Regulatory Guide 1.100: Difference between revisions

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{{Adams
{{Adams
| number = ML12305A261
| number = ML13350A292
| issue date = 08/31/1977
| issue date = 03/31/1976
| title = Seismic Qualification of Electric Equipment for Nuclear Power Plants.
| title = Seismic Qualification of Electric Equipment for Nuclear Power Plant.
| author name =  
| author name =  
| author affiliation = NRC/OSD, NRC/RES
| author affiliation = NRC/OSD
| 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
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 3
| page count = 2
}}
}}
{{#Wiki_filter:Revision I
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                                                                 March 1976
                                    U.S. NUCLEAR REGULATORY COMMISSION                                                                                 August 1977 REGULATORY GUIDE
* REGULATORY GUIDE
                                    OFFICE OF STANDARDS DEVELOPMENT
    OFFICE OF STANDARDS DEVELOPMENT
                                                              REGULATORY GUIDE 1.100
                                                                    REGULATORY GUIDE 1.100
                                              SEISMIC QUALIFICATION OF ELECTRIC
                                                        SEISMIC QUALIFICATION OF ELECTRIC
                                          EQUIPMENT FOR NUCLEAR POWER PLANTS
                                                    EQUIPMENT FOR NUCLEAR POWER PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
The provisions of the standard include principles, procedures, and methods of seismic qualification Criterion III, "Design Control," of Appendix B,                                    which, when satisfied, will confirm the adequacy of
basis earthquakes (OBEs). The standard contains require.
"Quality Assurance Criteria for Nuclear Power                                          the equipment design for the performance of Class I E
Plants and Fuel Reprocessing Plants," to 10 CFR                                        functions during and after the time the equipment is Part 50, "Licensing of Production and Utilization                                      subjected to the forces resulting from one safe shut- Facilities," requires, among other things, that design                                  down earthquake (SSE) preceded by a number of control measures provide for verifying the adequacy                                    operating basis earthquakes (OBE0s). The standard of design such as by the performance of a suitable                                      contains requirements indicated by the verbs "shall"
testing program. Where a test program is used to                                        and "must" and recommendations indicated by verify the adequacy of a specific design feature, it is                                "should."
required to include suitable qualification testing of a prototype unit under the most adverse design condi-                                          The standard, which is an ancillary standard of tions. This regulatory guide describes a method ac-                                      IEEE Std 323-1974, "IEEE Standard for Qualifying ceptable to the NRC staff for complying with the                                        Class I E Equipment for Nuclear Power Generating Commission's regulations with respect to verifying                                      Stations," (endorsed, with exceptions, by Regulatory the adequacy of the seismic design of electric equip-                                  Guide 1.89, "Qualification of Class IE Equipment ment for all types of nuclear power plants. The Ad-                                    for Nuclear Power Plants"), supplements part of the visory Committee on Reactor Safeguards has been                                        test methods required and references the margins consulted concerning this guide and has concurred in                                    given in IEEE Std 323-1974.


the regulatory position.
ments indicated by the verbs "shall" and "must" and Criterion Ill, "Design Control," of Appendix B,                            recommendations indicated by "should."
    "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part SO,                                    The standard, which is an an                          s      aid of IEEE
    "Licensing of. Production and Utilization Facilities,"                          Std 323-1974, "IEEE Standard rA ua1                                    Class IE
    requires, among other things, that design control meas-                          Equipment for NuclearP                                      rating Stations, ures provide for verifying the adequacy of design such as                        (endorsed, with excepti                    ,                  ry Guide 1.89),
    by the performance of a suitable testing program. Where                          supplements part                              -e      ethos required and a test program is used to verify the adequacy of a                              references the maa                    n r              Std 323-1974.


==C. REGULATORY POSITION==
specific design feature, it is required to include suitable qualification testing of a prototype unit under the most                                            CY                              POSITION
  adverse design conditions. This regulatory guide de- scribes a method acceptable to the NRC staff for                                      C     0                      the requirements and recommen- complying with the Commission's regulations with re-                              dati                      by IEEE Std 344-19751 for conducting spect to verifying the adequacy of the seismic design of                            ii                    tion of Class IE Equipment is accept- k  electric equipment for all types of nuclear power plants.                                                en such qualification is performed i;i ion with Regultory Guide 1.89, provides an


==B. DISCUSSION==
==B. DISCUSSION==
Conformance with the requirements and recom- IEEE Std 344-1975f(revision of IEEE Std 344- mendations specified by IEEE Std 344-1975' for con-
a        ate basis for complying with design verification equirements of Criterion Ill of Appendix B to 10 CFR
1971), "IEEE Recommended Practices for Seismic ducting seismic qualification of Class 1E equipment, Qualification of Class 1E Equipment for Nuclear                                        when such qualification is performed in conjunction Power Generating Stations," dated January 31, 1975,                                    with Regulatory Guide 1.89, provides an adequate was prepared by Working Group 2.5 (Seismic Qualification) of Subcommittee 2 (Equipment                                            basis for complying with design verification require- ments of Criterion III of Appendix B to 10 CFR Part Qualification) of the Institute of Electrical and
        IEEE Std 344-1975' (revision of                                     EeisE        t 50 with respect to verifying the seismic adequacy of
                                                                                        50 with respect to verifying the seismic adequacy of Electronics Engineers (IEEE) Nuclear Power electric equipment, subject to the following:
    344-;971), "IEEE Recommended Practi                                f    is      electric equipment, subject to the following:
Engineering Committee and was subsequently ap- proved by the IEEE Standards Board on December                                              1. As indicated in Section 5.3, "Static Coefficient
  Qualification of Class I E Equipment for ,liar wer Generating Stations," dated January 3                            ,        was       1. As indicated in Section 5.3, "Static Coefficient prepared by Working Group 2.5 (Seismic Q ication)                                Analysis," a static coefficient of 1.5 is used for of Subcommittee 2 (Equip                            t Quabfication) of the      equipment analysis to take "ntoaccount the effects of Institute of Electrical ant                    eU onics Engineers (IEEE)        both multifrequency excitation and multimode me- Nuclear Power Engineeri                              W ee, and was subse-        sponse. The use of 1.5 as a static coefficient should not quently approved                    Ue              Eftandards Board on          be considered acceptable unless justified by analysis.
20, 1974.                                                                               Analysis," a static coefficient of 1.5 is used for equip-
*Lines indicate substantive changes from previous issue.                                ment analysis to take into account the effects of both
'Copies may be obtained from the Institute of Electrical and                          multi frequency excitation and multimode response.


Electronics Engineers, United Engineering Center, 345 East 47th                        The use of 1.5 as the static coefficient is acceptable Street, New York, N.Y. 10017.                                                            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.
December 20. 19)                                  "
                                                                                          Basis: There is no adequate evidence presented in The p sio s                              standard include principles,       Section 5.3 to substantiate the validity of a static procedure                met o s of seismic qualification which, when satis                  will confirm the adequacy of the equipment de                    for the performance of Class IE                  'IEEE Std 344-1975. "IEEE Recommended Practices for functions during and after the time the equipm,.nt is                              Seismic Qualification of'Class IE Equipment for Nuclear Power Generating Stations." Copies may be obtained from the subjected to the forces resulting from one safe shutdown                            Institute of Electrical and Electronics Engineers, United Engio earthquake (SSE) preceded by a number of operating                                  neering Center. 345 Eait 47th Street. New York, N.Y. 10017.


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:
USNRC REGULATORY GUIDES                                      Comments ehould be sent to the Secretary of the Commission. U.S. Nuclate Regulattor Commission, Wash'ington. D.C.             :SS. Attention: Oickellng and Reguletory Guides arm sesued to describe end make available to the public methods acceptable to the NRC *fail of implementing specific parts of the         S er*vIrSection.
or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required.         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 3.  Fuels and Materials Facilities            8. Occupational Health of a permit or license by the Commission.                                              4.


5.  Environmental Materials      and Protection and Plant Siting              
Commission s regulal.ons. to detineate Itchnoques used by the staff in evelu      The guides are Isue    in  Ihefollowin  van broad dlslons- eling specific problems or postulated accidents. or to provide guidance to sppirt cents Regulatory Gudo$ arm not gublslitUtes lot requultions. and compliance        I Power qeReactor                      4S Prod-pets with them is not required Methods and solutlonsdifferent from those set out in    2  Research and Test Realtors            ?. Transportation thegudew.l bsacceplotbla*f they provides be,.i to, the findng$ requs.tleto        3  Fuetl end Motorists Facilities        i. Occupationall 5elth the isuance orcnni~nuance of a permit oa hCeOeft by the Comm,,uion                4.  rnviron*mntll and Siting             9. Antitrust RAevlew Comment, end suggestions lot *mprOviments on these guides are encouraged          S  Motori*t          PandPlant Protection      10. Oenaral ei &!Itimes an d gu      ide wlI
                              l    be revised. as appropriate. to accommodate eOrn men    ,nd to lletect nte    ,    hlonalilonor eapeieonco However. comments on  Copi.es of pubilished guides m rybe obtained by wlitten request Indicating 'he th,s ,.ide. ,I received within shout two months alter i1t issuance, will be pae    divisions deeired to the U.S Nuclet Regulatory Commission. Washington. D.C.


===9. Antitrust Review===
Itcute    utsful
                                                                                                                                    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: Director, Division of Document Control.
            ,y I    sn eviluating the tie ted An  O#early V#*Vision                  2 M6 , Attention Ditictor. Office at Sta dmdns Dar  eve lopm ertl.


tures, such as members physically similar to beams                  As stated in regulatory position 2, one of the re- and columns, that can be represented by a simple              quirements to ensure equipment operability is to ex- model. For equipment having configurations other              cite all modes of the equipment adequately and than a frame-type structure, justification should be          simultaneously to the required levels. One of the provided for use of a static coefficient.                    criteria used to verify the adequacy of the test input is to have the TRS enveloping the RRS as specified in
coefficient of 1.5, or one greateror less than 1.5, in its  8.6 Malfunction Data.
    2. Section 6.6.2.1, "Derivation of Test Input            Section 6.6.1 of the standard. The sine sweep test may Motion," (concerning single-frequency test input              not be suitable for equipment qualification for the motion) states that, for equipment with more than             following reasons:
one predominant frequency, the shake table motion should produce a test response spectrum (TRS) ac-                  a. For a fast sweep, even though the equipment celeration at the test frequencies equal to 1.5 times        may sense nearly simultaneous multimode effects, the the acceleration given by the specified required              duration for each mode to be excited may be too brief response spectrum (RRS) or less if justified. The sec-        to induce adequate resonance as compared to the ac- tion also states that the TRS need not envelop the            tual excitations.


RRS provided the factor of 1.5 is used.
applicationto equipment analysis.


b. For a slow sweep, the effects are nearly excita- The use of a factor of 1.5 and the concept that         tion of one mode at a time. Even with the TRS being the TRS need not envelop the RRS as a consequence            broad band and enveloping the RRS, the true sense of using 1.5 should not, in the absence of justifica-        of simultaneous multimode response is not provided.
2. Section 6.6.2.1, "Derivation of Test Input Mo-        If a malfunction -is defined in Section 2, "Defini- tion," (concerning single frequency test input motion)      tions," Ls experienced during any test, the effect of that states that, for equipment with more than orn predomi-      malfunction should be determined and documented in nant frequency, the shake table motion should produce        the test report.


tion, be considered acceptable. For example, in the event that the RRS is broad band, the use of single-              Sections 6.6.2 and 6.6.2.1 do not provide specific frequency test input with a 1.5 magnification factor        guidelines concerning either the sweep rate or a may not be adequate to excite all modes to the re-          justifiable methodology to define the TRS for a quired levels. For ensuring operability of an equip-        sweep input motion.
a test response spectrum (TRS) acceleration at the test         Basis: This Is a logical extention of &'ction 8, frequencies equal to 1.5 times the acceleration given by      "Documentation," and provides added emphasis on the the specified required response spectrum (RRS) or less if    need to document all malfunctions that might result In justified. The section also states that the TRS need not      consequences adverse to safety.


ment under seismic event, the test input motion                4. The requirements given in Section 8, "Documen- should closely simulate the characteristics of excita- tion. An equipment malfunction may not be                    tation," should be supplemented by the following:
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 should not, in the absence of                             
governed by the level of stress but is frequently caused by the vibratory behavior of the response. As          8.6 Malfunction Data stated in Section 6.6.1 of the standard, one of the general requirements for a justifiable seismic test in-          If a malfunction as defined in Section 2, put is that the wave forms should produce a TRS that        "Definitions," is experienced during any test, the ef- closely envelops the applicable portion of the RRS.          fect of that malfunction should be determined and This requirement is intended to ensure that all modes        documented in the test report.


of an equipment are adequately and simultaneously excited to the required level
==D. IMPLEMENTATION==
justification, be considered acceptable.


====s. Since the TRS====
Basis: These provisions violate the general require-      The purpose of this section is to provide information ments stated in Section 6.6.1 of the standard for              to applicants regarding the NRC staff's plans for using justifiable test input.                                      this regulatory guide.
produced by the single-frequency test input is narrow                       


==D. IMPLEMENTATION==
3. In the absence of justification, those portions of Except in those cases in which the applicant proposes Section 6.6.2.5, "Sine Sweep Test," which indicate that,     an acceptable alternative method for complying with for qualifying equipment using the sine sweep test input,    specified portions of the Commission's regulations, the the TRS must envelop the RRS according to the criteria        method described herein will be used in the evaluation described in Section 6.6.2 and 6.6.2.1 should not be         of submittals for construction permit applications considered acceptable.,                                        docketed after November 15, 1976, uldess this guide is Basis: Sections 6.6.2 and 6.6.2.1 do not provide      revised as a result of suggestions from the public or specific guidelines concerning a justfliable methodology      additional staff review.
band and the RRS may be broad band, the use of single-frequency test input with a 1.5 magnification            The purpose of this section is to provide informa- factor may not always be adequate to excite all modes        tion to applicants regarding the NRC staff's plans for of the equipment to the required levels. Thus it is         using this regulatory guide.


necessary that the TRS closely envelop the applicable portion of the RRS to verify the adequacy of test in-          This guide reflects current NRC staff practice.
to define the TRS for a sweep input motion and                    If an applicant wishes to use this regulatory guide in therefore violate the general requirements stated in Section 6.6.1 for a justifiable test input.


put motion.                                                 Therefore, except in those cases in which the appli- cant proposes an acceptable alternative method for
4. The requirements given in Section 8, "Documenta- tion," should be supplemented by the following:
    3. In the absence of justification, those portions of    complying with the specified portions of the Commis- Section 6.6.2.5, "Sine Sweep Test," which indicate          sion's regulations, the method described herein is be- that, for qualifying equipment using the sine sweep          ing and will continue to be used in the evaluation of test input, the TRS must envelop the RRS according          submittals for construction permit applications until to the criteria described in Sections 6.6.2 and 6.6.2.1      this guide is revised as a result of suggestions from the should not be considered acceptable.                        public or additional staff review.
                                                              developing submittals for applications docketed on or before November 15, 1976, the pertinent portions of the application will be evaluated on the basis of thki guide.


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Revision as of 00:17, 20 March 2020

Seismic Qualification of Electric Equipment for Nuclear Power Plant.
ML13350A292
Person / Time
Issue date: 03/31/1976
From:
NRC/OSD
To:
References
RG-1.100
Download: ML13350A292 (2)
v • d • e


U.S. NUCLEAR REGULATORY COMMISSION March 1976

  • REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.100

SEISMIC QUALIFICATION OF ELECTRIC

EQUIPMENT FOR NUCLEAR POWER PLANTS

A. INTRODUCTION

basis earthquakes (OBEs). The standard contains require.

ments indicated by the verbs "shall" and "must" and Criterion Ill, "Design Control," of Appendix B, recommendations indicated by "should."

"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part SO, The standard, which is an an s aid of IEEE

"Licensing of. Production and Utilization Facilities," Std 323-1974, "IEEE Standard rA ua1 Class IE

requires, among other things, that design control meas- Equipment for NuclearP rating Stations, ures provide for verifying the adequacy of design such as (endorsed, with excepti , ry Guide 1.89),

by the performance of a suitable testing program. Where supplements part -e ethos required and a test program is used to verify the adequacy of a references the maa n r Std 323-1974.

specific design feature, it is required to include suitable qualification testing of a prototype unit under the most CY POSITION

adverse design conditions. This regulatory guide de- scribes a method acceptable to the NRC staff for C 0 the requirements and recommen- complying with the Commission's regulations with re- dati by IEEE Std 344-19751 for conducting spect to verifying the adequacy of the seismic design of ii tion of Class IE Equipment is accept- k electric equipment for all types of nuclear power plants. en such qualification is performed i;i ion with Regultory Guide 1.89, provides an

B. DISCUSSION

a ate basis for complying with design verification equirements of Criterion Ill of Appendix B to 10 CFR

IEEE Std 344-1975' (revision of EeisE t 50 with respect to verifying the seismic adequacy of

344-;971), "IEEE Recommended Practi f is electric equipment, subject to the following:

Qualification of Class I E Equipment for ,liar wer Generating Stations," dated January 3 , was 1. As indicated in Section 5.3, "Static Coefficient prepared by Working Group 2.5 (Seismic Q ication) Analysis," a static coefficient of 1.5 is used for of Subcommittee 2 (Equip t Quabfication) of the equipment analysis to take "ntoaccount the effects of Institute of Electrical ant eU onics Engineers (IEEE) both multifrequency excitation and multimode me- Nuclear Power Engineeri W ee, and was subse- sponse. The use of 1.5 as a static coefficient should not quently approved Ue Eftandards Board on be considered acceptable unless justified by analysis.

December 20. 19) "

Basis: There is no adequate evidence presented in The p sio s standard include principles, Section 5.3 to substantiate the validity of a static procedure met o s of seismic qualification which, when satis will confirm the adequacy of the equipment de for the performance of Class IE 'IEEE Std 344-1975. "IEEE Recommended Practices for functions during and after the time the equipm,.nt is Seismic Qualification of'Class IE Equipment for Nuclear Power Generating Stations." Copies may be obtained from the subjected to the forces resulting from one safe shutdown Institute of Electrical and Electronics Engineers, United Engio earthquake (SSE) preceded by a number of operating neering Center. 345 Eait 47th Street. New York, N.Y. 10017.

USNRC REGULATORY GUIDES Comments ehould be sent to the Secretary of the Commission. U.S. Nuclate Regulattor Commission, Wash'ington. D.C. :SS. Attention: Oickellng and Reguletory Guides arm sesued to describe end make available to the public methods acceptable to the NRC *fail of implementing specific parts of the S er*vIrSection.

Commission s regulal.ons. to detineate Itchnoques used by the staff in evelu The guides are Isue in Ihefollowin van broad dlslons- eling specific problems or postulated accidents. or to provide guidance to sppirt cents Regulatory Gudo$ arm not gublslitUtes lot requultions. and compliance I Power qeReactor 4S Prod-pets with them is not required Methods and solutlonsdifferent from those set out in 2 Research and Test Realtors  ?. Transportation thegudew.l bsacceplotbla*f they provides be,.i to, the findng$ requs.tleto 3 Fuetl end Motorists Facilities i. Occupationall 5elth the isuance orcnni~nuance of a permit oa hCeOeft by the Comm,,uion 4. rnviron*mntll and Siting 9. Antitrust RAevlew Comment, end suggestions lot *mprOviments on these guides are encouraged S Motori*t PandPlant Protection 10. Oenaral ei &!Itimes an d gu ide wlI

l be revised. as appropriate. to accommodate eOrn men ,nd to lletect nte , hlonalilonor eapeieonco However. comments on Copi.es of pubilished guides m rybe obtained by wlitten request Indicating 'he th,s ,.ide. ,I received within shout two months alter i1t issuance, will be pae divisions deeired to the U.S Nuclet Regulatory Commission. Washington. D.C.

Itcute utsful

,y I sn eviluating the tie ted An O#early V#*Vision 2 M6 , Attention Ditictor. Office at Sta dmdns Dar eve lopm ertl.

coefficient of 1.5, or one greateror less than 1.5, in its 8.6 Malfunction Data.

applicationto equipment analysis.

2. Section 6.6.2.1, "Derivation of Test Input Mo- If a malfunction -is defined in Section 2, "Defini- tion," (concerning single frequency test input motion) tions," Ls experienced during any test, the effect of that states that, for equipment with more than orn predomi- malfunction should be determined and documented in nant frequency, the shake table motion should produce the test report.

a test response spectrum (TRS) acceleration at the test Basis: This Is a logical extention of &'ction 8, frequencies equal to 1.5 times the acceleration given by "Documentation," and provides added emphasis on the the specified required response spectrum (RRS) or less if need to document all malfunctions that might result In justified. The section also states that the TRS need not consequences adverse to safety.

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 should not, in the absence of

D. IMPLEMENTATION

justification, be considered acceptable.

Basis: These provisions violate the general require- The purpose of this section is to provide information ments stated in Section 6.6.1 of the standard for to applicants regarding the NRC staff's plans for using justifiable test input. this regulatory guide.

3. In the absence of justification, those portions of Except in those cases in which the applicant proposes Section 6.6.2.5, "Sine Sweep Test," which indicate that, an acceptable alternative method for complying with for qualifying equipment using the sine sweep test input, specified portions of the Commission's regulations, the the TRS must envelop the RRS according to the criteria method described herein will be used in the evaluation described in Section 6.6.2 and 6.6.2.1 should not be of submittals for construction permit applications considered acceptable., docketed after November 15, 1976, uldess this guide is Basis: Sections 6.6.2 and 6.6.2.1 do not provide revised as a result of suggestions from the public or specific guidelines concerning a justfliable methodology additional staff review.

to define the TRS for a sweep input motion and If an applicant wishes to use this regulatory guide in therefore violate the general requirements stated in Section 6.6.1 for a justifiable test input.

4. The requirements given in Section 8, "Documenta- tion," should be supplemented by the following:

developing submittals for applications docketed on or before November 15, 1976, the pertinent portions of the application will be evaluated on the basis of thki guide.

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