ML19246A282

Reg Guide 1.29,Revision 3, Seismic Design Classification

ML19246A282
Person / Time
Issue date:	09/20/1978
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
7590-01, 7590-1, REGGD-01.029, REGGD-1.029, NUDOCS 7810030052
Download: ML19246A282 (3)

Text

Revision 3

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U.S. NilCLEAR REGULATORY COMMISSION September 1978 e Af) REG L LATO RY Ga 3E

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OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1.29 SEISMIC DESIGN CLASSIFICATION A.

INTRODUCTION tures of light-water-ccoled nuclear power plants that should be designed to withstand the ef fects of the General Desiga Criterion 2,

' Design Bases for SSE The Adsisorv Committee on Reactor 1

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I Protection Against Natural Phenomena, of Appen-Safeguards has been consulted regarding th's guide dis A, " General Design Criteria for Nudear Power and has concurred in the regulators position.

I Pian t s, to 10 CFR Part 50, ' Domestic 1 icensmg of Production and Utilization Facilities, requires B.

DISCUSSION that nuclear power plant structures, ss stems, and Atter resiewing a number of applications f or con-components important to sately be designed to with-struction permits and operating licenes for boiling stand the ellects of. earthqual cs without low of. capa-and prewurued water nuclear power plants, the NRC bihty to peitorm their safety f, unctions.

statt has deseloped a seismic design classification Appendis B, "Qw"r> Assurance Criteria kr Nu.

vtem for identif ying those plant features that should clear Power Plants and r:uel Reprocessing Plants, ' to be designed to withstand the effects of the SSE.

10 CFR Part 50 establishes quality awurance re.

Those structures, sy stems, and components that quirements for the design, construction, and opera-should be designed to remain f unctional if the SSE tion of nucaar power plant structures, sy stems, and occurs base been designated as Seismic Category 1.

components that prese.a or miti" ate the consequences of postulated accidents that could cause undue risk to C.

REGULATORY POSITION the health and saf ety of the public. The pertinent re-

1. The following structures, sy stems, and compo-

@ quirements of Appendis B apply to all actisities at-nents of a nuclear power plant, including their foun-tecting the saf ety-related functions of those struc-dations and supports, are designated as Seismic Cate-tures, sy stems, and com;mnent' gory I and should be designed to withstand the effects Appendix A,

' Seismic and Geolucic Sitin e of the SSE and remain functional. The pertinent qual-Criteria for Nuclear Power Plants, to 10 CFR pat ity assurance requirements of Appendix B to 10 CFR Part 50 should be applied to 'll actisities af fecting 100, ' Reactor Site Criteria, requires that all nu-clear power plants be designed so that, if the Sate the safety-related functions o' these structa : sy s-Shutdown Earthquake (SSE occurs, certain struc_

tens and mnponents.

tures, sptems, and components remain functional.

a. The reactor coolant pressure boundary.

T hese plant tes'. ares are those necewary to ensure (1)

b. The reactor core and reactor sessel inte;nals.

the mtegrity of the reactor coolant pressure boundary, (2> the capability to shut down the reactor and main-

c. Sy stems ' or portions of sy stems that are re-tam it in a safe shutdow n condition, or di the caPd-quired for (1) emergency core cooling, (2) postacci-bihty to present or mitigate the cor sequences of ac-cidents that could result m potential of fsite exposures

.t mes micate substantne changes from preuous swue con, parable to the guideline exposures of 10 CFR i ne y uem boundary imcludes ihose ponions of the Pr m re-e Part 100.

h qmred to accon7 sh the speciheJ sarety funcnon anJ connected pTmg up to ard indumng the hrst s abe sincluJmg a safety or This guide describes a method acceptab,e to the eer uhei ihai n enher norma > hed or cambre or automanc l

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dent cont onment heat removal, or 0) postaccident The control room, including its associated containment atmosphere cleanup te p.

hydrogen re-equipment and all equipment needed to maint.un the moul sy stem).

control room within safe habitabihty limits for P" " " " " # ' "" "

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d. Sy stems ' or portions of sy sterns that are re-

1. 4

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quired for i1) reactor shutdown,121 residual heat re-mosal, or di cooling the spent tuel storage pool' Primary and secondary reactor contamment.

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e. T hose portions of the ste..,n ss stems of boil-ine water reactors extendine f rom the outermost con-

p. Sy en other than raJioactn e w aste man-tainment isolation uhe up to but not includine the agement sy stems, not cosered by items 1.a through turbine stop vahe, and connected pipine of 25 I o abow that contain oc may contain radioactne ma-inches or larger nonunal pipe i/e up to and includine teri d and whose postulated f ailure would result in the tint sabe that is either normally closed or capal conu n inwly calculated potennal of fsite doses t us-b'e of automatic closure durine all modes of normal ing ineteorology as recommended in Regulatory Guide 13, ' A ssu mption s ll sed f or Es aluating the reactor operation. T he turbine stop s abe should be designed to withstand the SSE and maintain its Potential Radiologi..al Consequences of a 1.o s s of Coolant Accident for Boiling Water Reacton, and integnts.

Regulatory Guide 1.4,

• Ass u mptions l' sed f or

f. Those portions of the stea.n and feedwater Es aluating the Potential Radiological Consequences sy stems of pressurized water reactors cuending trom ot' a 1.oss of Coolant Accident for Pressurized Water and includmg the secondary side of steam generators Reactors 1 that are more than 0.5 rem to the w hole up to and incluJing the outermost containment nola-body or its equn alent to any part of the boJy.

t on ubes, and connected piping of 2'; mehes or larger nominal pipe size up to and including the first y The Class IE electric sy stems, including the une uncluding a saf ety or relief uhe) that is either au xiliary systems for the onsite electric power normally closed or capable of automatic closure dur-supplies, that proside the emergency electne power mg all modes of normal reactor operation needed for lunctioning of plant f eatures included in items 1.a through I p abose.

g t,ooling w ater, component cooling, and auxiliary f eedw ater sy stenn ' or portions of these s)*

2. Those portions of structures, sy stems, or com-tems including the intake structures, that are re-ponents whose continued funcuon is not required but quired f or (1) emergency core cooling (2) postacci-whose failure could reduce the functionine of ans dent containment heat remoul,13) postaccider,t con-plant f eature inclu1J in nems 1.a through l' y abo [e tainment atmasphere cleanup, (4) residual heat re-to an unacceptable safets lesel or could result in in-mos al from the reactor, or (5) coohng the spent fuel capacitatmg injury to occupants of the control room

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storage pool-shoulJ be desiened and constructed so that the SSE would not cause mch failure.'

h. Cooling water and seal water sy stems ' or portions of these systems that are required for f unc-1 S. ismic Category I design requirements should e

tioning of reactor coolant sy stem comp,nents impor_

to h' ty sciunm reuMn(f structures Mond the de-euen tant to saf ety, such as reactor coolant pumps.

tined boundaries. Those portions o

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i. Sy stems ' or portions of systems that are re-te m s, or components that f orm intert ices b( t w ee n quired to supply fuel f or emergency equipment.

Seismic Category I and non-Seismic Category I lea-tures shouhl be designed to Seismic Category I

j. All electric and mechanical desices and cir-requireme nt s.

cuitry between the process and the input ternunals of the actuator sy stems inghed in generating signals

4. The pertinent quality assurance requirements of that mitiate protectiu action.

Appendix B to 10 CFR Part 50 should be applied to k Sy stems or portions of sy tems that are re.

all actis ties attecting the safety-related lunctions of i

quired for il) monitoring of sy stems important to those pornons of structures, sy stem s, and compo-nents cosered under Regulatory Position s 2 and 3 saf ety and (2) actuation of sy stems impmtant to ahos e.

sa fety.

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The spent fuel storage pool structure, includ-ing the fuel racks g

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m The reacthity control sy sterns, e.g.

control 7%emem y wnn n wer JeseHmem O' h e f t's C T pf.1C f 1C JI, s!T U C l u TC % dflJ equ ipIf!eill W ho%e IJ1lUTC rods, control rod drives and boron injection a mm me d inpries shNIJ be reloued or sepa-sy stem.

reed to the cue"a repred to ch.nate thn podlay 142 277 m2

D.

IMPLEMENTATION cant Froposes an acceptable alternatise niethod f or complying with specified portions of the Conimis-Ihe purpose of this section is to pros tde in!'irnla-s t o 'l 's legulations, thC ulCthod desCrlbed hCrCin is 9 tion to applicants regarding the NRC stall's plans ior being and will continue to be used in the es aluation using this regul.a iry guide.

of subnuttals f or operating hcense or construction permit applications until this cuide is res ised as a re-I his guide retlects currevit NR(' stall practice sult of suggestions tront the public or aJditional stati I heref ore, euert in those cases in wluth the appli-re s iew 142 278

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(>f F ICI AL (3 U ', # '. I i. S u % M AIL Pt N AL T Y F OH PHIV A 7 f U S E. $ 100 0

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