ML20003H826
| ML20003H826 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1976 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.029, REGGD-1.029, TAC-51587, NUDOCS 8105070509 | |
| Download: ML20003H826 (3) | |
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ReWsion 2 U.S. NUCLEAR REGULATORY COMMISSION February 1976 REGU LATORY GUIDE OFFICE OF STANDARDS DEVELOPMENT P00R ORIGINAL REGULATORY GUIDE 1.29 SElSMIC DESIGN CLASSIFICATION A. INTRODUCTION nuclear power plants that should be desiped to with.
stand the effects of the SSE.
.f..
General Deup Cn.erion 2. " Design Bases for Protec.
B. DISCUSSION tion Against Natural Phenoment." of Appendix A,
" General Design Catena for Sticicar Power Plants," to
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10 CFR Pars 50,"'scensmg of Producuen and Utiliza.
Afte rmwing a Qet obpph:ations for con-struction percuts a:HI opets:ng'henses for boiling and tion P.cihties," r: quires that nuclear power plant pressunzed wate:fu:laar power plants, the NRC staff structures. system' and componentsimportant to safety has developed a sv.laetc da:p classiticauon system for be designed to ithstand the effects of earthquakes idenutying those plantjestures that should be desiped uthout loss of.apabihty to perform their safety to withstandethe'v!.fect'i of the SSE. Those structures.
t un ctions.
4 systeme,' and c,ompcments that snould be desiped to remairnfunctiona! if the SSE occurs have been desig-Appendix B..'Quahty Assurance Cntena for b.uclear ni.6 as SticudCategory 1.
Power P' ants and Fuel Reprocessmg Plants, to 10 CFR v
Part 50 estabhshes quahty assurance requirements for C. REGUI.ATORY POSITION the design, construction and operation of nuclear power (41%
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plaat structures, ssstems. and components that prev.ent %
1."T' he following structures, systerns, and compo-4 or mityate the cunsequences of postulated aceden nents of a nuclear power plant,includag their founda.
that could cause undue nsk to the health and safety of tions and supports, are desipated as Seistruc Cateaory I the public. The pertinent requirements of Ar' and should be designed to withstand the effects of the apply to all activaces affecting the safetv ed uons of those structures, systems, and co.-
SSE and remam funcuonal. The periment quality nentsd assurance requirements of Appendix B to 10 CFR Part 50 should be appbed to all a:tivines affecung the AppNdix A... Seismic and Geologi: SiA itena sarety-related functions of these structures. systems,and for Nuclear Power Plants." to 10 CFR Pait 100, components.
" Reactor Site Cntena." requi.:as that all ruclear power plants be designed so th,st. if _the Safe ShutdowTi
- a. The reactor coolant pressure boundary.
Earthquake (SSE) occurs.%Qtr9etwes, systems, and components importarg,to uCety ' remain fur.:tional.
These plant featurge are these wecessary to ensure (1)
- b. The reactor core and reactor vesselinternals.
the integnty of theueactottoolant pressure boundary, (2) the capab@fy tJIhat dan the rea: tor and maintain
- c. Systems or poruons of systems that are it in a safe shcidoom cc rdition. or (3) the capability to required for (1) emergency core coohng. (2) postacc2 present or mhigate the consequences of accidents that dent containment heat removal, or (3) postaccident could result m pblactial offsite exposures comparable to the guidehne exposures of 10 CFR Part 100.
'The system boundary includes those portions of the system requtred to accomphsh the spec 6cd safety function and connected piping up to and includtng the first valve (tnclud:ng a his gu:de desenbes an a:ceptable method ofidenU*
safety or relief valvei that ts either normaUy closed or capatde t
fytng and classifying those features of hght. water cooled of aatomatic closure when the safety func*.gon is required.
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P00R ORIGINM centamment atmosphere c!canup (e.g.. hydrogen re-
- n. The control room,includmg its' associated vital moval system).
equipment, cooling systems for ntal equipment, and life support systems, and any structures or equipment insirle
- d. Systems, or portions of systems that are o, outside of the control room whose failure could result required for (1) reactor shutdov n. (2) residual heat n incapacitating injury to the occupants of the control removal, or (3) cochng the spent fuel s:orage pool.
room.2
- e. Those portions of the steam systems of boiling
- o. Pnmary and secondary reactor cor.taintnent.
water reactor: extendmg from the outermost contain.
ment nelation valve up to but not meludmg the tu3ine stop salve, and connected pipmg of 21/2 ii.ches or
- p. Systems,' other than radioactive waste rnanage. }.
larger nanunal pipe size up to and including the first ment systems,3 not covered by items 1.a through 1.o I valve that is estrier normally civied or capable of above that contain or may contain radioactive material automatic closure dunng all modes of norrnal reactor and whose postuhted fallare would result in conserva-operanon. The turbine stop valve should be designed to tively calculated potential offsite doses (usmg mete.
withstand the SSE and mamtun its mtegnty.
orology as presenbed by Regulatory Guide 1.3, "As-sumptions Used for Evaluatmg the Potential Radio-
- f. Those portions of the steam and feedwater logical Consequences of a Los: of Coolant Accident for systems of pressurized water reactors extending from Bothng Wter Reactors," arid Regulatory Guide 1.4, and includme tu secondary side of steam generators up
" Assumptions Used for Evaluatmg the Potential Radio-to and ircluding the outermust containment isolation lopcal Consequences of a Loss of Coolant Accident for valves, and connected pipmg of 21/2 inches or larger Pressunzed Water Reactors") that are more than 0.5 rem norrunal pipe size up to and including the first valve to the whole body or its equivalent to any part of t!ie (mciudmg a safety or rebef valve) that is either normally
- body, closed or capable of autematic closure dunn; all modes of normal reactor operauon.
- q. The Class IE electne systems, includmg tne p Cooline water, component coolmg, and auxil.
auxihary systems for the onsite electne power supphes, sary feedwater ' systems' or portions of these systems, that prowde the emergency electric power needed for includmg the mtake structures, that are required for (1) functioning of plant features included in items 1.a O
emergency core cooling, (2) postaccident contamment through 1.p above.
heat removal.,(3) postaccident containment atmosphere cleanup, (1) residual heat removal from the reactor, or
- 2. Those portions of structures, systems, or compo-(5) coohng the spent fuel storage pwl.
nents whose continued function is not required but whose failure could reduce the functioning of any plant i
- h. Cochng water and seal water systems or feature included in items 1.a through 1.q above to an portions of these svstems that are required for function-unacceptable safety level should be designed and con-mg of reactor coolant system components important t structed so that the SSE would not cause such failure.
safety,such as reactor coolant pumps.
- i. Systems' or portions of systems that are re-
- 3. Seismic Category I design requirements should quired to supply fuel for emergency equipment.
extend to the first seismic restraint beyond the def'med boundaries. Those portions of structures, systems, or
- j. All electnc and mechanical devices and circuitry components that form interfaces between Seismic Cate-between the process and the mput terrrunals of the gory I and non Seismic Category I features should be actuator systems mvolved in generating signals that designed to Seismic Category I requirements.
imtiate protective action.
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- 9"
- k. Systems' or portions of systems that are Appendix B to 10 CFR Part 50 should be applied to all required for (1) monitonng of systems important to activities affectmg the safety related functions of those safety and (2) actuation of systems important to safety, portions of structures, systems,and components covered
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- 1. The spent fuel storage pool structure,includmg the fuel racks.
- l.mes mdacate substantive changes from previous issue.
- m. The reactivity control systems. e g.. control
'Wherever practical, stru:tures and equipment whose fadute rods, control rod dnves, and boron mfecuon system.
could possibly ca me such insunes should be relocated or separated to the estent reqared to ettmtnate this possibdity.
' Specific guidance on seisnac requuements for radioact we saste
'See footnote 1, p.1.291 management systems is under development.
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P00R ORIGINAL
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O. IMPLEMENTATION proposes an acceptable alternative method for comp ly-The purpose of this section is to provide information ing with specified portions of the Comnussion's regula-to applicants regardmg the NRC staff's plans for using tions, the method described herein is being and will continue to be used in the evalua 5n oisubtruttais for th:s regulatory guide.
operating license or construction pernui applications Tlus guide reflects current NRC staiT practice.There-until this guide is revised as a result of sugestions from fore, except in those cases m which the applicant the public or additional staff review.
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