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{{Adams
{{Adams
| number = ML12305A261
| number = ML003740293
| issue date = 08/31/1977
| issue date = 06/30/1988
| title = Seismic Qualification of Electric Equipment for Nuclear Power Plants.
| title = (Task Ee 108-6), Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/OSD, NRC/RES
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.100, Rev. 1
| document report number = RG-1.100, Revision 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 3
| page count = 4
}}
}}
{{#Wiki_filter:Revision I August 1977 U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:Revision 2
COMMISSION
.4 o%"
REGULATORY  
U.S. NUCLEAR REGULATORY COMMISSION
GUIDE OFFICE OF STANDARDS
June 1988
DEVELOPMENT
!REGULATORY GUIDE
REGULATORY  
OFFICE OF NUCLEAR REGULATORY RESEARCH
GUIDE 1.100 SEISMIC QUALIFICATION  
REGULATORY GUIDE 1.100  
OF ELECTRIC EQUIPMENT  
(Task EE 108-5)
FOR NUCLEAR POWER PLANTS  
SEISMIC QUALIFICATION OF ELECTRIC AND MECHANICAL EQUIPMENT  
FOR NUCLEAR POWER PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
Criterion III, "Design Control," of Appendix B,"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires, among other things, that design control measures provide for verifying the adequacy of design such as by the performance of a suitable testing program. Where a test program is used to verify the adequacy of a specific design feature, it is required to include suitable qualification testing of a prototype unit under the most adverse design condi-tions. This regulatory guide describes a method ac-ceptable to the NRC staff for complying with the Commission's regulations with respect to verifying the adequacy of the seismic design of electric equip-ment for all types of nuclear power plants. The Ad-visory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
The Commission's regulations in 10 CFR Part 50,
"Domestic licensing of Production and Utilization Facilities," require that certain structures, systems, and components in a nuclear power plant be designed to withstand the effects of natural phenomena such as earthquakes and that design control measures such as testing be used to check the adequacy of design. This general requirement Is contained in Appendix A, "Gen eral Design Criteria for Nuclear Power Plants," to Part
50; in Criterion IIl, "Design Control," and Criterion XVII, "Quality Assurance Records," of Appendix B,  
"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to Part 50; and in Appendix A, "Seismic and Geologic Siting Criteria for Nuclear Power Plants," to Part 100, "Reactor Site Criteria."
In Appendix A to 10 CFR Part 100, Section VI,
"Application to Engineering Design," requires that the nuclear power plant be designed so that, if the safe shutdown earthquake occurs, certain structures, systems, and components will remain functional. These safety related structures, systems, and components are those necessary to ensure (1) the integrity of the reactor cool ant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe condition, or (3)
the capability to prevent or mitigate the consequences of accidents that could result in offsite exposures comparable to the Part 100 guideline
 
====s. In Appendix A ====
to Part 100, Section VI(aX2) requires that structures, systems, and components of the nuclear power plant necessary for continued operation without-undue risk to the health and safety of the public be designed to re main functional and within applicable. stress and defor mation limits when subjected to the effects of the vibratory motion of an operating basis earthquake in combination with normal operating loads. The engineer-'
Ing method used to ensure that the required safety'
functions are maintained during and after the vibratoryF
ground motion associated with the safe shutdown earth-'
quake or the operating basis earthquake must involve%
the use of either a suitable dynamic analysis or a suit able qualification test to demonstrate that structures,;
systems, and components can withstand the seismic and other concurrent loads.
 
This regulatory guide describes a method acceptable to the NRC staff for complying with NRC's regulations with respect to seismic qualification of electric and mechanical equipment.
 
The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
 
Any information collection activities mentioned in this regulatory guide are contained as requirements in
10 CFR Parts 50 or 100, which provide the regulatory basis for this guide. The information collection require ments in 10 CFR Parts 50 and 100 have been cleared under OMB Clearance Nos. 3150-0011 and 3150-0093, respectively.


==B. DISCUSSION==
==B. DISCUSSION==
IEEE Std 344-1975f (revision of IEEE Std 344-1971), "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations," dated January 31, 1975, was prepared by Working Group 2.5 (Seismic Qualification)  
IEEE  
of Subcommittee  
Std 344-1987, "Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations,"* was prepared by Working Group 2.5 (Seismic Qualification) of Subcommittee 2 (Equipment Qualification) of the Institute of Electrical  
2 (Equipment Qualification)  
*Copies may be obtained from the Institute of Eectdlcal and Electronics Engineers, IEEE Service Center, "S4 Hoes Lane, P.O. Box 1331, Plscataway, NJ 08855.
of the Institute of Electrical and Electronics Engineers (IEEE) Nuclear Power Engineering Committee and was subsequently ap-proved by the IEEE Standards Board on December 20, 1974.*Lines indicate substantive changes from previous issue.'Copies may be obtained from the Institute of Electrical and Electronics Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y. 10017.The provisions of the standard include principles, procedures, and methods of seismic qualification which, when satisfied, will confirm the adequacy of the equipment design for the performance of Class I E functions during and after the time the equipment is subjected to the forces resulting from one safe shut-down earthquake (SSE) preceded by a number of operating basis earthquakes (OBE0s). The standard contains requirements indicated by the verbs "shall" and "must" and recommendations indicated by"should." The standard, which is an ancillary standard of IEEE Std 323-1974, "IEEE Standard for Qualifying Class I E Equipment for Nuclear Power Generating Stations," (endorsed, with exceptions, by Regulatory Guide 1.89, "Qualification of Class IE Equipment for Nuclear Power Plants"), supplements part of the test methods required and references the margins given in IEEE Std 323-1974.C. REGULATORY
POSITION Conformance with the requirements and recom-mendations specified by IEEE Std 344-1975'
for con-ducting seismic qualification of Class 1 E equipment, when such qualification is performed in conjunction with Regulatory Guide 1.89, provides an adequate basis for complying with design verification require-ments of Criterion III of Appendix B to 10 CFR Part 50 with respect to verifying the seismic adequacy of electric equipment, subject to the following:
1. As indicated in Section 5.3, "Static Coefficient Analysis," a static coefficient of 1.5 is used for equip-ment analysis to take into account the effects of both multi frequency excitation and multimode response.The use of 1.5 as the static coefficient is acceptable for verifying structural integrity of frame-type struc-USNRC REGULATORY
GUIDES Comments should be sent to the Secretary of the Commission, US. Nuclear Regu-latory Commission, Washington, D.C. 20555, Attention:
Docketing and Service Regulatory Guides are issued to describe and make available to the Public methods Branch.acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions:
or postulated accidents, or to provide guidance to applicants.


Regulatory Guides are not substitutes for regulations, and compliance with them is not required.
USNRC REGULATORY GUIDES
The guides are Issued In the following ten broad divisions:
Regulatory Guides am Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing


1. Power Reactors 6. Products Methods and solutions different from those set Out in the guides wil be accept- 2. Research and Test Reactors 7. Transportation able if they provide a basis for the findings requisite to the issuance or continuance
===1. Power Reactors ===
6. Products specific parts of the CommIsslon's regulations, to delineate tech-  
2. Research and Test Reactors  
7. Transportation nlques used bY the staff In evaluating specific problems or postu-
3. Fuels and Materials Facilities  
3. Fuels and Materials Facilities  
8. Occupational Health of a permit or license by the Commission.
8. Occupational Health lated accidents, or to provide guidance to applicant
 
====s. Regulatory ====
4. Environmental and Siting
9. Antitrust and Financial Review Guldes are not substitutes for regulations, and compliance witn
5. Materials and Plant Protection 10. General them Is not required. Methods and solutions different from those met out In the guides will be acceptable If they. provide a basis for the findingreusttoteIsacoroniunefapemtr Copies of issued guides may be purchased from the Government lningse eCommission.-
Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of ThIs guide was Issued after consideration of comments received from Documents. U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for Improvements In these
37082. Washington. DC 20013-7082. telephone (202)275-2060 or guides are encouraged at all times, and guides will be revised, as
(202)275-2171.
 
apiropriate, to accommodate comments and to reflect new Informa n or experience.
 
Issued guides may also be purchased from the National Technical Written comments may be submitted to the Rules and Procedures Information Service on a standing order basis. Details on this Branch.
 
DRR
ADM,
U.S.
 
Nuclear Regulatory Commission, service may be obtained by writing NTIS. 5285 Port Royal Road, Washington. DE 20555.
 
Springfield, VA 22161.


4. Environmental and Siting 9. Antitrust Review 5. Materials and Plant Protection
and Electronics Engineers (IEEE) Nuclear Power Engi neering Committee, and was subsequently approved by the IEEE Standards Board on June 11, 1987.
10. General Comments and suggestions for improvements in these guides are encouraged at all Requests for single copies of issued guides (which may be reproduced)  
or for place-times, and guides will be revised, as appropriate, to accommodate comments and ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience.


This guide was revised as a result of divisions should be made in writing to the US. Nuclear Regulatory Commission, substantive comments received from the public and additional staff review. Washington, D.C, 20555, Attention:
The IEEE standard includes principles, procedures, and methods of seismic qualification that, when satis fied, will confirm the adequacy of the equipment design for the performance of safety functions before, during, and after the time the safety-related equipment is subjected to high stresses resulting from design basis events. For this guide, the design basis events are the loadings imposed by seismic events: the operating basis earthquake (OBE) and the safe shutdown earthquake (SSE). It is also necessary to combine other dynamic or vibratory loads as part of seismic qualification. It is recognized that hydrodynamic loads have their primary energy content in a frequency range greater than that of seismic vibrations; however, they are a part of the inplant equipment aging process, along with other non seismic vibration loads, and therefore should be con sidered in seismic testin&
Director, Division of Document Control.
Revision I of this guide was issued in August 1977.


tures, such as members physically similar to beams and columns, that can be represented by a simple model. For equipment having configurations other than a frame-type structure, justification should be provided for use of a static coefficient.
Since then, several new technical issues have arisen, such as treatment of hydrodynamic loads, the limits of generic testing, the treatment of rattling, methods of qualifying line-mounted devices, and the use of actual seismic experience data bases to qualify identical or similar equipment. These issues are covered by IEEE
Std 344-1987, which reflects the state-of-the-art tech nology. Further, the NRC has extended the application of this standard to the qualification of mechanical equipment on an interim basis. In extending the applica tion of IEEE Std 344-1987 to mechanical equipment, the NRC staff recognizes that there are differences in qualification methods for electric and mechanical equipment.


2. Section 6.6.2.1, "Derivation of Test Input Motion," (concerning single-frequency test input motion) states that, for equipment with more than one predominant frequency, the shake table motion should produce a test response spectrum (TRS) ac-celeration at the test frequencies equal to 1.5 times the acceleration given by the specified required response spectrum (RRS) or less if justified.
Specifically, qualification of mechanical equipment by analysis is permitted when such equip ment can be modeled to adequately predict its response.


The sec-tion also states that the TRS need not envelop the RRS provided the factor of 1.5 is used.The use of a factor of 1.5 and the concept that the TRS need not envelop the RRS as a consequence of using 1.5 should not, in the absence of justifica- tion, be considered acceptable.
The American Society of Mechanical Engineers is cur rently developing a standard for seismic qualification of mechanical equipment. Upon publication of this stan dard, the NRC staff will review it for suitability for endorsement by a revision to this regulatory guide.


For example, in the event that the RRS is broad band, the use of single-frequency test input with a 1.5 magnification factor may not be adequate to excite all modes to the re-quired levels. For ensuring operability of an equip-ment under seismic event, the test input motion should closely simulate the characteristics of excita-tion. An equipment malfunction may not be governed by the level of stress but is frequently caused by the vibratory behavior of the response.
This regulatory guide covers two categories of equip ment: (1)
safety-related electric (Class IE) equipment.


As stated in Section 6.6.1 of the standard, one of the general requirements for a justifiable seismic test in-put is that the wave forms should produce a TRS that closely envelops the applicable portion of the RRS.This requirement is intended to ensure that all modes of an equipment are adequately and simultaneously excited to the required levels. Since the TRS produced by the single-frequency test input is narrow band and the RRS may be broad band, the use of single-frequency test input with a 1.5 magnification factor may not always be adequate to excite all modes of the equipment to the required levels. Thus it is necessary that the TRS closely envelop the applicable portion of the RRS to verify the adequacy of test in-put motion.3. In the absence of justification, those portions of Section 6.6.2.5, "Sine Sweep Test," which indicate that, for qualifying equipment using the sine sweep test input, the TRS must envelop the RRS according to the criteria described in Sections 6.6.2 and 6.6.2.1 should not be considered acceptable.
and safety-related mechanical equipment, and (2)- non safety-related equipment whose failure can prevent the satisfactory accomplishment of safety functions. Exam ples of mechanical equipment within the scope of this guide are valves, valve operators, pumps, compressors, chillers, air handlers, fans, blowers, fuel rod assemblies, and control rod drive mechanisms.


As stated in regulatory position 2, one of the re-quirements to ensure equipment operability is to ex-cite all modes of the equipment adequately and simultaneously to the required levels. One of the criteria used to verify the adequacy of the test input is to have the TRS enveloping the RRS as specified in Section 6.6.1 of the standard.
IEEE Std 344-1987 recognizes the use of justified experience data as a method for seismic qualification.


The sine sweep test may not be suitable for equipment qualification for the following reasons: a. For a fast sweep, even though the equipment may sense nearly simultaneous multimode effects, the duration for each mode to be excited may be too brief to induce adequate resonance as compared to the ac-tual excitations.
This method of qualification will be evaluated by the NRC staff on a case-by-case basis.


b. For a slow sweep, the effects are nearly excita-tion of one mode at a time. Even with the TRS being broad band and enveloping the RRS, the true sense of simultaneous multimode response is not provided.Sections 6.6.2 and 6.6.2.1 do not provide specific guidelines concerning either the sweep rate or a justifiable methodology to define the TRS for a sweep input motion.4. The requirements given in Section 8, "Documen-tation," should be supplemented by the following:
IEEE' Std 344-1987 references other standards that contain valuable information. Those referenced standards not endorsed by a regulatory guide or incorporated intoK
8.6 Malfunction Data If a malfunction as defined in Section 2,"Definitions," is experienced during any test, the ef-fect of that malfunction should be determined and documented in the test report.
the regulations, if used, are to be used in a manner consistent with current regulations.
 
==C. REGULATORY POSITION==
The procedures described by IEEE Std 344-1987,
"Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations," are acceptable to the NRC staff for satisfying the Commission's regulations pertaining to seismic qualification of electric and mechanical equipment subject to the following:
For mechanical equipment, thermal distortion effects on operability should be considered, and loads imposed by the attached piping should also be accounted for.
 
If dynamic testing of a pump or a valve assembly is impracticable, static testing of the assembly is acceptable provided that (1) the end loading& are applied and are equal to or greater than postulated event loads, (2) all dynamic amplification effects are accounted for, (3) the component is in the operating mode during and after the application of loads, and (4) an adequate analysis is made to show the validity of the static application of loads.


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose of this section is to provide informa-tion to applicants regarding the NRC staff's plans for using this regulatory guide.This guide reflects current NRC staff practice.Therefore, except in those cases in which the appli-cant proposes an acceptable alternative method for complying with the specified portions of the Commis-sion's regulations, the method described herein is be-ing and will continue to be used in the evaluation of submittals for construction permit applications until this guide is revised as a result of suggestions from the public or additional staff review.1.100-2 UNITED STATES NUCLEAR REGULATORY  
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.
COMMISSION
 
WASHINGTON, D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORY
Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described herein will be used in the evaluation of seismic qualification of electric and mechanical equipment for the following nuclear power plants:
COMMISSION
I. Plants for which the construction permit is issued after June 30, 1988,
LI I,~ ~ V--* P}}
2. Plants for which the operating license application is docketed after December 30, 1988,
3. Plants for which the applicant or licensee voluntarily commits to the provisions of this guide.
 
1.100-2
4
 
VALUE/IMPACT STATEMENT
BACKGROUND
IEEE Std 344-1975, "Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations," was approved by the IEEE
in January 1975. In August 1977, the NRC staff issued Revision 1 to Regulatory Guide 1.100, which endorsed IEEE Std 344-1975, subject to four exceptions. Since then the staff has worked with the IEEE in developing IEEE Std 344-1987. As a result of these efforts, the exceptions to IEEE Std 344-1975 have been satisfacto rily resolved.
 
IEEE Std 344-1987 also addresses several recent technical issues, for example, treatment of hydrody namic loads, the limits of generic testing,, the treatment of rattling, methods of qualifying line-mounted devices, and the use of actual seismic experience data bases to qualify identical or similar equipment. IEEE Std 344
1987 thus reflects the state-of-the-art technology.
 
Issuance of Revision 2 is consistent with the NRC
policy of evaluating the latest versions of national standards in terms of their suitability for endorsement by regulatory guides.
 
SUBSTANTIVE CHANGES
IEEE Std 344-1987 applies to seismic and dynamic qualification of Class IE (safety-related electric) equip ment. The nuclear industry has used this standard for seismic qualification of mechanical equipment as well.
 
The NRC staff recognizes this fact and intends to
"extend the application of this standard to seismic qualification of mechanical equipment by this regulatory guide. Specifically, this regulatory guide coven two categories of equipment: (1) safety-related electric (Class IE) equipment and safety-related mechanical equipment, and (2) non-safety-related equipment whose failure can prevent the satisfactory accomplishment of safety func tions. The regulatory position provides guidance for qualification of mechanical equipment that is consistent with current NRC practice.
 
Regulatory Positions C.1 to C.4 in Revision 1 are not included in Revision 2 because they have been incorpo rated in IEEE Std 344-1987 as follows:
Regulatory Position in Rev. I of this Guide IEEE Std 344-1987 Section Number C.l
6.3 C.2
7.6.2.1 C.3
7.6.2.5 C.4
10.3.2(6)
VALUE
This guide endorses the latest version of a national standard and reflects the current state-of-the-art tech nology. The guide should also enhance the licensing process.
 
IMPACT
Although the scope of this revision has been ex tended to include seismic qualification of mechanical equipment, the requirements are consistent with NRC
current licensing practice. Thus, this regulatory guide does not impose any new requirements or costs on licensees or applicants.
 
1.100-3
 
UNITED STATES  
NUCLEAR REGULATORY COMMISSION  
WASHINGTON, D.C. 20555 OFFICIAL BUSINESS  
PENALTY FOR PRIVATE USE, $300
FIRST CLASS MAIL
APOIAGE
I FEES PAID  
USNRC
PERMIT N. G
111}}


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Latest revision as of 02:06, 17 January 2025

(Task Ee 108-6), Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants
ML003740293
Person / Time
Issue date: 06/30/1988
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.100, Revision 2
Download: ML003740293 (4)
v • d • e


Revision 2

.4 o%"

U.S. NUCLEAR REGULATORY COMMISSION

June 1988

!REGULATORY GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 1.100

(Task EE 108-5)

SEISMIC QUALIFICATION OF ELECTRIC AND MECHANICAL EQUIPMENT

FOR NUCLEAR POWER PLANTS

A. INTRODUCTION

The Commission's regulations in 10 CFR Part 50,

"Domestic licensing of Production and Utilization Facilities," require that certain structures, systems, and components in a nuclear power plant be designed to withstand the effects of natural phenomena such as earthquakes and that design control measures such as testing be used to check the adequacy of design. This general requirement Is contained in Appendix A, "Gen eral Design Criteria for Nuclear Power Plants," to Part

50; in Criterion IIl, "Design Control," and Criterion XVII, "Quality Assurance Records," of Appendix B,

"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to Part 50; and in Appendix A, "Seismic and Geologic Siting Criteria for Nuclear Power Plants," to Part 100, "Reactor Site Criteria."

In Appendix A to 10 CFR Part 100, Section VI,

"Application to Engineering Design," requires that the nuclear power plant be designed so that, if the safe shutdown earthquake occurs, certain structures, systems, and components will remain functional. These safety related structures, systems, and components are those necessary to ensure (1) the integrity of the reactor cool ant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe condition, or (3)

the capability to prevent or mitigate the consequences of accidents that could result in offsite exposures comparable to the Part 100 guideline

s. In Appendix A

to Part 100,Section VI(aX2) requires that structures, systems, and components of the nuclear power plant necessary for continued operation without-undue risk to the health and safety of the public be designed to re main functional and within applicable. stress and defor mation limits when subjected to the effects of the vibratory motion of an operating basis earthquake in combination with normal operating loads. The engineer-'

Ing method used to ensure that the required safety'

functions are maintained during and after the vibratoryF

ground motion associated with the safe shutdown earth-'

quake or the operating basis earthquake must involve%

the use of either a suitable dynamic analysis or a suit able qualification test to demonstrate that structures,;

systems, and components can withstand the seismic and other concurrent loads.

This regulatory guide describes a method acceptable to the NRC staff for complying with NRC's regulations with respect to seismic qualification of electric and mechanical equipment.

The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

Any information collection activities mentioned in this regulatory guide are contained as requirements in

10 CFR Parts 50 or 100, which provide the regulatory basis for this guide. The information collection require ments in 10 CFR Parts 50 and 100 have been cleared under OMB Clearance Nos. 3150-0011 and 3150-0093, respectively.

B. DISCUSSION

IEEE Std 344-1987, "Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations,"* was prepared by Working Group 2.5 (Seismic Qualification) of Subcommittee 2 (Equipment Qualification) of the Institute of Electrical

  • Copies may be obtained from the Institute of Eectdlcal and Electronics Engineers, IEEE Service Center, "S4 Hoes Lane, P.O. Box 1331, Plscataway, NJ 08855.

USNRC REGULATORY GUIDES

The guides are Issued In the following ten broad divisions:

Regulatory Guides am Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing

1. Power Reactors

6. Products specific parts of the CommIsslon's regulations, to delineate tech-

2. Research and Test Reactors

7. Transportation nlques used bY the staff In evaluating specific problems or postu-

3. Fuels and Materials Facilities

8. Occupational Health lated accidents, or to provide guidance to applicant

s. Regulatory

4. Environmental and Siting

9. Antitrust and Financial Review Guldes are not substitutes for regulations, and compliance witn

5. Materials and Plant Protection 10. General them Is not required. Methods and solutions different from those met out In the guides will be acceptable If they. provide a basis for the findingreusttoteIsacoroniunefapemtr Copies of issued guides may be purchased from the Government lningse eCommission.-

Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of ThIs guide was Issued after consideration of comments received from Documents. U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for Improvements In these

37082. Washington. DC 20013-7082. telephone (202)275-2060 or guides are encouraged at all times, and guides will be revised, as

(202)275-2171.

apiropriate, to accommodate comments and to reflect new Informa n or experience.

Issued guides may also be purchased from the National Technical Written comments may be submitted to the Rules and Procedures Information Service on a standing order basis. Details on this Branch.

DRR

ADM,

U.S.

Nuclear Regulatory Commission, service may be obtained by writing NTIS. 5285 Port Royal Road, Washington. DE 20555.

Springfield, VA 22161.

and Electronics Engineers (IEEE) Nuclear Power Engi neering Committee, and was subsequently approved by the IEEE Standards Board on June 11, 1987.

The IEEE standard includes principles, procedures, and methods of seismic qualification that, when satis fied, will confirm the adequacy of the equipment design for the performance of safety functions before, during, and after the time the safety-related equipment is subjected to high stresses resulting from design basis events. For this guide, the design basis events are the loadings imposed by seismic events: the operating basis earthquake (OBE) and the safe shutdown earthquake (SSE). It is also necessary to combine other dynamic or vibratory loads as part of seismic qualification. It is recognized that hydrodynamic loads have their primary energy content in a frequency range greater than that of seismic vibrations; however, they are a part of the inplant equipment aging process, along with other non seismic vibration loads, and therefore should be con sidered in seismic testin&

Revision I of this guide was issued in August 1977.

Since then, several new technical issues have arisen, such as treatment of hydrodynamic loads, the limits of generic testing, the treatment of rattling, methods of qualifying line-mounted devices, and the use of actual seismic experience data bases to qualify identical or similar equipment. These issues are covered by IEEE Std 344-1987, which reflects the state-of-the-art tech nology. Further, the NRC has extended the application of this standard to the qualification of mechanical equipment on an interim basis. In extending the applica tion of IEEE Std 344-1987 to mechanical equipment, the NRC staff recognizes that there are differences in qualification methods for electric and mechanical equipment.

Specifically, qualification of mechanical equipment by analysis is permitted when such equip ment can be modeled to adequately predict its response.

The American Society of Mechanical Engineers is cur rently developing a standard for seismic qualification of mechanical equipment. Upon publication of this stan dard, the NRC staff will review it for suitability for endorsement by a revision to this regulatory guide.

This regulatory guide covers two categories of equip ment: (1)

safety-related electric (Class IE) equipment.

and safety-related mechanical equipment, and (2)- non safety-related equipment whose failure can prevent the satisfactory accomplishment of safety functions. Exam ples of mechanical equipment within the scope of this guide are valves, valve operators, pumps, compressors, chillers, air handlers, fans, blowers, fuel rod assemblies, and control rod drive mechanisms.

IEEE Std 344-1987 recognizes the use of justified experience data as a method for seismic qualification.

This method of qualification will be evaluated by the NRC staff on a case-by-case basis.

IEEE' Std 344-1987 references other standards that contain valuable information. Those referenced standards not endorsed by a regulatory guide or incorporated intoK

the regulations, if used, are to be used in a manner consistent with current regulations.

C. REGULATORY POSITION

The procedures described by IEEE Std 344-1987,

"Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations," are acceptable to the NRC staff for satisfying the Commission's regulations pertaining to seismic qualification of electric and mechanical equipment subject to the following:

For mechanical equipment, thermal distortion effects on operability should be considered, and loads imposed by the attached piping should also be accounted for.

If dynamic testing of a pump or a valve assembly is impracticable, static testing of the assembly is acceptable provided that (1) the end loading& are applied and are equal to or greater than postulated event loads, (2) all dynamic amplification effects are accounted for, (3) the component is in the operating mode during and after the application of loads, and (4) an adequate analysis is made to show the validity of the static application of loads.

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.

Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described herein will be used in the evaluation of seismic qualification of electric and mechanical equipment for the following nuclear power plants:

I. Plants for which the construction permit is issued after June 30, 1988,

2. Plants for which the operating license application is docketed after December 30, 1988,

3. Plants for which the applicant or licensee voluntarily commits to the provisions of this guide.

1.100-2

4

VALUE/IMPACT STATEMENT

BACKGROUND

IEEE Std 344-1975, "Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations," was approved by the IEEE

in January 1975. In August 1977, the NRC staff issued Revision 1 to Regulatory Guide 1.100, which endorsed IEEE Std 344-1975, subject to four exceptions. Since then the staff has worked with the IEEE in developing IEEE Std 344-1987. As a result of these efforts, the exceptions to IEEE Std 344-1975 have been satisfacto rily resolved.

IEEE Std 344-1987 also addresses several recent technical issues, for example, treatment of hydrody namic loads, the limits of generic testing,, the treatment of rattling, methods of qualifying line-mounted devices, and the use of actual seismic experience data bases to qualify identical or similar equipment. IEEE Std 344

1987 thus reflects the state-of-the-art technology.

Issuance of Revision 2 is consistent with the NRC

policy of evaluating the latest versions of national standards in terms of their suitability for endorsement by regulatory guides.

SUBSTANTIVE CHANGES

IEEE Std 344-1987 applies to seismic and dynamic qualification of Class IE (safety-related electric) equip ment. The nuclear industry has used this standard for seismic qualification of mechanical equipment as well.

The NRC staff recognizes this fact and intends to

"extend the application of this standard to seismic qualification of mechanical equipment by this regulatory guide. Specifically, this regulatory guide coven two categories of equipment: (1) safety-related electric (Class IE) equipment and safety-related mechanical equipment, and (2) non-safety-related equipment whose failure can prevent the satisfactory accomplishment of safety func tions. The regulatory position provides guidance for qualification of mechanical equipment that is consistent with current NRC practice.

Regulatory Positions C.1 to C.4 in Revision 1 are not included in Revision 2 because they have been incorpo rated in IEEE Std 344-1987 as follows:

Regulatory Position in Rev. I of this Guide IEEE Std 344-1987 Section Number C.l

6.3 C.2

7.6.2.1 C.3

7.6.2.5 C.4

10.3.2(6)

VALUE

This guide endorses the latest version of a national standard and reflects the current state-of-the-art tech nology. The guide should also enhance the licensing process.

IMPACT

Although the scope of this revision has been ex tended to include seismic qualification of mechanical equipment, the requirements are consistent with NRC

current licensing practice. Thus, this regulatory guide does not impose any new requirements or costs on licensees or applicants.

1.100-3

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