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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References
RG-1.100
Download: ML13350A292 (2)

U.S. NUCLEAR REGULATORY COMMISSIONMarch 1976* REGULATORY GUIDEOFFICE OF STANDARDS DEVELOPMENTREGULATORY GUIDE 1.100SEISMIC QUALIFICATION OF ELECTRICEQUIPMENT FOR NUCLEAR POWER PLANTSA. INTRODUCTION basis earthquakes (OBEs). The standard contains require.ments indicated by the verbs "shall" and "must" andCriterion Ill, "Design Control," of Appendix B, recommendations indicated by "should.""Quality Assurance Criteria for Nuclear Power Plantsand 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 IErequires, 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 anda 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 suitablequalification testing of a prototype unit under the most CY POSITIONadverse 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 conductingspect 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;iion with Regultory Guide 1.89, provides anB. DISCUSSION a ate basis for complying with design verificationequirements of Criterion Ill of Appendix B to 10 CFRIEEE Std 344-1975' (revision of EeisE t 50 with respect to verifying the seismic adequacy of344-;971), "IEEE Recommended Practi f is electric equipment, subject to the following:Qualification of Class I E Equipment for ,liar werGenerating Stations," dated January 3 , was 1. As indicated in Section 5.3, "Static Coefficientprepared by Working Group 2.5 (Seismic Q ication) Analysis," a static coefficient of 1.5 is used forof Subcommittee 2 (Equip t Quabfication) of the equipment analysis to take "nto account the effects ofInstitute 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 notquently approved Ue Eftandards Board on be considered acceptable unless justified by analysis.December 20. 19) "Basis: There is no adequate evidence presented inThe p sio s standard include principles, Section 5.3 to substantiate the validity of a staticprocedure met o s of seismic qualification which,when satis will confirm the adequacy of theequipment de for the performance of Class IE 'IEEE Std 344-1975. "IEEE Recommended Practices forfunctions during and after the time the equipm,.nt is Seismic Qualification of'Class IE Equipment for Nuclear PowerGenerating Stations." Copies may be obtained from thesubjected to the forces resulting from one safe shutdown Institute of Electrical and Electronics Engineers, United Engioearthquake (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. NuclateReguletory Guides arm sesued to describe end make available to the public Regulattor Commission, Wash'ington. D.C. :SS. Attention: Oickellng andmethods 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 sppirtcents Regulatory Gudo$ arm not gublslitUtes lot requultions. and compliance I Power qeReactor 4S Prod-petswith them is not required Methods and solutlons different from those set out in 2 Research and Test Realtors ?. Transportationthegudew.l bsacceplotbla*f they provides be,.i to, the findng$ requs.tleto 3 Fuetl end Motorists Facilities i. Occupationall 5elththe isuance or cnni~nuance of a permit oa hC eOeft by the Comm,,uion 4. and Siting 9. Antitrust RAevlewComment, end suggestions lot *mprOviments on these guides are encouraged S PandPlant Protection 10. Oenaralei &!I times an d gu ide l wlI be revised. as appropriate. to accommodate eOrnmen ,nd to lletect nte , hlonalilon or eapeieonco However. comments on Copi.es of pubilished guides m ry be obtained by wlitten request Indicating 'heth,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 ert coefficient of 1.5, or one greater or less than 1.5, in itsapplication 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 producea test response spectrum (TRS) acceleration at the testfrequencies equal to 1.5 times the acceleration given bythe specified required response spectrum (RRS) or less ifjustified. The section also states that the TRS need notenvelop the RRS provided the factor of 1.5 is used. Theuse of a factor of 1.5 and the concept that the TRS neednot envelop the RRS should not, in the absence ofjustification, be considered acceptable.Basis: These provisions violate the general require-ments stated in Section 6.6.1 of the standard forjustifiable test input.3. In the absence of justification, those portions ofSection 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 criteriadescribed in Section 6.6.2 and 6.6.2.1 should not beconsidered acceptable.,Basis: Sections 6.6.2 and 6.6.2.1 do not providespecific guidelines concerning a justfliable methodologyto define the TRS for a sweep input motion andtherefore violate the general requirements stated inSection 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 thatmalfunction should be determined and documented inthe test report.Basis: This Is a logical extention of &'ction 8,"Documentation," and provides added emphasis on theneed to document all malfunctions that might result Inconsequences adverse to safety.D. IMPLEMENTATIONThe purpose of this section is to provide informationto applicants regarding the NRC staff's plans for usingthis regulatory guide.Except in those cases in which the applicant proposesan acceptable alternative method for complying withspecified portions of the Commission's regulations, themethod described herein will be used in the evaluationof submittals for construction permit applicationsdocketed after November 15, 1976, uldess this guide isrevised as a result of suggestions from the public oradditional staff review.If an applicant wishes to use this regulatory guide indeveloping submittals for applications docketed on orbefore November 15, 1976, the pertinent portions ofthe application will be evaluated on the basis of thkiguide..10(I-bi0.z0~in00I- UU'z8UitfJ C12uwI