the susceptibility test operating envelope will remain the same as at lower frequencies, 10

V/m (rms).
1.180-37

Figure 6.1 Electric-Field Radiated Emissions Envelope Above 1 GHz

7. DOCUMENTATION

Electromagnetic compatibility documentation should provide evidence that safety-related I&C

equipment meets its specification requirements and is compatible with the projected electromagnetic

environment, that the user adheres to acceptable installation practices, and that administrative controls

have been established covering the allowable proximity of portable EMI/RFI sources. Data used to

demonstrate the compatibility of the equipment with its projected environment should be pertinent to the

application and be organized in a readily understandable and traceable manner that permits independent

auditing of the conclusion presented.

The content of electromagnetic compatibility documentation should contain the information listed

below, as well as any additional information specified in the standards cited by this regulatory guide. 

These items, as a minimum, could be included as part of a qualification or dedication file.
1.180-38

 1. Identification of the equipment

 2. Specifications on the equipment

 3. Identification of safety functions to be demonstrated by test data

 4. Test plan

 5. Test results, including

5.1 Objective of the test

5.2 Detailed description of test item

5.3 Description of test setup, instrumentation, and calibration data

5.4 Test procedure

5.5 Summary of test data, accuracy, and anomalies

 6. The installation practices employed and administrative controls established to alleviate

potential EMI/RFI and power surge exposure

 7. Summary and conclusions

 8. Approval signature and date.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the

NRC staff’s plans for using this regulatory guide. No backfitting is intended or approved in connection

with the issuance of this guide. 

Except when an applicant or licensee proposes or has previously established an acceptable

alternative method for complying with the specified portions of the NRC’s regulations, the methods

described in this guide will be used in the evaluation of submittals in connection with applications for

construction permits, operating licenses, and combined licenses. This guide will also be used to evaluate

submittals from operating reactor licensees who propose system modifications that are voluntarily initiated

by the licensee if there is a clear connection between the proposed modifications and this guidance.
1

 International Electrotechnical Commission documents are available from the IEC at 3 rue de Varembe, PO Box 131, 1211

Geneva 20, Switzerland.

1.180-39

REFERENCES

CISPR 11, “Industrial, Scientific, and Medical Radio-Frequency Equipment—Electromagnetic

Disturbance Characteristics—Limits and Methods of Measurement,” International Special Committee on

Radio Interference, 1997.1

IEC 61000-3-2, “Electromagnetic Compatibility (EMC) - Part 3-2: Limits–Limits for Harmonic Current

Emissions,” International Electrotechnical Commission, 2001.1

IEC 61000-3-4, “Electromagnetic Compatibility (EMC) - Part 3-4: Limits–Limitation of Emission of

Harmonic Currents in Low-voltage Power Supply Systems for Equipment with Rated Current Greater

than 16 A,” International Electrotechnical Commission, 1998.1

IEC 61000-4-1, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 1: Overview of Immunity Tests," International Electrotechnical Committee, 1992.1

IEC 61000-4-2, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 2: Electrostatic Discharge Immunity Test," International Electrotechnical Committee, 1995.1

IEC 61000-4-3, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 3: Radiated, Radio-Frequency, Electromagnetic Field Immunity Test," International

Electrotechnical Committee, 1995.1

IEC 61000-4-4, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 4: Electrical Fast Transient/Burst Immunity Test," International Electrotechnical Committee,

1995.1

IEC 61000-4-5, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 5: Surge Immunity Test," International Electrotechnical Committee, 1995.1

IEC 61000-4-6, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 6: Immunity to Conducted Disturbances, Induced by Radio-Frequency Fields," International

Electrotechnical Committee, 1996.1

IEC 61000-4-7, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 7: General Guide on Harmonics and Interharmonics Measurements and Instrumentation, for

Power Supply Systems and Equipment Connected Thereto," International Electrotechnical Committee,

1991.1
2

 IEEE publications may be purchased from the IEEE Service Center, 445 Hoes Lane, Piscataway, NJ 08855.

1.180-40

IEC 61000-4-8, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 8: Power Frequency Magnetic Field Immunity Test," International Electrotechnical Committee,

1993.1

IEC 61000-4-9, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement Techniques,

Section 9: Pulse Magnetic Field Immunity Test," International Electrotechnical Committee, 1993.1

IEC 61000-4-10, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement

Techniques, Section 10: Damped Oscillatory Magnetic Field Immunity Test," International

Electrotechnical Committee, 1993.1

IEC 61000-4-11, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement

Techniques, Section 11: Voltage Dips, Short Interruptions, and Voltage Variations Immunity Test,"

International Electrotechnical Committee, 1994.1

IEC 61000-4-12, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement

Techniques, Section 12: Oscillatory Waves Immunity Tests," International Electrotechnical Committee,

1996.1

IEC 61000-4-13, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement

Techniques, Section 13: Immunity to Harmonics and Interharmonics," International Electrotechnical

Committee, 1998.1

IEC 61000-4-16, “Electromagnetic Compatibility (EMC) - Part 4: Testing and Measurement

Techniques, Section 16: Test for Immunity to Conducted, Common Mode Disturbances in the Frequency

Range 0 Hz to 150 kHz," International Electrotechnical Committee, 1998.1

IEC 61000-6-4, "Electromagnetic Compatibility (EMC) - Part 6: Generic Standards, Section 4: Emission

Standard for Industrial Environments,” International Electrotechnical Committee, 1997.1

IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Institute

of Electrical and Electronics Engineers, issued 1971.2

IEEE Std 473-1985, “IEEE Recommended Practice for an Electromagnetic Site Survey (10 kHz to 10

GHz),” Institute of Electrical and Electronics Engineers, issued 1985, reaffirmed 1997.2

IEEE Std 518-1982, “IEEE Guide for the Installation of Electrical Equipment To Minimize Noise Inputs

to Controllers from External Sources,” Institute of Electrical and Electronics Engineers, issued 1982,

reaffirmed 1996.2
3

 Military Standards are available from the Department of Defense, Standardization Documents Order Desk, Building 4D, 700

Robbins Avenue, Philadelphia, PA 19111-5094.

4

 Copies are available at current rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328

(telephone (202)512-1800); or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road,

Springfield, VA 22161; (<http://www.ntis.gov/ordernow>; telephone (703)487-4650;. Copies are available for inspection or

copying for a fee from the NRC Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDR’s mailing address is

USNRC PDR, Washington, DC 20555; telephone (301)415-4737 or (800)397-4209; fax (301)415-3548; email is

PDR@NRC.GOV.

1.180-41

IEEE Std 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations,” Institute of

Electrical and Electronics Engineers, issued 1991.2

IEEE Std 665-1995, “IEEE Guide for Generating Station Grounding,” Institute of Electrical and

Electronics Engineers, issued 1995, reaffirmed 2001.2

IEEE Std 1050-1996, “IEEE Guide for Instrumentation and Control Equipment Grounding in Generating

Stations,” Institute of Electrical and Electronics Engineers, issued 1996.2

IEEE Std C62.41-1991, “IEEE Recommended Practice on Surge Voltages in Low-Voltage AC Power

Circuits,” Institute of Electrical and Electronics Engineers, issued 1991, reaffirmed 1995.2

IEEE Std C62.45-1992, “IEEE Guide on Surge Testing for Equipment Connected to Low-Voltage AC

Power Circuits,” Institute of Electrical and Electronics Engineers, issued 1992, reaffirmed in 1997.2

MIL-STD-461C, “Electromagnetic Emission and Susceptibility Requirements for the Control of

Electromagnetic Interference,” Department of Defense, August 4, 1986.3

MIL-STD-461D, “Electromagnetic Emission and Susceptibility Requirement for the Control of

Electromagnetic Interference,” Department of Defense, January 11, 1993.3

MIL-STD-461E, “Requirements for the Control of Electromagnetic Interference Characteristics of

Subsystems and Equipment,” U.S. Department of Defense, August 20, 1999.3

MIL-STD-462, “Measurement of Electromagnetic Interference Characteristics,” Department of Defense,

July 31, 1967.3

MIL-STD-462D, “Measurement of Electromagnetic Interference Characteristics, Department of

Defense, Jan 11, 1993.3

NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power

Plants,” Chapter 7, “Instrumentation and Controls,” USNRC, June 1997.4

NUREG/CR-5609, “Electromagnetic Compatibility Testing for Conducted Susceptibility Along

Interconnecting Signal Lines,” USNRC, August 2003.4
5

 Copies are available for inspection or copying for a fee from the NRC Public Document Room at 11555 Rockville Pike (first

floor), Rockville, MD; the PDR’s mailing address is USNRC PDR, Washington, DC 20555; telephone (301)415-4737 or 1-

(800)397-4209; fax (301)415-3548; e-mail <PDR@NRC.GOV>.

6

 EPRI publications may be purchased from the EPRI Distribution Center, 207 Coggins Drive, P.O. Box 23205, Pleasant Hill,

CA 94523, telephone (510) 934-4212.

1.180-42

NUREG/CR-5700, “Aging Assessment of Reactor Instrumentation and Protection System

Components,” USNRC, July 1992.4

NUREG/CR-5904, “Functional Issues and Environmental Qualification of Digital Protection Systems of

Advanced Light-Water Nuclear Reactors,” USNRC, April 1994.4

NUREG/CR-5941, “Technical Basis for Evaluating Electromagnetic and Radio-Frequency Interference

in Safety-Related I&C Systems” April 1994.4 

NUREG/CR-6431, “Recommended Electromagnetic Operating Envelopes for Safety-Related I&C

Systems in Nuclear Power Plants,” USNRC, April 1999.4 

NUREG/CR-6436, “Survey of Ambient Electromagnetic and Radio-Frequency Interference Levels in

Nuclear Power Plants,” USNRC, November 1996.4

NUREG/CR-6406, “Environmental Testing of an Experimental Digital Safety Channel,” USNRC,

September 1996.4 

NUREG/CR-6579, “Digital I&C Systems in Nuclear Power Plants: Risk-Screening of Environmental

Stressors and a Comparison of Hardware Unavailability With an Existing Analog System,” USNRC,

January 1998.4

NUREG/CR-6782, “Comparison of U.S. Military and International Electromagnetic Compatibility

Guidance,” USNRC, August 2003.4

Safety Evaluation Report (SER), issued by USNRC by letter dated April 17, 1996, to Carl Yoder,

EPRI, from Eric Lee, NRC, Subject: Review of EPRI Utility Working Group Topical Report

TR-102323, "Guidelines for Electromagnetic Interference Testing in Power Plants."5

TR-102323, “Guidelines for Electromagnetic Interference Testing in Power Plants,” Electric Power

Research Institute (EPRI) topical report, September 1994.6
1

 IEEE publications may be purchased from the IEEE Service Center, 445 Hoes Lane, Piscataway, NJ 08855.

2

 Requests for single copies of draft or active regulatory guides (which may be reproduced) or for placement on an automatic

distribution list for single copies of future draft guides in specific divisions should be made in writing to the U.S. Nuclear

Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to

(301)415-2289; email <DISTRIBUTION@NRC.GOV>. Copies are available for inspection or copying for a fee from the NRC

Public Document Room at 11555 Rockville Pike (first floor), Rockville, MD; the PDR’s mailing address is USNRC PDR,

Washington, DC 20555; telephone (301)415-4737 or 1-(800)397-4209; fax (301)415-3548; e-mail <PDR@NRC.GOV>.

3

 EPRI publications may be purchased from the EPRI Distribution Center, 207 Coggins Drive, P.O. Box 23205, Pleasant Hill,

CA 94523, telephone (510) 934-4212.

4

 Copies are available for inspection or copying for a fee from the NRC Public Document Room at 11555 Rockville Pike (first

floor), Rockville, MD; the PDR’s mailing address is USNRC PDR, Washington, DC 20555; telephone (301)415-4737 or 1-

(800)397-4209; fax (301)415-3548; e-mail <PDR@NRC.GOV>.

1.180-43

REGULATORY ANALYSIS

1. PROBLEM

Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50), “Domestic Licensing of

Production and Utilization Facilities,” delineates the NRC’s design and qualification regulations for

commercial nuclear power plants. Appendix A, “General Design Criteria for Nuclear Power Plants,” to

10 CFR Part 50 “establishes minimum requirements for the principal design criteria for water-cooled

nuclear power plants,” and 10 CFR 50.55a(h) requires that reactor protection systems also satisfy the

criteria of the Institute of Electrical and Electronics Engineers (IEEE) standard (Std) 603-1991, “Criteria

for Safety Systems for Nuclear Power Generating Stations,”1 or IEEE Std 279-1971, ?Criteria for

Protection Systems for Nuclear Power Generating Stations,”1 contingent on the date of construction

permit issuance. In particular, General Design Criterion (GDC) 4 in Appendix A to 10 CFR Part 50

requires that structures, systems, and components be designed “to accommodate the effects of and to be

compatible with the environmental conditions associated with normal operation, maintenance, testing, and

postulated accidents, including loss-of-coolant accidents.” Furthermore, 10 CFR 50.49 and

50.55a(a)(1) address verification measures such as testing that can be used to confirm the adequacy of

design. 

While these regulations address environmental compatibility for electrical equipment that is

important to safety, they do not explicitly identify approaches to establishing electromagnetic compatibility

(EMC). As a result, Regulatory Guide 1.180, “Guidelines for Evaluating Electromagnetic and RadioFrequency Interference in Safety-Related Instrumentation and Control Systems,”2

 was developed to

identify practices acceptable to the NRC staff that can be employed to establish EMC for safety-related

instrumentation and control (I&C) systems in nuclear power plants. In addition, Electric Power Research

Institute (EPRI) topical report TR-102323, “Guidelines for Electromagnetic Interference Testing in

Power Plants,”3 was accepted in a Safety Evaluation Report (SER) by letter dated April 17, 1996,4 with

some exceptions and clarifications. The guidance offered in the regulatory guide and the SER constitute

consistent approaches to addressing issues of EMC for safety-related digital I&C systems in nuclear

power plants, with each serving as equally valid, acceptable methods. However, experience in the

nuclear industry has indicated some concern that the available guidance incorporates some conservatism

that could be reduced through development of an enhanced technical basis. In addition, certain EMC
5

 Military Standards are available from the Department of Defense, Standardization Documents Order Desk, Building 4D, 700

Robbins Avenue, Philadelphia, PA 19111-5094.

6

 International Electrotechnical Commission documents are available from the IEC at 3 rue de Varembe, PO Box 131, 1211

Geneva 20, Switzerland.

1.180-44

considerations (i.e., radiated emissions and susceptibility in the frequency band from 1 to 10 gigahertz and

conducted susceptibility along signal lines) have been identified by the NRC staff and the EPRI EMI

Working Group as open issues that should be addressed. Finally, a revised complete series of EMC

standards by the International Electrotechnical Commission (IEC), which has been issued recently,

warrants consideration for use by the U.S. nuclear power industry. The need to develop and maintain

specific practices for the nuclear power industry to address the effects of EMI/RFI and power surges on

safety-related I&C systems is stated in SECY-91-273, “Review of Vendors’ Test Programs To Support

the Design Certification of Passive Light Water Reactors.”4

2. ALTERNATIVE APPROACHES

The existing guidance is based on military and industrial methods for ensuring the compatibility of

I&C equipment with the electromagnetic conditions to which they are subjected in nuclear power plants. 

This guidance relies on consensus standards in the EMC community to ensure widespread familiarity and

reasonable levels of agreement. Recently, the U.S. Department of Defense (DoD) issued a revision of

the EMC testing standards, replacing military standard (MIL-STD) 461D and 462D with MIL-STD

461E.5 In addition, the IEC has revised the complete series of standards (IEC 61000)6 that offer a

potential alternative to the military EMC standards. The approach taken was to evaluate the recent

standards to establish conditions under which they can be applied as equivalent suites of test methods that

are relevant to the nuclear power plant electromagnetic environment. The revised standards contain test

methods that are applicable for assessing conducted susceptibility along signal lines so that issue was

addressed. The issue of high-frequency radiated EMC was also addressed with the identification of test

methods that are applicable for assessing radiated emissions and susceptibility above 1 GHz. The

alternative approach considered was to take no action and retain the existing guidance for EMC at

nuclear power plants. Thus, the two approaches considered are:

1. Take no action,

2. Update the existing guidance through development of an enhanced technical basis.

The first alternative, taking no action, requires no additional cost for the NRC staff or applicants

over current conditions since no change to the process would occur. The existing guidance in the

regulatory guide and SER provides clear, systematic approaches that are acceptable for ensuring

electromagnetic compatibility. However, the guidance endorses dated versions of EMC standards that

have been superseded by recent revisions. While there is currently substantial experience among testing

laboratories with the test methods from the previous versions of the standards, it is anticipated that such

capabilities will diminish in a few years as most industries adopt the methods of the current versions. 

Thus, taking no action places the responsibility for justifying the use of the most recent domestic and

international standards on the applicants at some future time. Continuing with the existing guidance

unchanged does not address the issues of high-frequency radiated EMC and conducted susceptibility
1.180-45

along signal lines. As a result, the process of establishing EMC for safety-related I&C modifications of

new installations may involve significant effort on the part of the applicant to anticipate the type and level

of evidence that is acceptable to the NRC staff to demonstrate compatibility of equipment in response to

these phenomena. In addition, the NRC staff review may involve considerable effort in evaluating

submitted approaches for addressing the open issues and reviewing the use of the revised standards on a

case-by-case basis. 

The second alternative, updating the existing guidance by developing an enhanced technical basis,

was considered. Consensus standards on methods for establishing EMC are available and represent

current good practice as agreed upon by responsible professionals in the U.S. military and industrial

(domestic and international) EMC community. These standards are maintained by their respective

standards bodies and each revision permits refinement of the consensus positions and improvement of the

standards through the resolution of open issues. Endorsing the current version of EMC standards allows

the staff and applicants to obtain the benefit of the work of responsible EMC professional standards

committee volunteers. In addition to the availability of a revised EMC standard from the U.S. DoD, the

recent completion of a series of international EMC standards by IEC offers the opportunity to introduce

greater flexibility in the choice of acceptable methods. Also, the issues related to high-frequency radiated

EMC and conducted susceptibility along signal lines can be addressed through identification of acceptable

test methods in the recent EMC standards. Adopting this approach requires NRC staff effort to review

the revised or new standards to select for endorsement those criteria and methods that address EMC

issues of concern for safety-related I&C systems in nuclear power plants. In addition, NRC staff effort

for this approach includes a review of existing evidence characterizing the electromagnetic conditions at

nuclear power plants and the rationale for electromagnetic operating envelopes to determine whether any

conservatism can be identified and justifiably reduced (i.e., by relaxing the operating envelopes as

warranted). The level of effort for each application is reduced for both NRC staff and applicant over that

involved with Alternative 1 because systematic review and endorsement of current standards by NRC

staff and up-front resolution of open EMC issues is a more effective use of resources than an ad hoc,

case-by-case method of handling the transition to recent standards that more fully address the range of

EMC issues. The result of this approach is an up-to-date, more complete guide on acceptable EMC

practices with the flexibility to select among suites of test methods from domestic and international

standards. Of course, the applicant retains the flexibility to establish an equivalent technical basis for

different criteria and operating envelopes by performing its own detailed assessment of the

electromagnetic conditions at the point of installation and evaluating any emerging practices.
1.180-46

3. VALUES AND IMPACTS

Values and impacts for each of the two identified approaches are analyzed below. In this

analysis, the probability of an alternative approach having a positive effect on EMC and the probability of

that effect on the achievement of overall safety goals are not known quantitatively. However, based on a

qualitative assessment of experience in the military and commercial industries, as well as the nuclear

industry, EMI/RFI and power surges clearly hold the potential for inducing an undesirable safety

consequence. Therefore, a positive correlation between EMC and the achievement of safety goals is

inferred from the negative effects of EMI/RFI and power surge susceptibility. Thus, EMC is a necessary

but not wholly sufficient factor by itself in achieving safety goals. 

In the summary below, an impact is a cost in schedule, budget, or staffing or an undesired

property or attribute that would accrue from taking the proposed approach. Both values and impacts

may be functions of time.

3.1 Alternative 1—Take No Action

This alternative has the attraction that its initial cost is low since there are no “start-up” activities. 

However, the burden of establishing the technical basis for the suitability of revised or new EMC

standards would rest with the applicants. In addition, it would remain for the applicant to determine what

practices, test criteria, and test methods are necessary to resolve the issues of high-frequency radiated

EMC and conducted susceptibility along signal lines. NRC staff would have to act on a case-by-case

basis for applications or requests to review safety questions involving the open issues or employing

unreviewed versions of EMC standards. The absence of a clearly established technical basis regarding

use of these revised standards or the resolution of these open issues could have adverse effects on the

level of staff effort required to conduct reviews or to ensure consistency among reviews of the EMC for

each I&C system modification. Thus, NRC staff review could take longer and require greater effort. 

From the applicant’s perspective, the marketplace will ultimately drive the industry to use the revised or

new standards as the testing resources that support the older standards diminish. As a result, the absence

of guidance regarding the revised standards and the open issues could lead to higher costs for the

applicants because of potential unknowns associated with demonstrating compliance with regulations

using unreviewed methods. Thus, although the initial cost would apparently be low, taking no action

could result in greater total costs, both to the NRC staff and the applicant, during the safety evaluation

process.

Value – No value beyond the status quo

Impact – Schedule, budget, and staffing cost, to the staff and applicant, associated with remaining

regulatory uncertainty regarding technical basis for use of revised or new standards and

resolution of open issues on a case-by-case basis
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3.2 Alternative 2—Update Existing Guidance

If the NRC staff endorses revised or new consensus EMC standards on the basis of a systematic

review, the staff and applicants obtain the benefit of the effort of expert professional organizations to

establish methods and practices to achieve and assess EMC. In addition, the update of the existing

guidance provides the opportunity to address open issues and reduce conservatism as warranted. The

cost of this approach involves NRC staff effort in reviewing the revised or new EMC standards,

identifying practices to address the open issues, and reevaluating the technical basis for plant operating

envelopes. Given the participation of NRC staff members on standards committees that are considered

to address issues important to safety, this cost can be kept to a minimum. The value in this alternative is

the common understanding between the NRC staff and applicants of approaches that have current

acceptance as good practice in the expert technical community. The benefit of this approach would be a

more comprehensive understanding of current EMC practices by the NRC staff and reduction of the

burden on the applicants. From the applicant’s perspective, a clear determination of acceptable

resolutions to open EMC issues, the flexibility of using methods from current domestic and international

EMC standards, and the potential reduction in conservatism would reduce the regulatory burden.

Value – Maintenance and evolution of the current definition of good practices by the EMC

community in military and commercial industries

– Probable improvement in the likelihood of achieving safety goals as a consequence of

resolution of open EMC issues

– Greater flexibility added in establishing EMC through the endorsement of equivalent

suites of test methods from both domestic and international standards

– Reduction of conservatism in existing guidance as warranted by the enhanced

technical basis

Impact – Staff cost of evaluating revised or new EMC practices for endorsement

– Reduction of burden for applicants

4. CONCLUSIONS

There is clear evidence that the electromagnetic conditions can adversely affect the performance

of safety-related I&C equipment. The Code of Federal Regulations requires that systems, structures,

and components important to safety be compatible with and accommodate the effects of environmental

conditions associated with nuclear power plant service conditions. EMC is an element of addressing that

requirement. Addressing open EMC issues and adopting improved or revised consensus practices,

where the safety case is maintained, can enhance the assurance of safety while potentially reducing

regulatory burden. Two approaches to maintaining existing EMC guidance were examined. 

Taking no action may result in accumulating regulatory expense as applicants propose ad hoc

solutions to open EMC issues or adopt unreviewed methods from revised or new standards as the basis

for providing evidence to the staff that safety-related equipment is compatible with the electromagnetic

conditions at the site and, thus, meet the requirements of NRC’s regulations. 
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General endorsement of military and commercial EMC standards addresses the stated problem

with good value and minimal impact. However, regulatory uncertainty regarding the applicability of each

technical element embodied in the standards and the means to adequately determine the electromagnetic

service conditions could still lead to accumulating regulatory expense as applicants submit proposed

methods based on the general practices for staff review. Eventually, a de facto standard set of practices

would emerge through an inefficient review process. 

The second alternative, updating the existing guidance through development of an enhanced

technical basis, provides good value with minimal impact. While this approach involves some additional

NRC staff effort, it maintains the long-term relevance of the existing guidance through adoption of current

versions of EMC standards, introduces greater flexibility in the generation of the safety case by offering

the option of equivalent suites of test methods from domestic and international EMC standards, and

reduces the potential burden on the applicants by addressing open EMC issues in a systematic manner

and reducing conservatism as warranted by the enhanced technical basis. Therefore, the second

alternative provides the highest value with reasonable impact on NRC staff and the greatest potential for

reducing the regulatory burden for applicants. Note that neither of these approaches present new

regulatory requirements; they define acceptable approaches for meeting existing requirements.

5. DECISION RATIONALE

Based on the highest value and reasonable impact for problem solution capability (especially

regulatory burden), the second alternative, updating existing guidance by developing an enhanced

technical basis, has been chosen. The highest value will be achieved by reviewing revised and new

consensus EMC standards (both domestic and international), assessing the applicability and equivalence

of each technical element embodied in the standards, reevaluating the electromagnetic environment

characteristic of nuclear power plants and the technical basis for the current operating envelopes,

determining testing methods that can address the open EMC issues, and identifying equivalent suites of

test methods from the alternative standards and the conditions under which they may be applied. This

approach will contribute to satisfying the safety goal for nuclear power plants.