Regulatory Guide 1.100

Seismic Qualification of Electric Equipment for Nuclear Power Plant.

ML13350A292
Person / Time
Issue date:	03/31/1976
From:	NRC/OSD
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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 "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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