Regulatory Guide 1.100: Difference between revisions

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{{Adams
{{Adams
| number = ML003740293
| number = ML13350A292
| issue date = 06/30/1988
| issue date = 03/31/1976
| title = (Task Ee 108-6), Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants
| title = Seismic Qualification of Electric Equipment for Nuclear Power Plant.
| author name =  
| author name =  
| author affiliation = 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, Revision 2
| document report number = RG-1.100
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 4
| page count = 2
}}
}}
{{#Wiki_filter:Revision 2 .4 o%" U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
COMMISSION  
COMMISSION
June 1988 !REGULATORY  
March 1976* REGULATORY  
GUIDE OFFICE OF NUCLEAR REGULATORY
GUIDE OFFICE OF STANDARDS
RESEARCH REGULATORY  
DEVELOPMENT
GUIDE 1.100 (Task EE 108-5) SEISMIC QUALIFICATION  
REGULATORY  
OF ELECTRIC AND MECHANICAL
GUIDE 1.100 SEISMIC QUALIFICATION  
EQUIPMENT  
OF ELECTRIC EQUIPMENT  
FOR NUCLEAR POWER PLANTS  
FOR NUCLEAR POWER PLANTS  


==A. INTRODUCTION==
==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.
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.


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 guidelines.
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
 
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 344-1987, "Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations,"*
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:
was prepared by Working Group 2.5 (Seismic Qualification)  
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  
of Subcommittee  
2 (Equip t Quabfication)  
2 (Equipment Qualification)  
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. 1001
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 0885
 
===5. 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 applicants.
 
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.-
===7. USNRC REGULATORY ===
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.
GUIDES Comments ehould be sent to the Secretary of the Commission.


U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for Improvements In these 37082. Washington.
U.S. Nuclate Reguletory Guides arm sesued to describe end make available to the public Regulattor Commission, Wash'ington.


DC 20013-7082.
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.


telephone
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.
(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.
or to provide guidance to sppirt cents Regulatory Gudo$ arm not gublslitUtes lot requultions.


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.
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


DE 20555. Springfield, VA 22161.
====s. tleto ====
3 Fuetl end Motorists Facilities


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.
====i. Occupationall ====
5elth the isuance or cnni~nuance of a permit oa hC eOeft by the Comm,,uion
4.


It is recognized that hydrodynamic loads have their primary energy content in a frequency range greater than that of seismic vibrations;
and Siting 9. Antitrust RAevlew Comment, end suggestions lot *mprOviments on these guides are encouraged S PandPlant Protection
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.
10. Oenaral ei &!I times an d gu ide l wlI be revised. as appropriate.


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.
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.


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


The American Society of Mechanical Engineers is cur rently developing a standard for seismic qualification of mechanical equipment.
D.C.Itcute ,y I utsful sn eviluating the tie ed t O# An early V#*Vision
2 M6 , Attention Ditictor.


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.
Office at Sta dmdn Dar s eve lopm ertl.


and safety-related mechanical equipment, and (2)- non safety-related equipment whose failure can prevent the satisfactory accomplishment of safety functions.
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.


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.
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.


IEEE Std 344-1987 recognizes the use of justified experience data as a method for seismic qualification.
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.
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==
==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
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..10 (I-bi 0.z 0~in 00 I- U U'z 8 Uitf J C 1 2u wI}}
STATEMEN
 
==T. 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 guide
 
====s. 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}}


{{RG-Nav}}
{{RG-Nav}}

Revision as of 19:52, 12 October 2018

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. 1001

7. 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.

and Siting 9. Antitrust RAevlew Comment, end suggestions lot *mprOviments on these guides are encouraged S 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..10 (I-bi 0.z 0~in 00 I- U U'z 8 Uitf J C 1 2u wI