Regulatory Guide 1.100: Difference between revisions

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| number = ML13350A292
| number = ML13350A292
| issue date = 03/31/1976
| issue date = 03/31/1976
| title = Seismic Qualification of Electric Equipment for Nuclear Power Plant.
| title = Seismic Qualification of Electric Equipment for Nuclear Power Plant
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/OSD
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| page count = 2
| page count = 2
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}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                                                                 March 1976
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
March 1976
* 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==
basis earthquakes (OBEs). The standard contains require.
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."
ments indicated by the verbs "shall" and "must" and Criterion Ill, "Design Control," of Appendix B,  
    "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
recommendations indicated by "should."
    "Licensing of. Production and Utilization Facilities,"                           Std 323-1974, "IEEE Standard rA ua1                                     Class IE
"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part SO,  
    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),
The standard, which is an an s  
    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.
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
specific design feature, it is required to include suitable qualification testing of a prototype unit under the most CY  
  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  
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==
a       ate basis for complying with design verification equirements of Criterion Ill of Appendix B to 10 CFR
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
IEEE  
    344-;971), "IEEE Recommended Practi                               f     is     electric equipment, subject to the following:
Std  
  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.
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  
"nto account 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 Reguletory Guides arm sesued to describe end make available to the public Regulattor Commission, Wash'ington. D.C.
 
:SS. Attention: Oickellng and methods acceptable to the NRC *fail of implementing specific parts of the S er*vIr Section.


December 20. 19)                                  "
Commission s regulal.ons. to detineate Itchnoques used by the staff in evelu The guides are Isue in Ihe followin 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
                                                                                          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.
4S Prod-pets with them is not required Methods and solutlons different from those set out in
2 Research and Test Realtors
?. Transportation thegudew.l bsacceplotbla*f they provides be,.i to, the findng$ requ


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.
====s. tleto ====
3 Fuetl end Motorists Facilities


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
====i. Occupationall ====
                              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.
5elth the isuance or cnni~nuance of a permit oa hC eOeft 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 &!I times an d gu ide l wlI be revised. as appropriate. to accommodate eOrn men  
,nd to lletect nte  
,  
hlonalilon or eapeieonco However. comments on Copi.es of pubilished guides m ry be 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
Itcute  
            ,y I   sn eviluating the tie ted An  O#early V#*Vision                 2 M6 , Attention Ditictor. Office at Sta dmdns Dar eve lopm ertl.
,y I  
utsful sn eviluating the tie ed t
O#  
An early V#*Vision  
2 M6 , Attention Ditictor. Office at Sta dmdn Dar s
eve lopm ertl.


coefficient of 1.5, or one greateror less than 1.5, in its   8.6 Malfunction Data.
coefficient of 1.5, or one greater or less than 1.5, in its application to equipment analysis.


applicationto equipment analysis.
2. Section 6.6.2.1, "Derivation of Test Input Mo- tion," (concerning single frequency test input motion)
states that, for equipment with more than orn predomi- nant frequency, the shake table motion should produce a test response spectrum (TRS) acceleration at the test frequencies equal to 1.5 times the acceleration given by the specified required response spectrum (RRS) or less if justified. The section 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 should not, in the absence of justification, be considered acceptable.


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.
Basis: These provisions violate the general require- ments stated in Section 6.6.1 of the standard for justifiable test input.


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.
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 Section 6.6.2 and 6.6.2.1 should not be considered acceptable.,
Basis: Sections 6.6.2 and 6.6.2.1 do not provide specific guidelines concerning a justfliable methodology to define the TRS for a sweep input motion and therefore violate the general requirements stated in Section 6.6.1 for a justifiable test input.


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


==D. IMPLEMENTATION==
If a malfunction -is defined in Section 2, "Defini- tions," Ls experienced during any test, the effect of that malfunction should be determined and documented in the test report.
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.
Basis: This Is a logical extention of &'ction 8,
"Documentation," and provides added emphasis on the need to document all malfunctions that might result In consequences adverse to safety.


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.
==D. IMPLEMENTATION==
The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.


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.
Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used in the evaluation of submittals for construction permit applications docketed after November 15, 1976, uldess this guide is revised as a result of suggestions from the public or additional staff review.


4. The requirements given in Section 8, "Documenta- tion," should be supplemented by the following:
If an applicant wishes to use this regulatory guide in 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.
                                                              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, 11 January 2025

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)


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

"nto account 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 Reguletory Guides arm sesued to describe end make available to the public Regulattor Commission, Wash'ington. D.C.

SS. Attention: Oickellng and methods acceptable to the NRC *fail of implementing specific parts of the S er*vIr Section.

Commission s regulal.ons. to detineate Itchnoques used by the staff in evelu The guides are Isue in Ihe followin 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 solutlons different from those set out in

2 Research and Test Realtors

?. Transportation thegudew.l bsacceplotbla*f they provides be,.i to, the findng$ requ

s. tleto

3 Fuetl end Motorists Facilities

i. Occupationall

5elth the isuance or cnni~nuance of a permit oa hC eOeft 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 &!I times an d gu ide l wlI be revised. as appropriate. to accommodate eOrn men

,nd to lletect nte

,

hlonalilon or eapeieonco However. comments on Copi.es of pubilished guides m ry be 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

,y I

utsful sn eviluating the tie ed t

O#

An early V#*Vision

2 M6 , Attention Ditictor. Office at Sta dmdn Dar s

eve lopm ertl.

coefficient of 1.5, or one greater or less than 1.5, in its application to equipment analysis.

2. Section 6.6.2.1, "Derivation of Test Input Mo- tion," (concerning single frequency test input motion)

states that, for equipment with more than orn predomi- nant frequency, the shake table motion should produce a test response spectrum (TRS) acceleration at the test frequencies equal to 1.5 times the acceleration given by the specified required response spectrum (RRS) or less if justified. The section 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 should not, in the absence of justification, be considered acceptable.

Basis: These provisions violate the general require- ments stated in Section 6.6.1 of the standard for justifiable test input.

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 Section 6.6.2 and 6.6.2.1 should not be considered acceptable.,

Basis: Sections 6.6.2 and 6.6.2.1 do not provide specific guidelines concerning a justfliable methodology to define the TRS for a sweep input motion and 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:

8.6 Malfunction Data.

If a malfunction -is defined in Section 2, "Defini- tions," Ls experienced during any test, the effect of that malfunction should be determined and documented in the test report.

Basis: This Is a logical extention of &'ction 8,

"Documentation," and provides added emphasis on the need to document all malfunctions that might result In consequences adverse to safety.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.

Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used in the evaluation of submittals for construction permit applications docketed after November 15, 1976, uldess this guide is revised as a result of suggestions from the public or additional staff review.

If an applicant wishes to use this regulatory guide in 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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