ML20205Q428
| ML20205Q428 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20204J261 | List: |
| References | |
| FOIA-87-714, RTR-REGGD-1.100, TASK-EE-108-5, TASK-RE REGGD-01.100, REGGD-1.100, NUDOCS 8811090233 | |
| Download: ML20205Q428 (14) | |
Text
. .
Pevision2(Draft 4)
December 1986 Cnntact: S. K. Aggarwal (301) 443-7840 REGULATORY GUTCE 1.100 (Task EE 108-5)
SEISMIC QUALIFICATION OF ELECTRIC AND MECHANICAL EQUIPMENT FOR NUCLEAR POWER PLANTS A. INTRODUCTION The Cornission's regulations in 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," require that cert 61n structures, systers, and components in a nuclear power plant be designeo to withstand 1.he effects of natural phenomena such as earthquakes, and that design control measures such as testing be used to check the adequacy of design. This i.
general requirement is contained in Appendix A. "General Design Criteria fcr Nuclear Power Plants " to Part 50; in Criterion !!!, "Design Control," and l~
Criterion XVII, "Ouality Assurance Records" of Appendix 8. "Cuality Assurane.e 4 Criteria for Nuclear Pcver Plants and Fuel Reprocessing Plants " to Part 50; and Appendix A. "Seismic and Geologic Siting Criteria for Nuclear Power Plants," to Part 100.
Appendix A to 10 CFR Part 100.Section VI, "Application to Engineering l
Design," requires that the nuclear power plant shall be designed so that, if l l
the Safe Shutdown Earthquake occurs, certain structures, systems and com- l' ponents will reeain functions 1. These safety-related structures, systems, and corponents are those necessary to asstre (1) :.ne integrity of the reactor cool-ant pressure boundary, (ii) the capability tc shut down the reactor and main- j l tain it in a safe condition, or (lit) the capability to prevent or alltigate the I' l
consequen:es of accidents which could result in offsite exposures comparable to ;
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i the 10 CFR Part 100 guidelines. Appendix A to Part 100. Section Y!.fa)(E) {
requires that structures, systems, and components of the mlear pcwer plant !
necessary for continued operation witheut undue risk to the health and safety !
of the public shall be designed to remain functional and aithin coplicable I stress and deformation limits when subjected to the effects of the vibratory motion of the Operating Basis Earthquake in combination with normal operating ;
loads. It is also required that the engineering method used to ensure that i the required safety functions are raintained during and after the vibratory f ground motion associated with the Safe Shutdown Earthquakt or Operating Basis l Earthquake, shall involve the use C1 either a suitable dynamic analysis or a i suitable qualification test to demonstrate that structures, systems, and f components can withstand the seismic and other concurrent loads. !
L This regulatory guide describes a method acceptable to the NRC staff for cceplying with the Comission's regolations with ret.pect to seismic qualifica- !
I tion of electric and mechanical equipment.
i B. DISCUS $10N
!!EE Std. 344-1987I "Recennended Practices for Seismic Qualification of Class li Equipment for Nuclear Power Generating Stations " was prepared by Working Group 2.5 (Seismic Qualification) of Subconnittee 2 (Eqvipment Quali- (
fication)oftheInstituteofElectricalandElectronicsEngineers(IEEE) f Nuclear Power Engineering Coneittee, and was subsequently approved by the }
IEEE Standards Board on ,, .
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I This guide is being de, eloped in parallel with the revision of IEEE Std. 344 The proposed revision of the guide will not be issued fot public coment .;
- until the Standard is published by IEEE. Draft 4 of RG 1.100, Rev. 2 is based [
l on a copy of the standard as approved by the IEEE Nuclear Pcwer Engineering [
Cessnittee. ~
! l l
i Oraft 4 2 December 4, 1966
The provisions of the IEEE Standard include principles, procedures, and riethods of seismic qualification which, when satisfied, will confir1n the adequacy of the ecuipment 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 purposes cf this guide, the design basis events are the loadings imposed by seismic events:
the Operating Pasis Earthquake (OBE), and the Safe Shutdown Earthquake (SSE).
It is also necessary to combine other dyna:nic or vibratory loads as part of seismic qualification. It is recognized that hydrodynamic loads have their primary energy content in a frequeacy range greater than that of seismic vibrations. However, they are a part of the in-plant equipment aging yrocess, along with other non-seismic vibration loads, and, as such should be considered in seismic testing'. l Rev. I of this guide was issued in August 1977. Several new technical issues have since arisen. Examples of these issues are treatrent of hydro-dynamic loads, the limits of generic testing, the treatrent of rattling, ,(
rethods of qualifying line-mounted devices, and the use of actual seismic j' experience data bases to qualify identical or similar equiprent. These issues ll have been covered by the latest national Standard IEEE Std 344-1987, which ,i reflects the state-of-the-art technology. The hRC staff has carticipated in the development of this Standaro. Further, the NRC has exte1ded the applica.
tion of this Standard to the qualification of mechanical equipment.
Specifically, this regulatory guide covers the following two categories of ,
equipTent: (i) safety-related electric (Class IE) equipment and safety-related ;;
mechanical ecuiprent, and (11) equipment whose failure can prevent the iI satisfactory acconplishment of safety functions. Examples of rechanical !l ecuipment and equipment supports within the scope of this guide are: valves, valve crerators, purps compressors, chillers, air handlers, fans, blowers, !
pipe supports, snubbers, restraints, hangers, fuel rod assemblies, and control l,l rod drive rechanisms.
l IEEE Std 344-1987 references other standards that contain valuable >
I l infomation. Dose referenced standards not endorsed by a reculatory guide or l
incorporated into the regulations, if used, are to be used in a manner consis-I tent with current regulations.
Draft 4 3 December 4,1986 l
C. REGillAT')RY POSi fION 1 The procedures described by IEEE Std 344-1987, "Reccuended Practicos for Set smic Cualification of Class IE Equipment for Nuclear power bentrating Sta. I tions," are acceptable to the NRC staff for satisfying the Corsnission's regula- ,
tions pertaining to seismic oualification of electric and mechanical equipment subject to the follcwing:
- 1. For mechanical equipment, thermal distortion effects on ocerabilicy should be considered and loads imposed by the attached piping should also be accounted for.
If dynamic testing of a purp or a valve asserbly is 'mpracticable, static ,
testing of the assembly is acceptable provided that (1) the end loadings are applied and are equal to or greater 'han, postulated event loads. (?) all !
dynamic amplification effects are accounted for. (3) the component is fn the !
operating rode during and after the application of luads, and (4) a* adequate analysis is r.ade 'o show the validity of the static applicstion of 1 cads.
- 2. Section 9 of IEEE Std 344-1987 recognizes % use of emptrience data as a method for seismic qualification. This rethod of qualifdcation should be '
apropriately justified and will be evaluated by the NRC staff on a case by-case basis.
D. IMPLEMENTATION j'
The purpose of this section is to provide inforr.ation to applicants and !
licensees regarding the hPC staff's plans for using this regulatory guide. !
Except in those cases in which the applicant or licensee proposes an acceptable alternative rethod for corplying with specified portions of the l'
i-Comenission's regulations, the rethods described herein will be used in the l
Draft 4 4 D3cember a.1986 1
evaluation of seismic qualification of electric and mechanical equipment for nuclear power plants as follows:
(1) Plants for which the co'1struction pennit is issued after the issue date of this guide.
(?) Plants for which the operating license application is docketed 6 months or more after the issue date of this guide.
(3) Plants for which the applicant or licensee voluntarily comits to the provisions of this guide.
VALUE/ IMPACT STATEMENT I BACKGROUND ,h l
IEEE Std 344-1975, "IEEE Recomended Practices for Seismic Qualification of Class IE Equipent for Nuclear Power Generating Stations," was approved by 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 IEEE in developing IEEE Std p 344-1987. As a result of these efforts, the exceptions to IEEE Std 344-1975 l have been satisfactorily resolved. ;
l' IEEE Std 344-1987 also addresses several recent technical issues, for example. l, treatment of hydrodynamic loads, the limits of generic testing, the treatment !.
of rattling, rethods of qualifying line-mounted devices, and the use of actual f
l i
i Draft 4 5 December 4, 1986 '
r seismic experience data bases to qualify identical or similar equipment. IEEE Std 344-1987 thus reflects the state-of-the-art technology.
Issuance of this Proposed Revision 2 is consistent with the NRC policy of evaluating the latest versions of national standards in terms of their suit-ability for endorsement by regulatory guides.
SUBSTANTIVE CHANGE 3 AND THEIR VALUE/ IMPACT IEEE Std 344-1987 applies to seismic and dynamic qualification of Class 1E (safety-related electric) equipment. 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 covers the following two categories of equipment: (i) safety-related electric (Class IE) equipment and safety-related mechanical equipment, and (ii) equipment whose failure can prevent the sattsfactory accomplishment of safety functions. Regulatory Posi-tion C.1 is included to provide juidance for qualification of mechanical equip-ment. This guidance is consistent with current NRC practices.
Regulatory Position C.2 recognizes the use of experience data as a method of seismic qualification. This method should be appropriately justified and will be evaluated by the NRC staff on a case-by-case basis.
Pegulatory Positions C.1 to C.4 in Revision 1 are not included in this Proposed Revision 2 because they are incorporated in IEEE Std 344-1987 as follows:
Regulatory Position Number Section Number Rev. 1 of this Guide (IEEE Std 344-1987)
C.1 6.3 C.2 7.6.2.1 C.3 7.6.2.5 C.4 10.3.2(6)
Draft 4 6 December 4, 1986
VALUE This guide endorses the latest version of a national standard and reflects the current state-of-the-art technology. The guide should also enhance the licensing process.
IMPACT Although the scope of this revision has been extended to include seismic qualification of mechanical equipment, the requirements are consistent with NRC current licensing practice. Thus, this regulatory guide does not impose I any new reqJirements or Costs on licensees or applicants. i it Il i
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Draft 4 7 December 4,1986 1
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Contact:
S. K. Aggarval (301) 443.Jjelf REGULATORY GUIDE 1.100 (TaskEE108-5) ,
s SCfA/C AND Nf'NA##bl~
SEISNIC)@t(MM9 QUALIFICATION OF A$$$h$$$6tgi EQUIPMENT FOR NUCLEAR POWER PLANTS A. INTRODUCTION .
The Comission's regulations in 10 CFR Part 50, "Domestic Licensing of .
Production and Utilization Facilities," require that certain structures,
. systems, and components in a nucleqr power plant be designed to withstand the effects of natural phenomena such as earthquakes, and that design control F measures such as testing be used to check the adequacy of design. This general requirement is contained in Appendix A, "General Design Criteria for Nuclear Power Plants," to Part 50; in Criterion III, "Design Control," and Criterion }l XVII, "Quality Assurance Records" of Appendix B. "Quality Ass,urance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to Part 50; and Appendix A. "Seismic and Geologic Siting Criteria for Nuclear Power Plants," to ,
l Part 100. l Appendix A to 10 CFR Part 100 Section VI, "Application to Engineering Design," requires that the nuclear power plant shall be designed so that, if the Safe Shutdown Earthquake occurs, certain structures, systems and compone '.s will remain functional. These safety-related structures, systems, and com-ponents are those necessary to assure (1) the integrity of the reactor coolant pressure boundary, (ii) the capability to shut down the reactor and maintain it in a safe condition, or (iii) the capability to prevent or mitigate the conse-quences of accidents which could result in offsite exposures cowparable to f
Nnember fodfs4 Draft 1 My i, 1966'
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the 10 CFR Part 100 guidel e @
structures, systems, and c p :e5 ary r con nue operation ei e j
nuclea= rre 4 eM 1 without undue risk to the health and safety of the public shall be designed to remain functional and within applicable stress and deformation limits when subjected to the effects of the vibratory inotion of the Operating Basis Earthquake in combination with nortnal operating loads. It is also required that the engineering method used to ensure that the required safety functions are maintained during and af ter the vibratory ground motion associated with the Safe Shutdown Earthquake or Operating Basis Earthquake, shall involve the use of either a suitable dynamic analysis or a suitable 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 the Comission's regulations with respect to seismic - ' i-rm ;c.
qualification of electric and mechanical c ' ; ._'. J equipment.
B.iDISCUSSION IEEE Std. 344-198f "Recomended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations," dated ,
was prepared by Working Group 2.5 (Seismic Qualification) of Subcomittee 2 (Equipment Qualification) of the Institute of Electrical and 1:lectronics Engineers (IEEE) Nuclear Power Engineering Cccinittee, and was subsequently approved by the IEEE Standards Board on .
1This guide is being developed in parallel with tng revision of IEEE Std. 344.
It is anticipated that the printed copies of the 3tandard will be available prior to issuance of the proposed revision to the guide for public coment.
Draf t 3 of RG 1.100, Rev. 2 is based on an advance copy of the approved jtandard.
ff l Draft 2 J uly-? [
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I The provisions of the IEEE Standard include principles, procedures, and niethods of seismic qualification which, when satisfied, will confirm the J 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 purposes of this guide, the design basis events are the loadings imposed by seismic events:
the Operating Basis Earthquake (0BE), and the Safe Shutdown Earthquake (SSE).
It is also necessary to combine other dynamic or vibratory loads as part of seismic qualification. It is recognized that hydrodynamic loads have their primary energy content in a frequency range greater than that of seismic vibrations. Howver, they are a part of the in-plant equipment aging process, along with other non-seismic vibration loads, and, as such thould be considered ,
in seismic testing.
Rev.1 of this guide was issued in August 1977. Several new technical issues have since arisen. Examples of these issues are: treatment of hydro-dynamic loads, the limits of generic testing, the treatment of rattling, methods of qualifying line-mountedI devices, and the use of actual seismic experience data bases to qualify identical or similar equipment. These issues have been covered by the latest national standard IEEE Std 344-1987,which reflects the state-of-the-art technology. The NRC staff has participated in the develonnent of this htandard. Further, the NRC has extended the applica-tion of this $tandard %%-Mifttf;t'bt)d%Ft#mpr)pspjp to the qualifi-cation of 4(eppfg4f44 mechanical equipment.) Examples of mechanical equipment and equipment supports within the scope of this guide are: valves '
e"'- --1:c N-Ef*M, valve operators, pumps, compressors, ,
chillers, air handlers, fans, blowers, pipe supports, snubbers, restraints, j ,
hangers, fuel rod assemblies, and control rod drive mechanisms.
\
IEEE Std 344-198 references other standards that contain valuable infonnation. Those referenced standards not endorsed by a regulatory guide or incorporated into the regulations, if used, are to be used in a manner consistent with current regulations. ,
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C. REGULATORY POSITION The procedures described by IEEE Std 344-198 . "Recomended Practicas for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations," are acceptable to the NRC staff for satisfying the Comission's regulations pertaining to seismic eedWassem4e qualification of electric and mechanical ne#sy:ankt255 equipment subject to the following:
1.
For mechanical equipment, thegdistortion effects on operability should be considered h 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 ssembly is acceptable provided that (1) the end loadings are
.cameown9sutp applied end 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 du' ring and after the application of loads, and (4) an adequate analysis is made to show the validity of the static application of loads.
- 2. Section 9 of IEEE Std 344-198frecognizestheuseofexperiencedata as a method for seismic qualification. This method of qualification thould be appropriately justified and will be evaluated by the NRC staff on a case-by-case basis.
D. IMPLEMENTATION The purpose of this section is to provide inforination 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 ,
Cossnission's regulations, the methods described herein will be u' sed in the
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evaluation of seismic mnKdg$fdp qualification of electric and mechanical !
Qad equipment for nuclear power plants as follows: '
(1)
Plants for which the construction perinit is issued after the issue date of this guide.
(2)
Plants for which the operating license application is docketed 6 inunths or more after the issue date of this guide.
(3)
Plants for which the applicant or licensee voluntarily comits to the provisions of this guide.
- YALUE/ IMPACT STATEMENT BACKGROUND IEEE Std 344-1975, "1EEE Recocnended Practices for Seismic Qualification of
- Class 1E Equipment for Nuclear Power Generating Stations," was , approved by 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 IEEE in developing IEEE Std 344-19 a result of these efforts, the exceptions to IEEE Std 344-1975 have been satisfactorily resolved.
IEEE Std 344-19h also addresses several recent technical issues, for example, treatment of hydrodynamic loads, the limits of generic testing, the treatment of rattling, inethods of qualifying line-mounted devices, and the use of actual 1
Nwaak /6 l'196 Ofrff 5
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I IEEE seismic experience data bases to qualify identical or similar equipment.
Std 344-198[thus reflects the state-of-the-art technology.
Issuance of this Proposed Revision 2 is consistent with the NRC pol, icy of evaluating the latest versions of nationaletGup standards in terms of their suitability for endorsement by regulatory guides.
SUBSTANTIVE CHANGES AND THEIR VALUE/ IMPACT ad dfMn'iC Ons fE ggf IEEE Std 344 applies to seismic 4 qualification ofdafety-related) electric equipment. Thenuclearindustryhasusedthisdtanderdforseismicqualifi-cation of sW4fpffD$e# mechanic:;l equipment as well. .ne NRC staff recognizes this fset and intends to extend the application of thishtandard to seismic qualification of s%fkfy.tyalAtpg mechanical equipment by this regulatory
- guide.] Regulatory Position C.1 is included to provide guidance for qualifica-tion of mechanical equipment. This guidance is consistent with current NRC j
practicas.
Regulatory Position C.2 recognizes the use of experience data as a method of seismic qualification. This method should be appropriately justified and will be evaluated by the NRC staff on a case-by-case basis, op .
Regulatory Positions C.1 to C.4 in Revision 1 )ser(not included in this 7 (e incorporated in IEEE Std 344-192)[as Proposed Revision 2 because they follows:
Section Number Regulatory Position Number ;
Rev.1 of this Guide flEEEStd 344-1981 6.3 C.1 7.6.2.1
.2 7.6.2.5
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4 10.3.2(6) F \
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Y l This guide endorses the latest version of a national standard and reflects the current state-of-the-art technology. The guide should also enhance the licensing process.
{l IMPACT Although the scope of this revision has been extended to include seismic qualification of mechanical equipment, the requirements are consistent with.bl(
NRC cu- ent licensing practice. Thus, this regulatory guide does not impose any new requirements or costs on licensees or applicants. " ' - - - - + ' "
. zivi t f re.T. f::e:re of th'.; W A i
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